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Volume 93 - Indira Gandhi Centre for Atomic Research

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ISSN 0972-5741 <strong>Volume</strong> 90 October 2011<br />

ISSN 0972-5741 <strong>Volume</strong> <strong>93</strong> July 2012<br />

IGCNewsletter<br />

IGCNewsletter<br />

IN THIS ISSUE<br />

Technical Articles<br />

• Per<strong>for</strong>mance Testing of Primary Ramp and Primary Tilting<br />

Mechanism of Inclined Fuel Transfer Machine<br />

of Prototype Fast Breeder Reactor<br />

• Science of Metal Nanoclusters<br />

Young Officer’s Forum<br />

• Design of Elliptical Heat Exchanger <strong>for</strong> Future Fast Breeder<br />

Reactors<br />

Young <strong>Research</strong>er’s Forum<br />

• Enhanced Transmission with Tunable Fano like Profile<br />

in Magnetic Soft Matter<br />

Conference/Meeting Highlights<br />

• Theme Meeting on Severe Accident Analysis and Experiments<br />

• Theme Meeting on Robust Instrumentation and Control <strong>for</strong><br />

Nuclear Facilities<br />

• Theme Meeting on Technological Advancement in Production<br />

of Enriched Boron <strong>for</strong> the Control Rods of Fast Reactors<br />

Visit of Dignitaries<br />

Awards & Honours<br />

INDIRA GANDHI CENTRE FOR ATOMIC RESEARCH<br />

http://www.igcar.gov.in/lis/nl<strong>93</strong>/igc<strong>93</strong>.pdf


From the Editor<br />

Dear Reader<br />

IGC Newsletter<br />

From the Editor<br />

It is my pleasant privilege to <strong>for</strong>ward a copy of the latest issue of IGC Newsletter (<strong>Volume</strong> <strong>93</strong>, July 2012 issue).<br />

In the Director’s Desk, Shri S. C. Chetal, Director, IGCAR has highlighted the contributions made by Chemistry Group towards<br />

supporting the fast reactor programme and closing the fuel cycle. The significant inputs provided by the Group in the last five years like<br />

fuel-fission product interaction studies, development of failed fuel detection system, production of useful radioisotopes, development<br />

of chemical sensors, decontamination and sodium cleaning studies, boron chemistry, cover gas purification system, studies related<br />

to fuel cycle with special emphasis on metallic fuel fabrication, separation studies, waste immobilization and other important research<br />

activities towards unravelling the basics in chemistry.<br />

Shri B.K. Sridhar and Shri S. Raghupathy have shared their experience on successful completion of the per<strong>for</strong>mance testing of primary<br />

ramp and primary tilting mechanism in air and sodium, and the effective in situ removal of sodium from primary ramp and primary<br />

tilting mechanism by water vapor and carbon dioxide process.<br />

In the second technical article, Dr. P. Gangopadhyay has discussed the Science of Metal Nanoclusters by analyzing and interpreting<br />

the results of the photoluminescence, optical absorption spectroscopy and Ruther<strong>for</strong>d backscattering experiments of silver ionexchanged/implanted<br />

soda-glass samples and Raman scattering spectroscopy of cobalt implanted silica samples.<br />

In the young officer’s <strong>for</strong>um, Shri V. Sudharshan gave an account of optimising the configuration of intermediate heat exchanger <strong>for</strong><br />

economy and designed an elliptical heat exhanger <strong>for</strong> future fast breeder reactors with design life of 60 years at 85% load factor.<br />

Dr. Junaid Masud Laskar, in the young researcher’s account, has presented the first experimental evidence <strong>for</strong> tunable fano resonance<br />

in magnetically polarizable soft matter system and explained the variation of different fano paramenters with external magnetic field on<br />

the basis of change in interference due to varying waveguide dimension and their dimensional distributions.<br />

This Newsletter carries reports on the Theme Meetings on “Severe Accident Analysis and Experiments", "Robust Instrumentation and<br />

Control <strong>for</strong> Nuclear Facilities” and “Technological Advancement in Production of Enriched Boron <strong>for</strong> the Control Rods of Fast Reactors”.<br />

Honorable Justice Shri S. Tamilvanan from Madras High Court and Prof. V. Manimozhi visited the <strong>Centre</strong> during the last quarter.<br />

We are happy to share with you the awards, honours and distinctions earned by our colleagues. We look <strong>for</strong>ward to your feedback,<br />

continued guidance and support.<br />

With my best wishes and personal regards,<br />

Yours sincerely,<br />

(M. Sai Baba)<br />

Chairman, Editorial Committee, IGC Newsletter<br />

&<br />

Associate Director, Resources Management Group


From the Director's Desk<br />

Director’s Desk<br />

IGC Newsletter<br />

Chemistry Programme at IGCAR<br />

The importance of chemistry as a key discipline in the<br />

development of fast reactor technology and the fuel cycle was<br />

recognised by our department in the very early stages of the<br />

fast reactor programme. The Radiochemistry Laboratory (RCL)<br />

was one of the first set of laboratories built at IGCAR. At that<br />

stage, the chemistry laboratory was intended to provide support<br />

<strong>for</strong> the development of the fast reactor programme through R&D<br />

activities related to fuel materials, liquid sodium and other alkali<br />

metals, and the fuel cycle <strong>for</strong> fast reactor. Over the years, the<br />

Chemistry Group (CG) has not only met this mandate, but also has<br />

provided key technological inputs to several other aspects of the<br />

fast reactor programme. The work on plutonium chemistry was<br />

initiated in the year 1983. The historical evolution of the chemistry<br />

programme at IGCAR and the contributions of CG in the first 25<br />

years were covered in the article that appeared in the newsletter<br />

in April 2005. In the present article, I have focused more on the<br />

achievements of CG in the subsequent period, while providing<br />

some idea of the earlier work in order to present a comprehensive<br />

perspective.<br />

CONTRIBUTIONS TO FBTR<br />

The Chemistry Group provided key inputs to the decision on the<br />

composition of the carbide fuel <strong>for</strong> FBTR. The knowledge base<br />

on the thermochemical properties of the fuel and fission product<br />

systems, and the strengths in thermochemical modeling were<br />

instrumental in arriving at an understanding of the chemical<br />

state of the carbide fuel at high burn-up. This was particularly<br />

necessary <strong>for</strong> extension of the burn-up of FBTR fuel beyond<br />

150 GWD/t. The equilibration experiments carried out to study<br />

the chemical interaction of (U 0.56<br />

Pu 0.44<br />

)O 2-x<br />

with liquid sodium<br />

were useful in obtaining safety clearance <strong>for</strong> the introduction of<br />

plutonium rich oxide fuel in FBTR.<br />

Chemistry Group was also responsible <strong>for</strong> the characterization<br />

of the sodium that was charged into FBTR and the chemical<br />

characterization of various structural materials. Over the years,<br />

the group has continued to provide characterization support<br />

<strong>for</strong> the sodium coolant in FBTR. Various impurities in sodium<br />

have been measured periodically, and gamma spectrometry<br />

measurements have been carried out on radioactive sodium from<br />

the primary sodium loop of FBTR.<br />

The Chemistry Group was involved in the development of a failed<br />

fuel detection system <strong>for</strong> FBTR, based on the measurement of<br />

Kr 87 /Kr 85 and Kr 88 /Kr 85 ratios in the cover gas by gamma<br />

spectrometry. This development proved to be crucial in the<br />

localization of the failed fuel in FBTR, in the first incidence of<br />

carbide fuel pin failure. The measurement of the krypton isotope<br />

ratios combined with the reactor power history led to an estimate<br />

of the age of failed fuel and burn-up of the breached sub-assembly.<br />

The age of the failed fuel computed from Cs 136 /Cs 137 ratio present<br />

in primary sodium confirmed this measurement.<br />

In the recent past, the CG has also started a programme to utilize<br />

FBTR <strong>for</strong> the production of societally beneficial radioisotopes. As<br />

a part of this programme, Sr 89 , a beta emitter used <strong>for</strong> alleviating<br />

pain in bone cancer patients, was produced in FBTR through<br />

the irradiation of yttria. CG has demonstrated the separation of<br />

Sr 89 from the irradiated yttria in the hot cells and its subsequent<br />

purification by ion-exchange. Characterisation of the Sr 89 is now<br />

in progress, and in the near future, the process know-how would<br />

be passed on to the Board of Radiation and Isotope Technology.<br />

CONTRIBUTIONS TO PFBR AND FUTURE FAST REACTORS<br />

Chemical Sensors<br />

The development of electrochemical meters <strong>for</strong> monitoring<br />

hydrogen, carbon and oxygen in sodium has been a major<br />

highlight of the contributions of CG. In particular, the development<br />

of the Electrochemical Hydrogen Meter (ECHM) to detect water-<br />

1


IGC Newsletter<br />

Figure 1: Electrochemical hydrogen meter ECHM<br />

steam leak in the steam generator at the incipient stage is one<br />

of the excellent contributions from the CG. Several versions<br />

of these meters were fabricated and tested <strong>for</strong> their long term<br />

per<strong>for</strong>mance in bench top loops as well as in large sodium loops<br />

in the <strong>Centre</strong>, and FBTR. This development had demanded<br />

several years of basic studies on various electrolyte systems<br />

including their phase diagrams and electrical conductivity<br />

measurements. This work has finally resulted in a robust ECHM<br />

(Figure 1) that can measure a change in ~ 10 ppb of hydrogen in<br />

sodium in a background of around 50 ppb. One hydrogen meter<br />

has been installed in the PHENIX reactor in France as a part of<br />

the collaboration programme between IGCAR and CEA, and its<br />

per<strong>for</strong>mance was as good as that of the hydrogen meter based<br />

on mass spectrometer. The excellent per<strong>for</strong>mance of the ECHM<br />

has provided us confidence to introduce the same as the primary<br />

steam generator tube leak detection system in the PFBR.<br />

A diffusion based hydrogen detection system has been developed<br />

to monitor the hydrogen concentration in the argon cover gas<br />

during start up or low power operation of the fast reactor. Four<br />

units of this system are now being fabricated <strong>for</strong> integration<br />

in PFBR. An electrochemical meter <strong>for</strong> the measurement of<br />

carbon activity in sodium has also been developed. The activity<br />

of carbon measured by this meter has been compared with<br />

the data obtained by foil equilibration measurements. From the<br />

temperature response of the cell the nature of carbon species<br />

in molten sodium was also evaluated. For the measurement of<br />

oxygen in sodium, a yttria doped thoria (YDT) solid electrolyte<br />

based electrochemical sensor has been developed and is<br />

undergoing tests in various loops.<br />

Chemistry Group is also engaged in the development of compact<br />

chemical sensors <strong>for</strong> a wide variety of other applications, besides<br />

basic research on sensor materials and sensing processes.<br />

Sensors based on thin films of semiconducting oxides (eg. tin<br />

oxide) have been developed. Thin film hydrogen sensor based<br />

on tin oxide has extended the detection limit of the hydrogen<br />

detection system <strong>for</strong> cover gas (based currently on Thermal<br />

Conductivity Detection) down to a few vppm. The sensor has<br />

per<strong>for</strong>med satisfactorily in different engineering scale facilities of<br />

our <strong>Centre</strong> <strong>for</strong> more than five years. Promising semiconducting<br />

oxide <strong>for</strong>mulations have also been identified <strong>for</strong> sensing oxides<br />

of nitrogen (NOx), oxygen, ammonia and hydrogen sulphide. The<br />

sensor systems will be useful <strong>for</strong> the reprocessing plants, reactor<br />

operating areas and heavy water production plants.<br />

Cleaning of Sodium Wetted Components<br />

Components exposed to liquid sodium in coolant circuits of fast<br />

reactors need to be cleaned free of sodium when removed from<br />

coolant circuits <strong>for</strong> periodic maintenance or replacement. A water<br />

vapour-CO 2<br />

process <strong>for</strong> cleaning sodium from reusable large<br />

components has been studied at CG. A pilot plant (Figure 2) was<br />

constructed and the sodium cleaning experiments carried out in<br />

the pilot plant showed that the cleaning process could be carried<br />

out in a controlled manner by manipulating injection of moisture<br />

into the reaction chamber. Accordingly, this process has been<br />

recommended <strong>for</strong> cleaning sodium wetted components of PFBR.<br />

Chemical and Electrochemical Decontamination<br />

A chemical decontamination method <strong>for</strong> primary components<br />

of PFBR using sulpho-phosphoric acid was standardized with<br />

inactive SS316LN specimens exposed to sodium. The process<br />

conditions such as chemical composition of the decontamination<br />

solution, temperature and the process time were optimized <strong>for</strong><br />

various sodium sensitized cold worked specimens. The chemical<br />

decontamination <strong>for</strong>mulation, evolved based on these studies has<br />

been recommended <strong>for</strong> decontamination of primary components<br />

of PFBR. An electrochemical brush decontamination method was<br />

also standardized <strong>for</strong> decontamination of hot spots of primary<br />

components of PFBR using SS316LN material, in collaboration<br />

with CECRI, Karaikudi.<br />

Boron Chemistry<br />

One of the important contributions of the Chemistry Group towards<br />

PFBR was the development of the technology <strong>for</strong> the production<br />

of elemental boron required <strong>for</strong> fabricating the absorber rods, in<br />

association with BARC and Heavy Water Board (HWB). Figure 3<br />

shows the pilot plant <strong>for</strong> elemental boron production. The process<br />

<strong>for</strong> the conversion of boric acid to potassium tetrafluoroborate<br />

(KBF 4<br />

) and its subsequent conversion to elemental boron through<br />

molten salt electrowinning route were optimized at the laboratory<br />

and the know-how transferred to HWB, which is presently<br />

engaged in regular production of elemental boron through this<br />

route. During this process, a few kilogram of pure enriched<br />

elemental boron was also produced and characterized and the<br />

Figure 2: Pilot plant <strong>for</strong> sodium wetted component cleaning: water<br />

vapour - CO 2<br />

process<br />

From the Director's Desk<br />

2


From the Director's Desk<br />

IGC Newsletter<br />

Figure 3: Pilot plant <strong>for</strong> elemental boron production<br />

material was sent to BARC <strong>for</strong> conversion to boron carbide. The<br />

group was responsible <strong>for</strong> the determination of B 10 /B 11 ratios in a<br />

large number of samples, generated during the development of<br />

the ion-exchange based enrichment process at IGCAR, and the<br />

determination of the ratio also in the boron produced at Manuguru<br />

as well as boron carbide fabricated at BARC. Experiments to<br />

assess the chemical compatibility of high-density boron carbide<br />

pellets with D9 clad material in the presence of sodium were also<br />

carried out.<br />

The Chemistry Group also set up a unique facility <strong>for</strong> measuring<br />

the isotopic ratio of boron in irradiated boron carbide pellets,<br />

using the home built reflectron time of flight mass spectrometry.<br />

Using this facility, the analysis of the isotopic ratio of B 10 to B 11 in<br />

the carbide pellets in the control rod of FBTR that was discharged<br />

from the reactor was measured. These data have provided<br />

important inputs about the feasibility of recycling of the enriched<br />

boron carbide.<br />

Cover Gas Purification System<br />

The cover gas purification system in PFBR uses activated charcoal<br />

at cryogenic temperatures to delay the passage of radioactive<br />

isotopes of krypton and xenon which ensures that they decay<br />

considerably be<strong>for</strong>e they are let out into the atmosphere. In<br />

collaboration with FRTG, CG has carried out the demonstration<br />

of the cover gas purification system on a pilot plant scale. The<br />

dynamic adsorption coefficient of charcoal <strong>for</strong> krypton and<br />

xenon was measured and the data have been used to arrive at the<br />

amount of charcoal required <strong>for</strong> the purification <strong>for</strong> PFBR.<br />

FAST REACTOR FUEL CYCLE<br />

In the Indian context, the fuel cycle of fast reactors pose many<br />

unique challenges. The first Indian experience of fast reactors<br />

was with high plutonium content mixed carbide fuel <strong>for</strong> FBTR;<br />

the PFBR would use mixed oxide fuel, while future fast reactors<br />

are expected to use metal alloys as the fuels. Thus, the group<br />

has engaged itself in the study of all these fuel systems as well<br />

as their fuel cycle aspects. In the recent past, the CG has been<br />

playing a key role in the development of fabrication routes <strong>for</strong> fuel<br />

Figure 4: Spot technique <strong>for</strong> measurement of solidus- liquidus<br />

temperature of fuel materials<br />

materials and also fabrication of test fuel pins in collaboration<br />

with BARC.<br />

Fuel Chemistry<br />

Chemistry Group has carried out thermophysical and<br />

thermochemical property measurements of a variety of fuel<br />

materials, fission product systems and compounds of alkali<br />

metals. Heat capacity and thermal conductivity data of U-Pu mixed<br />

oxides, carbides and nitrides, as well as oxygen potential over<br />

mixed oxide have been measured in the Chemistry Group. More<br />

recently, the novel “SPOT technique” (Figure 4) was established<br />

<strong>for</strong> the first time to measure the solidus liquidus temperatures<br />

of fuel materials. The U-Zr system was comprehensively studied<br />

using this technique. Ef<strong>for</strong>ts are now on to make measurements<br />

on the carbide fuel of FBTR and metal alloy systems.<br />

Fuel Cycle Chemistry<br />

In collaboration with BARC, CG has set up a unique lab scale<br />

facility <strong>for</strong> the fabrication of test fuel pins using fuel materials<br />

synthesized through SOL-GEL route. The fabrication of test fuel<br />

pins with (U 0.6<br />

Pu 0.4<br />

) mixed oxide is being pursued and the test<br />

fuel pins will be introduced in FBTR <strong>for</strong> irradiation in the coming<br />

months. The group has also demonstrated lab scale synthesis of<br />

U-Pu mixed oxide microspheres with 28% Pu, and U-Am mixed<br />

oxide microspheres with 5% Am.<br />

Extensive investigations were carried out on the extraction<br />

of actinides by tri-n-butyl phosphate (TBP) extractant used in<br />

the PUREX process <strong>for</strong> reprocessing and also other members<br />

of trialkyl phosphate family. A thorough investigation on the<br />

phenomenon of third phase <strong>for</strong>mation in the extraction of<br />

plutonium by TBP generated the understanding that was vital in<br />

the design of the process flow sheet in the reprocessing of fast<br />

reactor fuels. To avoid the possibility of third phase <strong>for</strong>mation,<br />

several other trialkyl phosphates and especially tri-isoamyl<br />

phosphate (TiAP) were investigated. Counter current liquid -<br />

liquid extraction experiment, carried out with TiAP solvent under<br />

the conditions simulating the PUREX process, has indicated<br />

satisfactory behaviour of the TiAP.<br />

3


IGC Newsletter<br />

From the Director's Desk<br />

Figure 5: The setup used <strong>for</strong> minor actinide<br />

partitioning in hot cell<br />

Figure 6: Mixer-settler facility used <strong>for</strong> flow<br />

sheet development studies with TiAP <strong>for</strong> fast<br />

reactor fuel reprocessing<br />

Figure 7: Supercritical fluid extraction facility in<br />

glove box <strong>for</strong> recovery of actinides from waste<br />

matrices<br />

The Chemistry Group has also been active in the area of minor<br />

actinide partitioning (Figure 5) from high-level liquid waste.<br />

The group has synthesized the extractant octyl(phenyl)-N,Ndiisobutyl<br />

carbamoyl methyl phosphine oxide (OΦCMPO) and<br />

carried out several extraction experiments with americium and<br />

other lanthanides such as neodymium. Recently, a typical high<br />

active waste arising from the reprocessing of the carbide fuel of<br />

FBTR irradiated to a burn-up of 155 GWD/Te was transported<br />

from the CORAL facility to RCL. A mixer settler run was carried<br />

out in the hot cells of RCL using the CMPO extractant, which<br />

established the recovery of over 99% of the minor actinides (Figure<br />

6). For this experiment, CG developed a complex <strong>for</strong>mulation that<br />

enabled the stripping of the actinides and lanthanides without the<br />

<strong>for</strong>mation of interfacial crud. The group has also synthesized<br />

novel and unsymmetrical diglycolamide and diglycolamic acid<br />

extractants. The extraction data on various solvent systems<br />

generated will be very useful <strong>for</strong> arriving at a partitioning scheme<br />

<strong>for</strong> the minor actinides from the high-level waste generated in<br />

fast reactor plants.<br />

Development of Glass and Ceramic Matrices <strong>for</strong> Radioactive<br />

Waste Immobilization<br />

Borosilicate glass is the accepted matrix world over, <strong>for</strong> the<br />

immobilization of the high-level radioactive liquid waste generated<br />

in nuclear fuel reprocessing. However, this matrix may have many<br />

limitations <strong>for</strong> the immobilization of high-level liquid waste from<br />

fast reactor fuel cycle. Chemistry Group has been carrying out<br />

a systematic study on alternate matrices to address this issue.<br />

Iron phosphate glass and crystalline synthetic rock (synroc)<br />

are examples of matrices that have been explored. Simulated<br />

waste <strong>for</strong>ms based on these two have been fabricated, and<br />

their thermophysical and thermochemical properties have been<br />

studied using a number of techniques. The matrices have also<br />

been subjected to rigorous chemical durability studies in order to<br />

evaluate their potential.<br />

Advanced Separations<br />

The Chemistry Group has also made several original contributions<br />

in the development of a variety of advanced separation techniques.<br />

The group has demonstrated high resolution, fast separation of<br />

individual lanthanides and actinides based on high-level liquid<br />

chromatography. In fact, CG was the first to demonstrate rapid<br />

separation of all the lanthanides using small particle columns and<br />

monolith columns. A separation time of 2.7 minutes <strong>for</strong> all the<br />

fourteen lanthanides achieved by the Chemistry Group is, as of<br />

now, the shortest reported in liquid chromatographic separation<br />

of the lanthanides. These techniques have been very valuable <strong>for</strong><br />

the determination of the burn-up of FBTR fuel with considerable<br />

reduction in analysis time and consequent reduction in the<br />

radiation dose to the operator.<br />

The Chemistry Group has also set up <strong>for</strong> the first time, a<br />

supercritical fluid extraction facility (Figure 7) inside the glove<br />

box <strong>for</strong> recovery of actinides from various waste matrices and<br />

was the first to demonstrate quantitative recovery of uranium,<br />

plutonium and americium from tissue waste, and a novel modifier<br />

free approach <strong>for</strong> application to systems where the extractant is a<br />

solid. The extraction procedure developed was demonstrated on<br />

actual waste generated in the fuel cycle operation.<br />

The Chemistry Group has also carried out pioneering work on the<br />

applications of room temperature ionic liquids (RTIL) <strong>for</strong> actinide<br />

and fission product separations. The use of RTILs as a diluents,<br />

extractant and electrolytic medium has been investigated. The<br />

Chemistry Group was the first to demonstrate the extraction<br />

and electrodeposition technique <strong>for</strong> the recovery of uranium and<br />

palladium from nitric acid medium. The electrowinning of uranium<br />

oxide by oxidative chlorination of the oxide to chloride <strong>for</strong>m in<br />

ionic liquid medium followed by electrodeposition as oxide was<br />

also demonstrated.<br />

Fuel Cycle <strong>for</strong> Metal Alloy Fuelled Fast Reactors<br />

Metallic fuels will be introduced in future commercial fast reactors<br />

in India to exploit their high breeding potential and enhance the<br />

growth of fast reactors in the country. Towards the development<br />

of the front end of the metal fuel cycle, IGCAR has taken up a<br />

programme in close collaboration with BARC to fabricate sodium<br />

4


From the Director's Desk<br />

IGC Newsletter<br />

a) b)<br />

Figure 8: Glove box train facility <strong>for</strong> sodium bonded metallic test fuel<br />

pin fabrication<br />

bonded and mechanically bonded test fuel pins and irradiate<br />

them in FBTR. A lab scale facility <strong>for</strong> fabrication of test fuel pins<br />

with sodium bonding has been set up by the Chemistry Group<br />

(Figure 8). U-Zr alloy slugs supplied by BARC have been<br />

encapsulated in the pins and currently six of these pins are now<br />

being irradiated in FBTR. It is now planned to take up fabrication<br />

of test fuel pin containing enriched U-Zr alloy and subsequently<br />

U-Pu-Zr alloy.<br />

Unlike the oxide and carbide fuels that are processed by<br />

the conventional PUREX process, the metallic fuel will be<br />

processed by pyroelectrochemical route. CG has been engaged<br />

in the R&D of pyrochemical processing of metal fuels <strong>for</strong><br />

nearly two decades. Starting with a lab scale facility, in which<br />

electro-refining of uranium was demonstrated on 200 gram<br />

scale, an engineering scale demonstration facility (Figure 9) <strong>for</strong><br />

process studies on a one kilogram scale has been commissioned.<br />

Electrorefining experiments have been carried out on kilogram<br />

scale with U metal as well as U-6%Zr alloy. Studies on the<br />

electrorefining of plutonium and its rare earth alloys on lab<br />

scale to understand the chemical behaviour be<strong>for</strong>e scaling<br />

up the process were carried out. The group is now engaged in<br />

setting up facilities, along with Fast Reactor Technology Group,<br />

<strong>for</strong> electrorefining and consolidation studies on ten kilogram<br />

scale. Several studies have been taken up on a fundamental<br />

plane on molten salt chemistry and thermochemistry relating to<br />

pyroprocessing. Studies on electrochemical reduction behavior<br />

of plutonium and zirconium ions in LiCl-KCl molten salt at various<br />

temperatures have been carried out by transient electrochemical<br />

techniques such as cyclic voltammetry and chronopotentiometry.<br />

Towards modelling the electrorefining process, a code, based on<br />

thermochemical equilibria (PRAGAMAN) and a code based on<br />

diffusion layer theory (DIFAC) have been developed.<br />

Direct Electrochemical Reduction of Uranium Oxides<br />

Currently, the actinide metals are produced by the calciothermic<br />

reduction of their respective fluorides which in turn are produced<br />

from their oxides. The direct electrochemical reduction of<br />

uranium oxides by making them as the cathode of an electrolytic<br />

Figure 9: a) Engineering scale demonstration facility <strong>for</strong> pyroprocess<br />

studies on uranium alloys and b) uranium metal ingot consolidated from<br />

electrorefining<br />

cell using platinum/graphite as anode and the molten salt LiCl<br />

or CaCl 2<br />

containing small amounts of lithium oxide or calcium<br />

oxide as the electrolyte has been studied, and ef<strong>for</strong>ts are on to<br />

optimize the process parameters to achieve complete reduction<br />

and extend the process <strong>for</strong> PuO 2<br />

.<br />

BASIC RESEARCH<br />

Thermochemistry<br />

The Chemistry Group has pursued a number of programmes<br />

in basic research related to the mission programmes.<br />

High temperature mass spectroscopy has been an area of<br />

specialization in Chemistry Group. Using the Knudsen mass<br />

spectrometer established <strong>for</strong> the first time in the country, a<br />

large number of systems of relevance to fuel cycle interaction<br />

in oxide fuels such as tellurides of iron, nickel and chromium<br />

have been studied. Phase diagrams and vaporization behaviour<br />

have been established <strong>for</strong> the first time in several systems. The<br />

thermal expansion behavior of (U,RE) mixed oxides as well as the<br />

solubility limits of rare earth oxides were also determined using<br />

high temperature X-ray diffraction. The heat capacity data of<br />

these mixed oxides by differential scanning calorimetry have also<br />

corroborated the solubility limits of rare earth oxides.<br />

Separation Science<br />

Third phase <strong>for</strong>mation during the extraction of Th(IV) and<br />

Pu(IV) by several trialkyl phosphates such as TBP, tri-iso-butyl<br />

phosphate (TiBP), tri-sec-butyl phosphate (TsBP), TAP, T2MBP,<br />

TsAP etc., were studied in a comprehensive manner. Studies have<br />

also been carried out on third phase <strong>for</strong>mation in the extraction<br />

of trivalent lanthanides by CMPO based solvents. A number of<br />

phosphonate extractants such as Dibutylbutyl phosphonate<br />

(DBBP), Dibutylhexyl phosphonate (DBHeP), Dibutyloctyl<br />

phosphonate (DBOP) and Diamylamyl phosphonate (DAAP) have<br />

been synthesized and studies on extraction of actinides (U, Th,<br />

Pu and Am) and third phase <strong>for</strong>mation have been carried out in<br />

detail <strong>for</strong> the first time. A unique instrument has been developed<br />

<strong>for</strong> the measurement of phase separation time of solvents based<br />

on light scattering technique. The thermal decomposition of TBP-<br />

5


IGC Newsletter<br />

nitric acid systems was also studied by adiabatic calorimetry.<br />

Enthalpy and activation energy of decomposition of nitric acid<br />

solvated TBP were reported <strong>for</strong> the first time.<br />

A laser mass spectrometry system comprising in-house<br />

developed reflectron time-of-flight mass spectrometer was used<br />

to study solid and liquid samples containing UO 2<br />

doped with<br />

lighter rare earths, towards developing a method <strong>for</strong> the direct<br />

determination of burn-up of irradiated nuclear fuel, without<br />

chemical separations on the fuel solution.<br />

Boron Chemistry<br />

Besides demonstrating the production of enriched elemental<br />

boron, a number of basic studies on the electrochemistry of boron<br />

in the molten salt medium as well as vaporization chemistry of<br />

boric acid were carried out. The vaporization behavior of H 3<br />

BO 3<br />

(s)<br />

was studied by the transpiration method (using a commercial<br />

thermo gravimetric apparatus) as well as Knudsen Effusion<br />

Mass Spectrometry (KEMS). Using Ag/AgCl reference electrode<br />

developed in-house, <strong>for</strong> the first time, the cyclic voltammogram<br />

of boron deposition on a platinum electrode from KCl-KF-KBF 4<br />

molten salt mixture was recorded. The influence of oxideion<br />

impurity in the KCl-KF-KBF 4<br />

melt system on the electrode<br />

potentials was also investigated by linear sweep voltammetry.<br />

Matrix Isolation Infrared Spectroscopy<br />

A Matrix Isolation – Fourier Trans<strong>for</strong>m Infrared Spectroscopy<br />

facility (MI-FTIR) has been set up to study the con<strong>for</strong>mations<br />

of organic molecules and intermolecular interaction between<br />

the molecules. Using this facility, con<strong>for</strong>mations and structures<br />

of trimethyl phosphate, triethyl phosphates, tributyl phosphate,<br />

phosphites, phosphonates, methoxy compounds, carbonates<br />

and silanes were studied. By controlled annealing experiments,<br />

weak and strong hydrogen bonded complexes and van der Waals<br />

complexes have also been studied. CG is now in the process<br />

of setting up a MI-FTIR facility at RRCAT, Indore to carry out<br />

photochemical studies on some of the systems indicated above,<br />

using the Synchrotron facility.<br />

Fluorescence Spectroscopy<br />

Fluorimetric methods were developed to detect uranium and<br />

lanthanide ions such as terbium, dysprosium, europium, and<br />

samarium at trace levels (


Technical Article<br />

IGC Newsletter<br />

Per<strong>for</strong>mance Testing of Primary Ramp and Primary Tilting Mechanism<br />

of Inclined Fuel Transfer Machine of Prototype Fast Breeder Reactor<br />

Prototype Fast Breeder Reactor employs two machines <strong>for</strong><br />

handling fuel sub-assemblies within and out of the main<br />

vessel, viz. (i) transfer arm – <strong>for</strong> in-vessel handling of fuel,<br />

blanket and control sub-assemblies within the main vessel<br />

and (ii) inclined fuel transfer machine – <strong>for</strong> transfer of spent<br />

sub-assemblies out of the main vessel and replacing them with<br />

fresh sub-assemblies (Figure 1). The primary side of the inclined<br />

fuel transfer machine consists of: primary tilting mechanism,<br />

primary ramp, shield plug, inter connecting piece, bellows and<br />

primary gate valve. Primary tilting mechanism is bolted to the<br />

grid plate and primary ramp is located on the primary ramp liner<br />

of roof slab. The bottom of the primary ramp engages with the<br />

guide funnel of the primary tilting mechanism to <strong>for</strong>m a sliding<br />

joint that accommodates the differential thermal expansion<br />

between primary ramp and primary tilting mechanism from room<br />

temperature to various operating conditions (normal operation/<br />

fuel handling ). The secondary side of the inclined fuel fransfer<br />

machine consists of secondary gate valve, secondary ramp<br />

and secondary tilting mechanism, which are located inside the<br />

fuel building. Primary side and secondary side of inclined fuel<br />

transfer machine are interconnected through the rotatable shield<br />

leg, which includes a rotatable table supported on a slewing ring.<br />

During fuel handling, the spent fuel sub-assembly is loaded<br />

into the transfer pot, which is inside primary tilting mechanism<br />

by transfer arm. Transfer pot containing the sub-assembly and<br />

sodium to remove decay heat from the spent sub-assembly is<br />

hoisted through primary ramp into rotatable shield leg which then<br />

rotates by 180 o to engage with secondary side. Transfer pot with<br />

sub-assembly is then lowered into the secondary tilting<br />

mechanism thus transferring the spent sub-assembly from the<br />

in-vessel transfer position located in the periphery of the core<br />

to the ex-vessel transfer position located in fuel building. The<br />

transfer pot is then loaded with a fresh sub-assembly and the<br />

above sequence of operations is then reversed to transfer a fresh<br />

sub-assembly back into the reactor.<br />

Two tilting rails and one guide rail are provided on both the<br />

primary and secondary sides of inclined fuel transfer machine<br />

and corresponding tilting and guide rollers are provided on<br />

the transfer pot. The rollers are high temperature ball bearings<br />

designed to work in sodium. Material selection of rollers and<br />

hard facing of the rails is based on tribological considerations<br />

suitable <strong>for</strong> sodium service. Rails of primary/secondary tilting<br />

mechanism are designed such that transfer pot is tilted from<br />

17 o 23 ’ inclination to vertical while lowering in them and<br />

vice-versa.<br />

Primary ramp and primary tilting mechanism (Figure 2) were<br />

fabricated by M/s MTAR, Hyderabad. After completion of shop<br />

Figure 1: Inclined fuel transfer machine<br />

Figure 2: Schematic of primary ramp/primary tilting mechanism test<br />

set-up<br />

7


IGC Newsletter<br />

Technical Article<br />

Figure 3: Primary ramp with<br />

primary ramp liner<br />

Figure 4: Ramp extension piece,<br />

drive mechanism and support<br />

structure<br />

floor testing, per<strong>for</strong>mance testing was carried out in test vessel-2<br />

of the large component test rig under reactor simulated conditions.<br />

The testing was limited to ~10 % of the total number of cycles<br />

expected in the reactor life of 40 years as the same components<br />

are to be installed in the reactor after testing.<br />

Primary ramp and primary tilting mechanism were assembled in<br />

test vessel-2 of large component test rig along with additional<br />

components like ramp extension piece, gate valve, simplified<br />

hoisting system with support structure and transfer pot with<br />

dummy sub-assembly. Schematic of test set-up is shown<br />

in Figure 2. Test vessel-2 is a vessel of 2 meter diameter and<br />

12 meter height. It is provided with a branch pipe at 17 o inclination<br />

to simulate the assembly of primary side of inclined fuel transfer<br />

machine. Primary tilting mechanism was bolted to the grid plate<br />

inside test vessel-2 while primary ramp was mounted on a<br />

specially fabricated liner simulating the rigid support in the reactor<br />

(Figure 3). The entire length of primary ramp was housed in the<br />

branch pipe at 17 o inclination to vertical. Relative motion between<br />

primary ramp and primary ramp liner was arrested by two locking<br />

pins. Transfer pot with dummy sub-assembly was lowered into<br />

the primary tilting mechanism through primary ramp followed<br />

by sequential assembly of gate valve and ramp extension piece<br />

(Figure 4). The top of ramp extension piece was connected to<br />

the structure supporting the hoisting mechanism through another<br />

sliding joint with O-ring sealing. The assembly of the primary<br />

ramp, primary tilting mechanism and ramp extension piece was<br />

carried out such that inclination of 17 o to vertical of primary ramp,<br />

ramp extension piece and alignments of the rails were achieved.<br />

The alignment of guide rails between primary ramp and primary<br />

tilting mechanism was critical and was achieved within 0.5 mm.<br />

The hoisting mechanism consists of chain and sprocket<br />

arrangement, sprocket shaft, motor (3.7 kW, 1440 RPM) with<br />

brake and speed reduction gear train (helical gears with worm<br />

reducer, reduction ratio of 1000:1). A torque limiting safety<br />

coupling is provided between the motor and driving end of<br />

gear train. The sprocket and sprocket shaft are housed inside a<br />

leak tight housing with viewing windows. Operation of the test<br />

set-up was carried out through a control console incorporated<br />

with safety interlocks.<br />

The instrumentation provided <strong>for</strong> the hoisting mechanism<br />

includes continuous on-line monitoring of transfer pot position<br />

using potentiometer, automatic stop of transfer pot at top limit<br />

using reed switch and potentiometer, and at bottom limit using<br />

tension sensing mechanism, potentiometer, and limit switches to<br />

identify open and closed positions of gate valve. In addition to<br />

the above, thermocouples are provided at various locations along<br />

the vessel, branch pipe and ramp extension piece to monitor<br />

temperature. An arrangement consisting of dial gauges and<br />

linear variable differential trans<strong>for</strong>mer is provided to monitor the<br />

deflection of test vessel-2 at the elevation of the grid plate during<br />

high temperature operation.<br />

One cycle of testing consisted of the following operations:<br />

• Hoisting of transfer pot with dummy sub-assembly from<br />

inside primary tilting mechanism at 29.2 mm/s speed<br />

(corresponds to motor speed of 600 RPM) from bottom<br />

position i.e. 22400 to 24279 mm elevation<br />

• Hoisting through sliding joint between primary ramp<br />

and primary tilting mechanism at 7.3 mm/s speed<br />

(corresponds to motor speed of 150 RPM) up to<br />

29550 mm elevation<br />

• Hoisting inside primary ramp at 29.2 mm/s speed up to<br />

29550 mm elevation<br />

• Hoisting at gate valve location at the speed of 7.3 mm/s up<br />

to 31400 mm elevation<br />

• Hoisting inside ramp extension piece at 29.2 mm/s speed<br />

up to topmost location i.e. 35800 mm elevation. During<br />

hoisting, transfer pot was parked <strong>for</strong> 150 s at 29660 and<br />

32405 mm elevations respectively <strong>for</strong> siphoning and<br />

dripping of sodium from it<br />

• Lowering of transfer pot from top most elevation to bottom<br />

elevation with different speeds at different elevation as<br />

mentioned above<br />

Elevation details of primary ramp/primary tilting mechanism test<br />

set-up <strong>for</strong> set value and observed value during testing are given<br />

in Table-1.<br />

Per<strong>for</strong>mance testing of primary ramp and primary tilting<br />

mechanism was carried out in various stages viz. in air at room<br />

temperature, in hot air and in sodium at 200 o C which is the fuel<br />

handling temperature of Prototype Fast Breeder Reactor. The<br />

8


Technical Article<br />

IGC Newsletter<br />

Table-1: Elevation details of primary ramp/primary tilting mechanism test set-up<br />

Position of transfer pot Set point Raising Lowering<br />

Top 35800 stop by potentiometer signal manual start at 600 RPM<br />

Dripping 32045 stop 150s <strong>for</strong> dripping NA<br />

Speed change-3 31400 speed to 600 RPM speed to 150 RPM<br />

Speed change-2 29550 speed to 150 RPM speed to 600 RPM<br />

Speed change-1 24279 speed to 600 RPM speed to 150 RPM<br />

Bottom 22400 manual start at 150 RPM stop by potentiometer signal<br />

per<strong>for</strong>mance of the system was monitored continuously by<br />

measuring the current drawn by motor (measure of motor torque)<br />

and monitoring the system <strong>for</strong> noise and vibration. A total of<br />

100 cycles of air testing was carried out at room temperature.<br />

Current drawn by the motor was within 4.4 A. Measured value<br />

of torque was within 15 to 16 N-m. No rubbing marks or scoring<br />

marks were observed on the rails and rollers. Overall per<strong>for</strong>mance<br />

of the system was satisfactory.<br />

In order to conduct sodium tests, pressure hold test of the<br />

system was conducted <strong>for</strong> 24 hours duration with compressed<br />

air at a pressure of 200 mbar (g). Hot purging was done which<br />

reduced the moisture and oxygen levels in the system to 118 and<br />

487 vppm, respectively. Prior to the start of sodium tests, hot air<br />

test was carried out <strong>for</strong> 24 cycles at different temperatures of 65,<br />

95, 110, 125 and 150 o C. Overall per<strong>for</strong>mance of the system was<br />

satisfactory. Current drawn by the motor and torque values were<br />

well within the acceptable limits.<br />

In sodium per<strong>for</strong>mance testing was carried out at 200 o C. Oxygen<br />

level in sodium was maintained to less than 2 ppm. The effect of<br />

reactor operation at rated temperature of 547 o C on the aerosol<br />

deposition in cold regions like gate valve was also simulated<br />

by means of two dwell period tests each of 150 hours duration<br />

at 547 o C. The dwell periods were interspersed between the<br />

cyclic tests. The system was tested <strong>for</strong> a total of 510 cycles in<br />

sodium. The per<strong>for</strong>mance of the system was along expected<br />

lines. Maximum current drawn by the motor was within 4.5 A.<br />

Measured values of torque were within 14 to 19 N-m.<br />

(a)<br />

(b)<br />

After completion of the testing, the sodium in test vessel-2 was<br />

drained and vessel cooled to 60 o C. Test vessel-2 was isolated<br />

from large component test rig loop and connected to a specially<br />

fabricated system <strong>for</strong> sodium removal using water vapor-CO 2<br />

process. The cleaning process was very effective (Figure 5). A<br />

total of 3 kg of sodium was removed by this method. The value<br />

obtained experimentally (from H 2<br />

monitoring during the process)<br />

was close to that obtained by estimation. The time taken <strong>for</strong> vapor<br />

phase reaction was 85 hours. The vapor phase reaction was<br />

followed by water wash using fine spray followed by washing in<br />

distilled water in a jet facility erected <strong>for</strong> the purpose as well as in<br />

a specially fabricated water tub. The rollers of transfer pot were<br />

dismantled and cleaned in ultrasonic bath.<br />

After cleaning and drying, primary ramp and primary tilting<br />

mechanism were inspected by Quality Assurance Division. Visual<br />

examination of the primary ramp and primary tilting mechanism<br />

revealed no scoring or rubbing marks on the rails. The weld<br />

between the primary tilting mechanism body and base plate<br />

was subjected to liqiud penetrant inspection examination and<br />

found to be defect free. Liqiud penetrant inspection examination<br />

of accessible portion of the primary ramp and primary tilting<br />

mechanism rails indicated absence of cracks. All screws holding<br />

the rails of primary tilting mechanism and primary ramp to the<br />

body were tack welded and the components cleaned by acetone,<br />

packed and dispatched to BHAVINI.<br />

The successful completion of the per<strong>for</strong>mance testing of primary<br />

ramp, primary tilting mechanism in air and sodium, and the<br />

effective in situ removal of sodium from primary ramp and primary<br />

tilting mechanism by water vapor and CO 2<br />

process have qualified<br />

the component <strong>for</strong> reactor operations. Visual examination followed<br />

by the subsequentliqiud penetrant inspection examination of<br />

components after cleaning has confirmed the healthiness of the<br />

components.<br />

Figure 5: Primary tilting mechanism inside the test vessel a) be<strong>for</strong>e<br />

reaction and b) after reaction<br />

Reported by B.K.Sreedhar, Fast Reactor Technology Group and<br />

S.Raghupathy, Reactor Design Group<br />

9


IGC Newsletter<br />

Technical Article<br />

Science of Metal Nanoclusters<br />

Now it may be the time we say goodbye to the well-known<br />

old proverb: Big is Beautiful. Almost everyday the world is<br />

witnessing advancement and breakthrough discoveries that<br />

lead to miniaturization of devices through the knowledge of<br />

nanoscience and nanotechnology. 'Nano' is a generic buzz-word<br />

in this context. As we know, nanomaterials are nothing different<br />

from the parent phase of materials except its’ physical dimension<br />

ranges between 1-100 nm (1 nm=10 -9 m), at least in one direction.<br />

At the nanoscale, physical, chemical and biological properties<br />

of materials differ from the properties of individual atoms and<br />

molecules or bulk matter. That brings up spiraling applications<br />

of various nanoscale materials in almost every sphere of life. So,<br />

understanding the science of synthesis and novel properties of<br />

matters at nanoscales is one of the most active areas of research<br />

today. It brings out abundance of unexpected results to ponder.<br />

In this perspective, metal nanoclusters that <strong>for</strong>m an important<br />

class in the world of nanomaterials may deserve special attention<br />

<strong>for</strong> a comprehensive research study. Metal nanoclusters may be<br />

synthesized as embedded in various matrices or supported on<br />

functional substrates of interest. Synthesis of metal nanoclusters<br />

and nanostructures has been broadly classified according to two<br />

approaches: bottom up and top down. As the name suggests,<br />

the first method deals with techniques where nanoclusters are<br />

grown from single atom onwards. Top down approaches start<br />

exactly in the reverse way: from bulky crystals to nanocrystals of<br />

nanoclusters. Thus, there are some successful techniques <strong>for</strong> the<br />

processing of such novel materials, <strong>for</strong> example, metal dielectric<br />

co-sputtering, recoil-implantation, molten salt bath, direct<br />

implantation of metal ions, sol-gel, evaporation-condensation,<br />

electron beam lithography, optical lithography, ion-beam<br />

induced sputtering, etc. Controlled synthesis of size-selective<br />

metal nanoclusters in various media is of prime importance as<br />

most of the exotic properties depend primarily on their physical<br />

dimensions. To realize a better control on the preparations, basic<br />

understanding of the mechanisms governing <strong>for</strong>mation and<br />

evolution of metal nanoclusters while processing these novel<br />

materials is of great interest.<br />

Rich phenomena such as strong optical responses in the<br />

ultraviolet-visible to near infrared wavelength ranges of light,<br />

photoluminescence, local field enhancements, etc. are associated<br />

with metal nanoclusters and nanostructures. Interaction of<br />

visible light with surface electrons of metal nanoclusters, <strong>for</strong><br />

example, leads to fascinating colors of glasses through an optical<br />

phenomenon (known as surface-plasmon resonance). Colors of<br />

the glass depend on size, shape and number density of the metal<br />

nanoclusters as well as on dielectric constants of the media. In<br />

addition, this optical effect leads to large local field enhancements<br />

in the close vicinity of metal nanoclusters. These novel physical<br />

Figure 1: Photographic image shows the change of optical features of<br />

the silver-exchanged soda-glass samples due to the isochronal heat<br />

treatments<br />

effects have been motivating fundamental and experimental<br />

researchers <strong>for</strong> a long time extensively. Such research driven<br />

challenging applications of the plasmonic nanostructures<br />

are numerous. For example, fast-response optical switches,<br />

high sensitivity nanosensors, in<strong>for</strong>mation storages, chemical<br />

catalysis, tumor or cancer diagnosis and treatments, surfaceenhanced<br />

Raman spectroscopy, solar cell materials and so on.<br />

Accordingly, besides their exciting scientific and technological<br />

interests, research studies of nanoscale materials are becoming<br />

highly relevant in diverse disciplines including biology and<br />

medicines. However, there are several difficulties in handling,<br />

detection and measurements of such tiny materials due to their<br />

physical restrictions.<br />

Embedded Metal Nanoclusters in Glass Matrices<br />

Nanoscale silver clusters have been prepared in a soda-glass<br />

matrix through the silver ion-exchange (Ag + ↔ Na + ) process.<br />

Ion-exchange of various metal ions in soda glasses followed<br />

by thermal annealing or light ion irradiations (H + , He + ) are<br />

methods to modify linear and nonlinear optical properties of<br />

glasses. The method is commercially viable <strong>for</strong> applications in<br />

optoelectronic devices. Due to the technological importance,<br />

precise spectroscopic studies to elucidate the thermal stability<br />

of these optical nanomaterials are of great interest. A simple<br />

photograph is shown in Figure 1 to demonstrate how the colors<br />

have changed due to the given heat treatments. As seen, with<br />

the increase of annealing temperature, samples have darkened<br />

significantly. Darkening, or in other words, increase in the opacity<br />

implies that optical absorption density has increased consistently<br />

with the annealing temperature. This qualitative visual observation<br />

con<strong>for</strong>ms to the precise experimental results of optical absorption<br />

spectroscopy (Figure 2b). Metal nanoclusters are experimentally<br />

identified through the characteristic optical resonance (surfaceplasmon<br />

resonance) wavelengths. In case of Ag nanoclusters in<br />

a glass matrix, surface-plasmon resonance position is ~420 nm.<br />

10


Technical Article<br />

IGC Newsletter<br />

(a)<br />

(b)<br />

Figure 2: (a) Photoluminescence (with 488 nm excitation) and (b)<br />

optical absorption spectroscopy of Ag nanoclusters in the matrix<br />

Figure 3: Ruther<strong>for</strong>d backscattering spectra of silver-exchanged sodaglass<br />

samples annealed at (a) 320, (b) 450, (c) 550 and (d) 600 o C<br />

Increase in the absorption intensity with the increase of annealing<br />

temperature is attributed to the thermal growth of the silver<br />

nanoclusters in the glass matrix. The observed growth may be<br />

explained from Mie theory of light scattering. Assuming average<br />

size of metal nanoclusters to be much smaller than the optical<br />

wavelength, Mie theory calculates the resonance absorption<br />

intensity to scale up with volume fractions of metal nanoclusters.<br />

Photoluminescence spectroscopy results corroborate further<br />

with the growth of the silver nanoclusters. For example, drastic<br />

changes in the photoluminescence intensity have been observed<br />

on post-annealing the silver-exchanged glass samples at various<br />

temperatures (Figure 2a). Silver monoxide (AgO) <strong>for</strong>med in the<br />

as-exchanged soda-glass sample is chemically unstable and it<br />

decomposes into species like Ag 2<br />

O and Ag while annealing in<br />

vacuum around 380 o C. Further increase of annealing temperature<br />

only helps in the growth of the Ag nanoclusters due to thermal<br />

decomposition of Ag 2<br />

O. As a result, the photoluminescence<br />

intensity quenches (Figure 2a). A strong correlation of the<br />

growth of the silver nanoclusters and drastic changes in the<br />

photoluminescence intensity due to thermal annealing of the<br />

silver-exchanged glass samples has been so established.<br />

Ruther<strong>for</strong>d backscattering experiments have been carried out in<br />

these samples to measure the concentration profiles of Ag after<br />

thermal annealing (1 hour isochronal) at various temperatures.<br />

An analyzing beam of He + ions at energy of 2 MeV, backscattered<br />

by an angle of 160 o , was used during the backscattering<br />

measurements. It is observed from the backscattering spectra<br />

(Figure 3) that silver got accumulated near the surface of the glass<br />

during the annealing. Accumulation of silver is higher <strong>for</strong> samples<br />

annealed at higher temperatures. Near-surface (within~100 nm)<br />

accumulation is due to the thermal diffusion of silver ions in the<br />

soda-glass matrix. This outward diffusion of silver ions relaxes<br />

the stress (which arises due to size difference of Ag + and Na +<br />

ions) and minimizes the total energy in the system. Applying<br />

suitable diffusion theory to the Ruther<strong>for</strong>d backscattering data,<br />

it has been possible to estimate activation energy <strong>for</strong> thermal<br />

diffusion of silver ions in the soda-glass matrix. This short-range<br />

accumulation of silver ions during annealing allows to consider<br />

the case as a semi-infinite diffusion system with the bulk acting<br />

as a constant source of known density (say,c 0<br />

). Accumulated<br />

mass of silver per unit area (m) on the surface can be calculated<br />

as, m = c Dt<br />

0 p where t is the time of diffusion in the sample held<br />

at temperature T; D is the diffusion coefficient of silver ions at<br />

ε a −<br />

kT<br />

temperature T. Assuming D to vary as e (ε a<br />

is the activation<br />

energy <strong>for</strong> the diffusion of silver ions and k is the Boltzmann<br />

constant), m can be rewritten as,<br />

ε<br />

a<br />

ln( m)<br />

= K1<br />

−<br />

2kT<br />

(1)<br />

where k 1<br />

is a constant in the present experimental conditions.<br />

For samples annealed at different temperatures, m has been<br />

estimated using the expression m = N<br />

A<br />

M / NAvo.<br />

where<br />

N A<br />

(number of Ag atoms/cm2 ) is directly obtained from the<br />

backscattering data, M is the atomic weight of silver and N Avo<br />

is the Avogadro number. Plugging the Ruther<strong>for</strong>d backscattering<br />

data in equation (1), the Arrhenius plot is reported. From the slope<br />

of the fitted line, activation energy <strong>for</strong> the diffusion of silver ions in<br />

the soda-glass is estimated to be about 0.74 eV.<br />

Apart from the chemical routes, ion implantation has been a very<br />

popular technique to synthesize metal nanoclusters in various<br />

matrices. In general, ion implantation techniques provide distinct<br />

advantages over many other synthetic processes, because:<br />

embedded species are protected by the matrix and hence<br />

chemically clean, superior control over depth as well as size<br />

distributions and the process is not limited by the solubility factor<br />

of the matrix. As the first example, nanoscale cobalt clusters<br />

have been synthesized in a silica glass matrix by implanting high<br />

energy (2 MeV) cobalt ions. Optical and vibrational properties<br />

of the cobalt nanoclusters are particularly interesting. Surfaceconfined<br />

acoustic vibration modes (phonons) of these cobalt<br />

nanoclusters have been detected using the low-frequency<br />

Raman scattering spectroscopy. Raman scattering spectroscopy<br />

11


IGC Newsletter<br />

Technical Article<br />

Figure 4: Raman scattering intensity of surface acoustic vibrational<br />

modes confined to cobalt nanoclusters as a function of excitation<br />

wavelengths (spectra are offset along the intensity-axis <strong>for</strong> better<br />

clarity)<br />

has been used extensively and effectively as a nondestructive<br />

experimental means to study the ion implantation-induced<br />

growth as well as the thermal growth of the metal nanoclusters<br />

in various glass matrices. As shown in Figure 4, Raman spectra<br />

have been recorded in the cobalt implanted silica sample using<br />

different excitation wavelengths. Interestingly, intensity of<br />

the vibrational modes is found to depend significantly on the<br />

wavelength of laser excitations (Figure 4). Strong local field of<br />

surface-plasmon resonance in cobalt nanoclusters with 351.1 nm<br />

excitation wavelength is thought to be the reason <strong>for</strong> the observed<br />

enhancement of Raman scattering intensity. It is because<br />

the characteristic surface-plasmon resonance wavelength of<br />

cobalt nanoclusters in silica is around 350 nm. Results thus<br />

obtained from the Raman scattering spectroscopy experiments,<br />

particularly, emphasizes the importance of plasmon-phonon<br />

coupling in the metallic nanoclusters.<br />

Figure 5: Ruther<strong>for</strong>d backscattering spectra <strong>for</strong> silver ion implanted<br />

soda-glass samples with various ion fluences (indicated with symbols)<br />

In a similar way, using the ion implantation (1 MeV Ag + ions)<br />

technique, growth of embedded nanoscale silver clusters in a<br />

soda-glass matrix has been studied mainly to highlight interesting<br />

optical properties of large scale metal nanoclusters. Prior to the<br />

discussion on the optical results, in<strong>for</strong>mation about concentration<br />

profiles of silver atoms in the soda-glass samples measured<br />

by the backscattering spectrometry (Figure 5) would be more<br />

important. Only the partial spectra at high energy channels are<br />

shown here to emphasize the backscattering from silver atoms.<br />

Interestingly, in the sample implanted with the highest fluences,<br />

most of the concentration of the silver atoms is found to be<br />

close to the glass surface (Figure 5, blue dots) and the atomic<br />

concentration of silver reduces continuously along the depth in the<br />

soda-glass matrix. Defect-enhanced diffusion of Ag atoms in<br />

the soda-glass matrix would lead to the segregation of the Ag<br />

atoms close to the glass surface. Surface segregation of the Ag<br />

Figure 6: Ag + ion implanted soda-glass sample with fluences 5 x 10 16 ions cm -2 (Figure a) and ion-beam sputtered (5 x 10 16 Ar + ions cm -2 ) thin film of Ag<br />

metals on silica glass (Figure c) show dipolar as well as quadrupolar surface-plasmon resonance absorption in samples with larger Ag nanoclusters.<br />

Only dipolar absorption has been observed <strong>for</strong> Au thin films sputtered with Ar + ions (5 x 10 16 ions cm -2 ) (Figure b). Corresponding scanning electron<br />

micrographs display morphologies and various sizes of the Ag and supported Au nanoclusters on the glass substrates.<br />

12


Technical Article<br />

IGC Newsletter<br />

Figure 7: Ruther<strong>for</strong>d backscattering spectra of the Au film and Ar + ion<br />

irradiated Au films as a function of fluences (partial spectra to emphasize<br />

the backscattering from Au are only shown)<br />

atoms has been confirmed further by the electron microscopy<br />

measurements (Figure 6a). The microscopy results particularly<br />

support the observed backscattering results, i.e., the increase<br />

in the Ruther<strong>for</strong>d backscattering yield as well as the shift in<br />

the concentration profile of Ag atoms (Figure 5) close to the<br />

glass surface. In this sample, large clusters of silver atoms<br />

(sizes ~100 to 200 nm) have been estimated. These largescale<br />

silver nanoclusters play a dominant role in modifying the<br />

optical absorption properties. For example, intensity and the<br />

width of the surface-plasmon resonance are greatly modified,<br />

as it is clearly observed in the spectral response characteristics<br />

(Figure 6a). With increasing cluster sizes, additional higher-order<br />

(e.g., quadrupole) optical resonances become important because<br />

of the non-zero field gradient across the metal clusters. The<br />

optical results reveal a shoulder on the low wavelength side of<br />

the dipole peak. This was assigned to the quadrupolar resonance<br />

peak (inset, Figure 6a and Figure 6c).<br />

Supported Metal Nanostructures on Glass Substrates<br />

Ion-beam sputtering based non-equilibrium synthesis (top<br />

down approach) is a promising method leading to production<br />

of tailored nanoclusters as well as nanostructure materials on<br />

given substrates. The ion-beam sputtering based processing<br />

is also of interest because it is cost-effective compared to<br />

direct-write techniques, such as optical or electron beam<br />

lithography. Ion sputtering is a physical process whereby atoms<br />

are ejected from the surface due to bombardment of the target by<br />

energetic particles. It is driven by momentum transfer between<br />

the ions and atoms in the materials during the atomic collisions.<br />

In the present case, gold (Au) as well as silver (Ag) metallic films<br />

were deposited separately on cleaned silica substrates using the<br />

thermal evaporation set-up. Subsequently, the metal films were<br />

irradiated using the 100 keV Ar + ions with various ion fluences.<br />

Ruther<strong>for</strong>d backscattering experiments have been carried out to<br />

measure the areal density of Au atoms in the as-deposited Au film<br />

as well as in the ion irradiated Au film samples. Figure 7 displays<br />

the backscattering spectra of the samples. Systematic decrease<br />

Figure 8: Log-Linear plot of areal density of Au atoms as a function of<br />

fluences of the Ar + ions (experimental data points (•) are obtained from<br />

the backscattering results)<br />

of the backscattering yield with the increase of Ar + ion fluences<br />

may be observed. The decrease of area under the Au peak (which<br />

is proportional to the Au areal density) with increase of Ar + ion<br />

fluences confirms the loss of Au atoms from the films due to the<br />

ion sputtering processes. This particular experimental aspect is<br />

explained here. To describe the observed experimental facts in a<br />

quantitative way in the case of sputtering of a thin film by the ionbeam,<br />

a phenomenological model equation is proposed:<br />

dN<br />

T<br />

= −kN<br />

where dN T<br />

is the reduction (due to the sputtering) of Au areal<br />

density on the substrate. Intuitively, the loss should be<br />

proportional to the instantaneous available areal density of Au<br />

atoms (N T<br />

) and the associated increment of the ion-fluences (dø).<br />

The above differential equation is readily solved to obtain,<br />

ln( N T<br />

) = −kφ<br />

+ c<br />

T<br />

dφ<br />

( 2)<br />

( 3)<br />

Phenomenological constants, k and c would depend on the<br />

projectile ions, ion-beam and target material parameters.<br />

Experimentally measured areal density of Au atoms (N T<br />

) is plotted<br />

against the respective ion-fluences (ø) (shown in Figure 8 as a<br />

log-linear graph). This result clearly shows that during sputtering<br />

of the Au thin films, areal density of Au atoms decreases<br />

exponentially with the increase of ion-fluences, as prescribed by<br />

the equation 3.<br />

Presence of the metallic nanoclusters in the ion-beam sputtered<br />

samples has been elaborated through the optical absorption<br />

spectroscopy and electron microscopy results (Figure 6b<br />

and 6c). The optical response peak around 550 nm is attributed to<br />

the surface-plasmon resonance absorption in Au nanoclusters on<br />

silica substrates. Electron microscopy results show that nearly<br />

uni<strong>for</strong>m size (~50 nm) of Au nanoclusters are produced on silica<br />

due to the ion-beam induced sputtering process.<br />

Reported by P. Gangopadhyay and colleagues<br />

Materials Physics Division<br />

Materials Science Group<br />

13


IGC Newsletter<br />

Young Officer's Forum<br />

Young Officer’s<br />

FORUM<br />

Design of Elliptical Heat Exchanger<br />

<strong>for</strong> Future Fast Breeder Reactors<br />

The commercialization of fast breeder reactor programme needs<br />

further optimization of the reactor components <strong>for</strong> the future<br />

fast reactors. A considerable portion of the total cost of the pool<br />

type fast reactor, goes into the material cost which is a function<br />

of dimensions of the main vessel, which is in turn decided by<br />

reactor internals. Main vessel dimensions are controlled by the<br />

diameter of the intermediate heat exchanger and pump in both<br />

circumferential and radial directions. Diameter of the pump is<br />

optimised <strong>for</strong> its per<strong>for</strong>mance; further reduction is not possible<br />

without major design changes. With the dimension of the pump<br />

as basis, the shape of intermediate heat exchanger is optimised<br />

<strong>for</strong> the most economical configuration.<br />

A novel shape is proposed <strong>for</strong> the intermediate heat exchanger<br />

of future fast breeder reactor considering the techno-economical<br />

feasibilities. Optimization of the configuration of intermediate<br />

heat exchanger <strong>for</strong> the most economical benefit is brought out<br />

in this report along with detailed process design of intermediate<br />

heat exchanger with a design life of 60 years at 85% load factor.<br />

The intermediate heat exchanger is a vertical counter current<br />

flow, shell and tube heat exchanger with primary sodium flowing<br />

downwards on the shell side and secondary sodium flowing<br />

upwards on the tube side. Each intermediate heat exchanger<br />

Shri V. Sudharshan took his B.E. degree<br />

in Mechanical Engineering from Andhra<br />

University. He is the Homi Bhabha Award<br />

winner <strong>for</strong> topping the Mechanical<br />

Engineering discipline from the 4 th batch<br />

of BARC Training School at IGCAR and is<br />

currently Scientific Officer (C) in Reactor<br />

Components Division, Reactor Design Group. He is responsible <strong>for</strong><br />

the design of sodium – sodium heat exchangers.<br />

(Figure 1) is rated <strong>for</strong> 314.7 MW (t) and consists of a tube bundle<br />

having straight tubes. Each tube is 8050 mm and is made of<br />

austenitic stainless steel SS316LN, rolled and welded to the tube<br />

sheets at both the ends (Figure 1). The tubes are arranged in<br />

a circumferential pitch around an inner shell. This inner shell is<br />

welded to the tube sheets at both the ends.<br />

Choice of Intermediate Heat Exchanger Shape<br />

The reactor assembly proposed <strong>for</strong> future fast breeder reactors<br />

is shown in Figure 2. If the opening <strong>for</strong> the pump at the roof slab<br />

level is made to be the governing parameter <strong>for</strong> the main vessel<br />

diameter, diameter of main vessel can be further reduced by<br />

~300 mm. This is possible based on the fact that area available<br />

<strong>for</strong> the heat transfer to take place is the parameter and not the<br />

shape of the heat exchanger especially <strong>for</strong> liquid metals. With<br />

this factor as the basis, the area available in the reactor assembly<br />

is studied <strong>for</strong> other parameters like interface of internals etc. and<br />

it is concluded that the maximum dimensions available <strong>for</strong> heat<br />

exchanger <strong>for</strong> a 500 MWe, two loop design with two intermediate<br />

heat exchanger per loop, are 2140 mm along the circumference<br />

and 1550 mm along the radial direction <strong>for</strong> the outer shell<br />

dimensions. With these dimensions, the possible configurations<br />

<strong>for</strong> intermediate heat exchanger shape are worked out and the<br />

final shapes that are considered <strong>for</strong> the study are elliptical, oval<br />

1.Pump<br />

2.Intermediate heat<br />

exchanger<br />

3.Control plug<br />

4.Top shield<br />

5.Rotatable plugs<br />

6.Core<br />

7.Core support structure<br />

8.Main vessel<br />

9.Safety vessel<br />

10.Reactor vault<br />

Figure 1: Intermediate heat exchanger <strong>for</strong> future fast breeder reactors<br />

Figure 2: Reactor assembly of future fast breeder reactors<br />

14


Young Officer's Forum<br />

IGC Newsletter<br />

Figure 3: Comparison of possible shapes <strong>for</strong> intermediate heat<br />

exchanger<br />

and bean/kidney as shown in Figure 3.<br />

With two different dimensions along the axes, ellipse appears to<br />

be a natural choice, but a close examination of Figure 3 shows that<br />

by adopting kidney shape there is overall optimization of space.<br />

Kidney shape though utilises the maximum space available, is<br />

made of segments with different centres that pose problems<br />

during manufacturing. Further its advantage over the oval shape<br />

is also minimal. So the oval shape which is a simple extension<br />

of circular shape with a horizontal portion connecting two semicircles<br />

is preferred as the shape of intermediate heat exchanger<br />

<strong>for</strong> future fast breeder reactors. With oval shape, the scheme <strong>for</strong><br />

the ferrule and anti-vibration belt shall be retained same as that<br />

<strong>for</strong> the intermediate heat exchanger of Prototype Fast Breeder<br />

Reactor. Once the outer shell shape (shape of intermediate heat<br />

exchanger) is decided, the next parameter is to decide upon the<br />

shape of the central down comer, through which the secondary<br />

sodium enters the intermediate heat exchanger. The governing<br />

parameter <strong>for</strong> the choice of down comer is that the velocity of<br />

sodium in the down comer must be restricted to a maximum<br />

of 9.0 m/s due to erosion of structural material in intermediate<br />

heat exchanger. Since this is a limiting value, it is retained as a<br />

guiding parameter to arrive at other parameters <strong>for</strong> intermediate<br />

heat exchanger.<br />

Design Constraints<br />

1. Maximum pressure drop on shell side (H) = 1.45 mlc Na<br />

2. Maximum dimension of intermediate heat exchanger outer<br />

shell (shroud) = 2140/1550 mm<br />

The other design constraint is the maximum heat transfer length.<br />

Table 1: Chemical composition of SS316LN (balance-iron)<br />

Element C N Cr Ni Mo Si Mn S P<br />

Compositionw(wt%) 0.03 0.085 16 11.2 2.0 0.6 1.3 0.005 0.042<br />

Table 2: Chemical composition of nuclear grade sodium<br />

Impurity element O C CI Ca+Mg Fe<br />

Content, ppm


IGC Newsletter<br />

Young Officer's Forum<br />

Figure 5: Graphical representation of<br />

feasibility study<br />

It is recommended that the corrosion allowance <strong>for</strong> 60 year<br />

design life of intermediate heat exchanger is 0.114 mm. Analysis<br />

and design of components is proceeded accordingly.<br />

Prototype Fast Breeder Reactor intermediate heat exchanger<br />

tube thickness is 0.8 mm and margin on thickness is 0.2<br />

mm, comprising of both corrosion allowance and negative<br />

tolerance on tube diameter (10%). Studies also show that <strong>for</strong><br />

Prototype Fast Breeder Reactor, the unaffected base thickness<br />

of 0.6 mm is adequate <strong>for</strong> all loadings <strong>for</strong> 40 year design life.<br />

Further, optimization studies are planned to reduce the pressure<br />

transmitted to intermediate heat exchanger tube designed <strong>for</strong><br />

60 year design life based on 0.6 mm unaffected base thickness.<br />

Considering possible uncertainty, 0.8 and 1 mm thick tubes<br />

are selected <strong>for</strong> optimization of intermediate heat exchanger<br />

configuration.<br />

Parametric Study on Process Design of Intermediate Heat<br />

Exchanger <strong>for</strong> Tube Selecton<br />

A parametric study is conducted <strong>for</strong> the selection of tube size<br />

and arrangement <strong>for</strong> the specially shaped intermediate heat<br />

exchanger to check feasibility and optimization with the tube<br />

sizes (OD/THK), 14/1, 14/0.8, 16/1, 16/0.8, 19/1, 19/0.8,<br />

24/1 mm. A computer code is written <strong>for</strong> this purpose and is<br />

validated with Prototype Fast Breeder Reactor values. Ratio of<br />

the circumferential pitch and radial pitch (Sc/Sr) = π/3, which is<br />

adopted same as that <strong>for</strong> Prototype Fast Breeder Reactor, as the<br />

arrangement of tubes in the sodium to pass through is turning out<br />

to be same <strong>for</strong> any of the other configurations which are made<br />

to exploit the symmetry in the geometry of the systems which is<br />

60 0 <strong>for</strong> Prototype Fast Breeder Reactor and 90 0 <strong>for</strong> the present<br />

intermediate heat exchanger. The study included a feasibility study<br />

<strong>for</strong> the mentioned sizes which means simultaneous satisfaction<br />

of all the design constraints and the options are further studied<br />

<strong>for</strong> optimising the convex region, which gives most economic<br />

Figure 6: Variation of number of tubes in<br />

Intermediate heat exchanger as a function of<br />

radial pitch<br />

Figure 7: Variation of shell side pressure drop<br />

as a function of radial pitch<br />

benefit. Results of feasibility study is shown in a graph in the<br />

Figure 5. Variation of optimization parameters with respect to<br />

tube size and radial pitch <strong>for</strong> the feasible options (tube size) are as<br />

shown in the Figures 6, 7 and 8. All the configurations are studied<br />

from OD+5 mm since at least a 5 mm ligament is required <strong>for</strong> the<br />

tube sheet to prevent tearing. Study <strong>for</strong> 16/0.8 case is carried out<br />

to with Sr < OD + 5 mm to study the behaviour in that range.<br />

19/0.8 mm with radial pitch 25 mm is selected as the best suited<br />

option from economic considerations (material and manufacturing<br />

costs) <strong>for</strong> the future fast breeder reactors, the next option being<br />

16/0.8 and 22 mm radial pitch. Table 3 gives a comparison of<br />

intermediate heat exchanger configuration <strong>for</strong> the Prototype Fast<br />

Table 3: Comparison of intermediate heat exchanger configuration <strong>for</strong><br />

Prototype Fast Breeder Reactor and future fast breeder reactors<br />

Parameter PFBR Future FBR<br />

Design life (Y)/cap. factor 40/75% 60/85%<br />

Number of tubes 3600 3680<br />

Tube diameter/thickness (mm) 19/0.8 19/0.8<br />

Number of rows 25 23<br />

Number of tubes in first row 72 94<br />

Corrosion allowance (mm) 0.12 0.142<br />

Shroud dimensions (mm) 1850 2140/1550<br />

Area margin 24% 28%<br />

Average primary inlet velocity (m/s) 0.377 0.362<br />

Velocity of secondary sodium in down<br />

comer (m/s)<br />

9.2 7.36<br />

Shell side pressure drop (mlc Na) 1.45 1.39<br />

Velocity of secondary sodium in down<br />

comer (m/s)<br />

9.2 7.36<br />

Shell side pressure drop (mlc Na) 1.45 1.39<br />

Main vessel diameter (m)<br />

* with oval Intermediate heat<br />

exchanger<br />

12.9 11.9*<br />

16


Young Officer's Forum<br />

IGC Newsletter<br />

Figure 8: Variation of available down comer flow<br />

area as a function of radial pitch<br />

Figure 9: Average axial temperature profile in<br />

intermediate heat exchanger<br />

Figure 10: Radial and circumferential temperature<br />

distribution in tube bundle<br />

Breeder Reactor and future fast breeder reactors.<br />

Thermal Hydraulic Investigation on the Intermediate Heat<br />

Exchanger<br />

Intermediate heat exchanger is a counter current heat<br />

exchanger with primary sodium flow on the shell side and<br />

heat transfer area is based on the outer diameter of the tube,<br />

whereas in the actual scenario heat transfer takes place by<br />

a combination of cross flow and counter current parallel flow.<br />

These 3-Dimensional features contribute to uncertainties<br />

in the design vis-a- vis assumptions, correlation, by-pass<br />

flow near shells (inner and outer shells) etc. Taking these into<br />

consideration and the possibility of plugging of a few tubes during<br />

manufacturing, it has been estimated from the CFD studies that<br />

28% area margin on the rated value is required to overcome<br />

the uncertainties in thermal design <strong>for</strong> Prototype Fast Breeder<br />

Table 4: Comparison of Analytical and CFD results<br />

Parameter<br />

Analytical<br />

Result<br />

CFD Result<br />

Deviation<br />

%<br />

Heat flux Primary 313.18 MW 319.541 MW + 2.03<br />

Secondary 313.25 MW 319.538 MW + 2.0<br />

Mass flux Primary 1649 Kg/s 1648.465 Kg/s - 0.03<br />

Temperature<br />

Secondary 1450 kg/s 1450 Kg/s 0<br />

Primary<br />

inlet<br />

Primary<br />

outlet<br />

Secondary<br />

inlet<br />

Secondary<br />

outlet<br />

Pressure drop on shell<br />

side<br />

817 K 817 K 0<br />

667 K 664.1 K -0.4<br />

628 K 628 K 0<br />

798 K 801.567 K + 0.45<br />

11479.679*<br />

Pa (1.3926<br />

mlc) *<br />

11456.191 Pa<br />

(1.3898 mlc)<br />

*Considering 10% uncertainty margin <strong>for</strong> correlations<br />

-0.2<br />

Reactor. The same has been adopted in the present study.<br />

Since the shape is non-circular, there is a possibility <strong>for</strong> a<br />

non-uni<strong>for</strong>m flow along the circumferential direction in addition to<br />

the maldistribution of flow that is happening in the radial direction<br />

(to the shells) due to the cross flow entry of the primary sodium.<br />

There can be flow distribution along the peripheral and axial<br />

direction in the hot pool at intermediate heat exchanger inlet. In<br />

order to check the adequacy of design margin <strong>for</strong> the heat transfer<br />

owing to various uncertainties mentioned earlier, a CFD <strong>for</strong> a 90 0<br />

sector model study simulating the full load operation has been<br />

carried out. Table 4 gives the comparison of analytical results<br />

with CFD results. The results confirm that the provisions in the<br />

design are sufficient <strong>for</strong> the specified rating and the pressure<br />

drop on the shell estimated using correlations and that calculated<br />

by CFD simulation are matching within a deviation of 0.2%. This<br />

sufficiently validates the analysis. Average axial temperature<br />

distribution is shown in the Figure 9. The heat transfer process<br />

in the intermediate heat exchanger at various elevations with<br />

zero meter elevation as the bottom of the top tube sheet and<br />

-7.75 meter elevation as the top of the bottom tube sheet is<br />

depicted in the graph. Outer shell is present between the two<br />

windows, starting at -1 meter elevation, spanning 5.7 meter.<br />

Figure 10 shows the average temperature of tubes estimated at six<br />

different locations along with weighted average row temperature<br />

of tube bundle.<br />

Summary<br />

Elliptical intermediate heat exchanger <strong>for</strong> future Fast Breeder<br />

Reactors is optimized <strong>for</strong> achieving overall economics and<br />

compactness. Detailed 3D thermal hydraulic investigations<br />

on 90° symmetry sector of intermediate heat exchanger<br />

con<strong>for</strong>ms the adequacy of design margins <strong>for</strong> various process<br />

parameters such as heat transfer area, pressure drop, etc.<br />

Reported by V. Sudharshan<br />

Reactor Components Division, Reactor Design Group<br />

17


IGC Newsletter<br />

Young <strong>Research</strong>er’s<br />

FORUM<br />

Enhanced Transmission with Tunable Fano<br />

like Profile in Magnetic Soft Matter<br />

Resonance exhibiting distinctly asymmetric line shape, well<br />

known as Fano resonance is a ubiquitous phenomenon observed<br />

in various condensed matter systems such as quantum dots,<br />

carbon nanotubes and graphene etc. The observation of the<br />

enhanced transmission with Fano shape in per<strong>for</strong>ated metallic<br />

films have also attracted enormous attention due to their<br />

application in molecular sensing, spectroscopy, photonic<br />

devices etc. besides fundamental understanding. The observed<br />

enhanced transmissions, in per<strong>for</strong>ated periodic and aperiodic<br />

metallic systems are attributed to surface plasmon and localized<br />

waveguide resonances, respectively. However, the exact origin of<br />

enhanced transmission and Fano resonance is still not very clear.<br />

Moreover, till now all the Fano resonances are observed only in<br />

systems with well-engineered structures. Soft matter systems like<br />

nanofluids have been a topic of intense research during the last<br />

one decade due to their interesting properties and technological<br />

applications. The issues that we tried to address here are the<br />

following: (i) can Fano resonance be realized in a smart soft matter<br />

with aperiodic or random tubes and (ii) is it possible to tune the<br />

Fano profile using external stimuli like magnetic field. We provide<br />

first experimental evidence of Fano resonance in soft matter.<br />

Under an external magnetic field, the transmittance spectrum<br />

of a ferrofluid emulsion containing oil droplet size (diameter) of<br />

~ 220 nm (polydispersity < 2 %) shows an enhanced peak<br />

with Fano-like profile, which is attributed to localized waveguide<br />

resonance from random array of tubes, with charged inner<br />

surface, <strong>for</strong>med by the alignment of magnetically polarizable<br />

droplets. Further, by varying the magnetic field, the Fano profile<br />

is tuned and an opaque emulsion is turned to a transparent one.<br />

This finding will have interesting applications in tunable photonic<br />

devices.<br />

The ferrofluid (ff) emulsion used in our studies is octane oil<br />

droplets containing magnetic (Fe 3<br />

O 4<br />

, d ~ 6.5 nm) nanoparticles<br />

dispersed in water. The oil droplets are electrostatically stabilized<br />

with an anionic surfactant of sodium dodecyl sulphate. On<br />

applying an external magnetic field H 0<br />

, the strength of interaction<br />

between the droplets increases, which is described by the<br />

Young <strong>Research</strong>er's Forum<br />

Mr. Junaid Masud Laskar did his Masters in<br />

Physics from Tezpur University, Assam. He is the<br />

University third rank holder <strong>for</strong> M.Sc. He joined<br />

as a research fellow in January 2006 under the<br />

guidance of Dr. John Philip, Head, SMARTS, MMG<br />

and has submitted his Ph.D thesis in September,<br />

2011 to the University of Madras. The title of his<br />

thesis is “Probing of Structural Transitions in Magnetically Polarizable Soft<br />

Matters by Light Scattering”. He has published eight papers in reputed<br />

international journals. He has attended six international conferences and<br />

won the best poster presentation award at Second International Conference<br />

on Frontiers in Nanoscience and Technology, Cochin. Presently, he is<br />

pursuing his post doctoral research at the prestigious Max Planck Institute<br />

<strong>for</strong> Polymer <strong>Research</strong>, Mainz, Germany.<br />

3 2 2<br />

coupling constant L = pµ 0<br />

d χ H0<br />

72kBT<br />

where χ and k B<br />

T<br />

are the magnetic susceptibility and thermal energy respectively.<br />

When L > 1, the emulsion undergoes disorder-order structural<br />

transition, where linear chain-like structures are <strong>for</strong>med due to<br />

head on aggregation of oil droplets along H 0<br />

. To obtain insight into<br />

the implications of field induced structures, the transmitted light<br />

intensity is recorded as a function of H 0<br />

at different ramp rates<br />

using an automated light scattering set-up. The ff emulsion of<br />

volume fraction f =0.0033 is observed to be opaque to red light<br />

(He-Ne Laser, λ=632.8 nm) <strong>for</strong> cuvette of path length L=1 mm.<br />

This scattered light emerges from the exit face of the cuvette<br />

in the <strong>for</strong>m of a cone, which originates from the scattering of<br />

incident light from the cylindrical surface of field induced chains.<br />

Figure 1(a) shows the images of the exit face of the cuvette that<br />

contains the sample, at different H 0<br />

. The intersection, of this cone<br />

of scattered light, on a screen placed at far field and perpendicular<br />

to the incident light <strong>for</strong>ms a ring like pattern as shown in<br />

Figure 1 (c). A bright spot is also observed on the upper right<br />

Figure 1: (a) Images of transmitted light as a function of magnetic<br />

field during increase (ramp rate ~0.6 G/s) just at the exit face of<br />

quartz cuvette, which contains the ferrofluid emulsion, (b) Variation<br />

of transmitted light spot [top right corner of ring circumference of (c)]<br />

intensity during increase in magnetic field <strong>for</strong> different ramp rates,<br />

(c) Scattered patterns at four different fields during the increase at three<br />

ramp rates of 0.6, 1.67 and 10 G/s<br />

18


Young <strong>Research</strong>er's Forum<br />

IGC Newsletter<br />

part of ring circumference, which is the transmitted light spot in<br />

the direction of incident light. Figure 1(b) shows the intensity<br />

variation of this transmitted light spot as a function of increasing<br />

H 0<br />

at different ramp rates. The emulsion remains opaque to the<br />

incident light upto a H 0<br />

of 50 G, above which the transmitted<br />

intensity increases with the increase in H 0<br />

. For low ramp rate<br />

(0.6 G/s), the transmitted intensity again decreases above 150 G<br />

with increase in H 0<br />

.<br />

Considering the emulsion as a system of random scatterers, the<br />

transmitted light intensity <strong>for</strong> a path length L is given by<br />

I = I exp ( − nQ p 2<br />

t 0 ext<br />

a L)<br />

where I 0<br />

, a, n and Q ext<br />

are the<br />

incident light intensity, scatterer radius, scatterer number density,<br />

scattering extinction efficiency respectively. The Q ext<br />

is calculated<br />

using Mie scattering theory as a function of size parameter (ka)<br />

and is found to be very high <strong>for</strong> the ferrofluid emulsion, where the<br />

scatterer (oil droplet) radius a=110 nm i.e. ka =1.45. At H 0<br />

=0 G,<br />

the calculated incident light transmitted intensity I t<br />

/I 0<br />

<strong>for</strong> the given<br />

system is found to be very small (~ 2.9113×10 -46 ). There<strong>for</strong>e,<br />

significant scattering from the oil droplets in the emulsion <strong>for</strong>bids<br />

the light transmission in the absence of any magnetic field.<br />

On application of H 0<br />

, due to the aggregation of oil droplets, the<br />

internal structure inside the ferrofluid emulsion looks like array<br />

of random tubes (diameter D ~ λ) as shown in Figure 2. Now,<br />

the behavior of light transmission as a function of H 0<br />

, through the<br />

above mentioned structural arrangement, is basically influenced<br />

by two factors. First, the effect of change in light scattering due<br />

to changing chain length and secondly, the effect of changing<br />

dimensions of tubes, both tube diameter (D) and tube length (z).<br />

With the increase in H 0<br />

, due to the increase in chain length by the<br />

aggregation of oil droplets, the space between the chains i.e. the<br />

tube diameter also opens up.<br />

This structural rearrangement takes place <strong>for</strong> the uni<strong>for</strong>m<br />

distribution of the field induced structures through out the entire<br />

volume of the sample. In fact due to opening up of the tubes and<br />

increase in their diameter, effective scattering cross section of<br />

Figure 2: Schematic of ff emulsion at (a) H 0<br />

= 0 G, (b) 60 G < H 0<br />

<<br />

300 G, the array of chains and tubes and their dimensional variation as<br />

function of external magnetic field strength, arrow shows the direction<br />

of incident light and magnetic field, (c) cross sectional view of field<br />

induced tubes; (d) optical microscopic image of the cross sectional<br />

view of chains under external field, inset shows the chain <strong>for</strong>mation<br />

along the field direction<br />

the system decreases, which results in increase in transmitted<br />

light, thereby making the transition of the system from opaque<br />

to transparent above 50 G as shown in Figure 1(b). There<strong>for</strong>e, it<br />

is clear from this observation that the above mentioned second<br />

factor dominates over the first one on the light transmission<br />

behavior under external field.<br />

The specialty of the field induced tubes are discussed in detail<br />

further. Because of the negatively charged anionic head group<br />

of surfactant sodium dodecyl sulphate and free π electrons<br />

present, the inner tube surfaces are highly charged with a typical<br />

charge density 500 µC/cm 2 (10 12 /cm 2 in terms of electron<br />

number density), so that electric and magnetic fields of incident<br />

electromagnetic wave cannot penetrate the inner surface, thereby<br />

making the tubes behave like waveguides. Now, the system<br />

looks like an array of aperiodic random tube waveguides, whose<br />

dimensions are function of H 0<br />

. The transmitted wave amplitude<br />

decreases exponentially along the waveguide as exp(-α w<br />

z) due<br />

to the finite impedance of inner charged walls of the waveguide,<br />

where α w<br />

and z are the waveguide damping coefficient and<br />

waveguide length respectively. This causes the decrease of<br />

transmitted intensity with the increase in z, on increasing H 0<br />

[above 150 G <strong>for</strong> 0.6 G/s in Figure 1 (b)]. There<strong>for</strong>e, opening of<br />

tubes and increase in their ‘D’ cause the initial transition of the<br />

system from opaque to transparent around 50 G as shown in<br />

Figure 1(b). Whereas, the decrease of transmitted intensity above<br />

150 G <strong>for</strong> 0.6 G/s is caused by the increase in ‘z’.<br />

The aggregation time (t c<br />

), at a given H 0<br />

depends on the competition<br />

between the magnetic <strong>for</strong>ce and viscous <strong>for</strong>ce experienced by<br />

the oil droplets in the carrier liquid. This t c<br />

is the time required<br />

<strong>for</strong> aggregation of two oil droplets of radius 'a' containing the<br />

magnetic nanoparticles, when they are separated by a distance<br />

'r' in a medium with viscosity 'h' . For lower ramp rates, external<br />

field exposure time is longer and sufficient (> t c<br />

) so that the tubes<br />

can attain the maximum permissible dimensions (by aggregation<br />

of oil droplets) <strong>for</strong> a given H 0<br />

. There<strong>for</strong>e, both the diameter of the<br />

tubes and the proportion of the number of tubes to single chains<br />

increases as the external field ramp rate is decreased. This is also<br />

the reason why the tube waveguide transmission behavior plays<br />

a prominent role on transmitted intensity variation at low ramp<br />

rate (0.6 G/s). For higher ramp rates (field exposure time < t c<br />

),<br />

only short chains are able to <strong>for</strong>m, which are unable to arrange<br />

themselves to <strong>for</strong>m tubes. The scattering effect by the short field<br />

induced chains dominates on the transmitted intensity output and<br />

there<strong>for</strong>e, it does not reach its equilibrium saturation value.<br />

The experiments mentioned above are also carried out while<br />

decreasing the H 0<br />

, immediately after reaching the maximum<br />

field (300 G), at the same ramp rate at which it is increased.<br />

Figure 3(b) shows the scattered pattern images, on a<br />

screen placed perpendicular to the incident light, but during<br />

19


IGC Newsletter<br />

Young <strong>Research</strong>er's Forum<br />

Figure 3: (a) Variation of transmitted light spot intensity during decrease<br />

in magnetic field at different ramp rates and (b) scattered patterns at<br />

four different fields during the decrease at three ramp rates<br />

the decrese in H 0<br />

at ramp rates of 0.6, 1.67 and 10 G/s.<br />

Figure 3(a) shows the intensity variation of the transmitted<br />

light spot [upper right part of ring circumference of<br />

Figure 3(b)] as a function of decreasing H 0<br />

. During the decrease<br />

in H 0<br />

, the transmitted intensity increases unusually and peaks at<br />

68 G be<strong>for</strong>e falling sharply to zero value below 50 G. When H 0<br />

is decreased at 0.6 G/s, the ring structure gradually disappears<br />

and intensity of the transmitted spot on its circumference<br />

reaches its maximum at 68 G be<strong>for</strong>e complete disappearance<br />

[Figures 3(a & b)]. We attribute the enhanced transmission peak<br />

observed <strong>for</strong> the field induced array of random tubes to the<br />

localized waveguide resonances related to individual tubes.<br />

To get further insight into the observed enhanced transmission,<br />

the zero order transmittance spectra of the emulsion at different<br />

H 0<br />

during the decrease in field (ramp rate~ 0.6 G/s) are recorded<br />

using a fiber optical spectrophotometer and is shown in<br />

Figure 4. With the decrease in H 0<br />

, the transmittance of the emulsion<br />

increases <strong>for</strong> the entire range of wavelengths (λ=450-800 nm).<br />

Besides, an enhanced asymmetric peak is also observed in each<br />

transmission spectrum, which shows a red shift with the decrease<br />

in H 0<br />

. The transmittance spectra <strong>for</strong> H 0<br />

= G i.e. the disordered<br />

system of scatterers can be explained from the calculation<br />

of Q ext<br />

using the Mie scattering theory. For λ =450-800 nm,<br />

ka=2.04-1.15, the corresponding Q ext<br />

is significantly high<br />

(3.65-1.48) which results in very less transmittance<br />

I t<br />

/I 0<br />

(~ 2.155×10 -36 – 3.451×10 -15 ). But, <strong>for</strong> λ in the range<br />

800-1000 nm (ka=1.15-0.91), Q ext<br />

decreases from 1.48<br />

to 0.58, thereby reducing the scattering or increasing<br />

the fraction of incident light intensity that is transmitted,<br />

I t<br />

/I 0<br />

(~ 3.451×10 -15 – 2.15×10 -6 ).<br />

The transmittance over the entire wavelength range increases<br />

with the decrease in H 0<br />

, due to the deaggregation of oil droplets,<br />

the length ‘z’ of the tubes decreases on decreasing the field. This<br />

increases the number of tubes and there<strong>for</strong>e decreases their<br />

D. This arrangement takes place <strong>for</strong> the uni<strong>for</strong>m distribution of<br />

the field induced structures throughout the entire volume of the<br />

ferrofluid emulsion, so as to reach the minimum energy state.<br />

The fractional aperture area can be considered to remain more<br />

or less the same after the redistribution of the tubes at different<br />

Figure 4: Transmittance spectra of the ff emulsion at different magnetic<br />

fields when decreased at a ramp rate of 0.6 G/s from 300 G. The solid<br />

lines are the best fits obtained using Fano resonance profile<br />

H 0<br />

. For a given fractional aperture area of an array of aperiodic<br />

waveguides, the transmittance increases with increase in the<br />

number of tubes.<br />

The reasons <strong>for</strong> the red shift of asymmetric peak, observed in the<br />

transmittance spectra, on decreasing H 0<br />

, enumararated below. The<br />

light transmission process, through an array of tube waveguides<br />

with their dimensions in the subwavelength regime or of the order<br />

of the wavelength of incident electromagnetic wave, involves<br />

two interfering contributions propagating through two different<br />

scattering paths. The first path is non-resonant and is related to<br />

direct scattering of the incident light field through the waveguides.<br />

The observed non-resonant transmittance variation can also be<br />

characterized well by the extension of Bethe-Bouwkamp theory,<br />

<strong>for</strong> a circular hole waveguide with negligible thickness in a<br />

perfectly electrical conducting film, to that with definite thickness<br />

and real metal. The non-resonant transmission continuum<br />

of direct scattered states related to individual waveguides is<br />

detected as background in the transmission spectra. The second<br />

path corresponds to a resonant contribution, as it first goes<br />

through the localized resonance state of the waveguide be<strong>for</strong>e<br />

being scattered to outside continuum. The interference between<br />

the transition amplitudes associated with each scattering path<br />

gives the resulting light transmittance with an asymmetric peak in<br />

the spectra, known as Fano resonance as shown in Figure 4. The<br />

transmittance spectra have been fitted with the functional <strong>for</strong>m of<br />

Fano resonance I ∝ ( F + ω − ω )<br />

2<br />

2 2<br />

[ g ] [( ω − ω ) + ]<br />

0 0<br />

g<br />

and variation of the fit parameters ω 0<br />

, F and g as a function<br />

decreasing H 0<br />

are shown in Figure 5. The actual resonance<br />

position i.e. the resonant wavelength (ω 0<br />

) of Fano resonance<br />

in the transmission spectra appears near the waveguide cut-off<br />

wavelength (λ c<br />

) <strong>for</strong> single hole, array of aperiodic and periodic<br />

holes in a conducting film.<br />

For a circular hole waveguide in a perfectly electrical conductor<br />

film, λ c<br />

=3.4r , where r is the hole radius. The ω 0<br />

that appears<br />

around this λ c<br />

shows a red shift with the decrease in waveguide<br />

length, which is demonstrated both numerically in perfectly<br />

conducting film, real metal and experimentally in single hole<br />

in a metal (Ag) film. There<strong>for</strong>e, we attribute the red shift of ω 0<br />

[Figures 4 & 5], to the decrease in tube length z on decreasing<br />

20


Young <strong>Research</strong>er's Forum<br />

Figure 5: Fano resonance fit parameters ω 0<br />

, F and g as a function<br />

of external magnetic field H 0<br />

(during decrease)<br />

H 0<br />

. Interestingly, <strong>for</strong> H 0<br />

of 70 G, the extracted value of ω 0<br />

is<br />

the incident light wavelength (633 nm) at which the resonantly<br />

enhanced transmission is also observed almost at the same<br />

field (68 G) [Figure 3 (a)], which corroborates our argument of<br />

transmission resonance to the localized waveguide resonance.<br />

The λ c<br />

of a waveguide is directly related to its lateral dimension<br />

(‘D’ in the case of tube). Though the ω 0<br />

of a waveguide is of the<br />

order of its λ c<br />

, the exact resonance position depends on the ‘z’<br />

of the waveguide. The resonant wavelength, <strong>for</strong> the circular hole<br />

waveguide, coincides exactly with the cut off wavelength <strong>for</strong> the<br />

waveguide length z=r/3. There<strong>for</strong>e, the observed red shift of<br />

resonance position (ω 0<br />

) in the transmittance spectra [Figures 4 &<br />

5] also shows that on decreasing H 0<br />

, the effect of decreasing ‘z’<br />

dominates over the decreasing ‘D’, on determining the resonance<br />

peak position. Further, on decreasing H 0<br />

, at first ‘z’ decreases by<br />

deaggregation of oil droplets from the chains. Then, the spatial<br />

rearrangement takes place <strong>for</strong> the uni<strong>for</strong>m distribution of the<br />

field induced structures throughout the entire volume resulting<br />

in the decrease of ‘D’, so as to reach the minimum energy state.<br />

There<strong>for</strong>e, the rate of decrease in ‘z’ is faster than their ‘D’, thereby<br />

making the effect of decreasing ‘z’ more prominent on ω 0<br />

.<br />

The discrete localized state corresponding to the resonant state<br />

of a waveguide depends on its dimension. At higher H 0<br />

(e.g.<br />

300 G), due to high coupling constant L, there is very less<br />

dimensional distribution (z ±Dz & D ±DD) of the waveguides.<br />

On decreasing H 0<br />

, this dimensional distribution increases along<br />

with the decrease in ‘z’ and ‘D’, as mentioned earlier. This leads to<br />

increase in the number of discrete resonant states of the random<br />

array of field induced tube waveguides. There<strong>for</strong>e, the transition<br />

amplitude associated with the resonant scattering path i.e. the<br />

discrete localized states, increases as compared to non-resonant<br />

direct scattering path as mentioned earlier. The increase in the<br />

ratio of these two transition amplitudes, defined as the asymmetry<br />

parameter F, with the decrease in H 0<br />

, as shown in Figure 5,<br />

demonstrates this phenomenon. The actual resonant wavelength<br />

(ω 0<br />

) lies somewhere between the observed maximum and<br />

minimum of the asymmetric transmittance spectra indicated in<br />

Figure 4 and the value of parameter F defines the relative deviation.<br />

In the situation ⎜ F ⎜→ ∞, the ‘ω 0<br />

’ coincides with the maximum<br />

IGC Newsletter<br />

of the spectra, <strong>for</strong> F=0 the ω 0<br />

coincides with minimum and <strong>for</strong><br />

F =1 it is located exactly half the distance between the maximum<br />

and minimum of the spectrum. With the increase in the value<br />

of F, as H 0<br />

is decreased, the ω 0<br />

<strong>for</strong> a transmittance spectrum<br />

shifs more towards its maximum. This is also evident from the<br />

extracted values of ω 0<br />

[Figure 5] in the observed transmittance<br />

spectra [Figure 4] <strong>for</strong> different H 0<br />

.<br />

The non-resonant background in the transmittance spectra<br />

depends on the number of tube waveguides, their dimensions<br />

(z & D) and their dimensional distribution (z ±Dz & D ±DD)<br />

at a particular H 0<br />

. On decreasing H 0<br />

, if only the ‘z’ would have<br />

changed while keeping the other factors constant; only a red<br />

shift of transmittance resonance position (ω 0<br />

) with similar<br />

background would have been observed, as discussed earlier.<br />

At the resonance, the phase of the scattering wave changes<br />

sharply by p. Thus, the interaction of scattering waves results<br />

in constructive and destructive interference phenomena located<br />

very close to each other, corresponding to a maximum E max<br />

and minimum E min<br />

of the transmission, respectively. The width<br />

of the resonance is proportional to the distance between them,<br />

g ~⎜E max<br />

- E min<br />

⎜. Due to the increase in the number discrete<br />

localized states of the array of random waveguides with the<br />

decrease in H 0<br />

, the number of possible resonant scattering paths<br />

to the continuum through these states also increases. This leads<br />

to an increase in the number of possible interferences among<br />

the transition amplitudes corresponding to different resonant<br />

scattering paths. Since each of these interferences has both<br />

constructive and destructive interferences, it results in the<br />

occurrence of many resonances. This leads to the observation of<br />

many overlapped resonances in a single transmittance spectrum<br />

and increases the width of transmittance spectra when H 0<br />

is<br />

decreased, as demonstrated by the increase in g [Figures 4 &<br />

5]. Note that similar broad Fano transmission resonance with<br />

changing background is also observed <strong>for</strong> an array of aperiodic<br />

uncorrelated holes on a conducting film. There<strong>for</strong>e, the increase<br />

in transmittance and red shift of the resonance position (ω 0<br />

),<br />

observed on decreasing H 0<br />

, indicates that the decrease in ‘z’ has<br />

the dominant contribution over other field dependent variable<br />

parameters on the resulting transmitted intensity behavior<br />

through the field induced array of randomly uncorrelated tube<br />

waveguides in the emulsion. Whereas, the increase in asymmetry<br />

parameter F and resonance width (g), observed on decreasing<br />

H 0<br />

, indicates that the increase in dimensional distribution (z ±Dz<br />

& D±DD) of the tube waveguides also plays significant role on<br />

the resulting transmitted intensity behavior. On decreasing the H 0<br />

below 65 G, L becomes less than unity, which leads to complete<br />

dissolution of the field induced structures.<br />

Reported by Junaid Masud Laskar<br />

Smart Materials Section<br />

Metallurgy and Materials Group<br />

21


IGC Newsletter<br />

Conference/Meeting Highlights<br />

Theme Meeting on Severe Accident Analysis and Experiments<br />

April 26-27, 2012<br />

Panel members Shri H. G. Lele, RSD, BARC, Shri S.S. Bajaj, Chairman, AERB, Shri S. K. Mehta, Former Director, Reactor Group, BARC, Prof.<br />

K. Iyer, Mechanical Engineering Department, IIT Bombay, Dr. P. Chellapandi, Director, RDG, IGCAR and Shri P. K. Malhotra, NPCIL on the dais<br />

Following the Fukushima events, there is a need to review and<br />

re-assess the strategies adopted in various nuclear facilities<br />

<strong>for</strong> severe accident management. This is essential <strong>for</strong> evolving<br />

a robust accident mitigation and management guideline <strong>for</strong> all<br />

future nuclear reactors. A theme meeting was organized by<br />

SRI-AERB in collaboration with IGCAR, at Anupuram during<br />

April 26-27, 2012 with an aim to take a consolidated look at the<br />

current status of on-going analytical and experimental research<br />

work on various aspects of severe accident management,<br />

within the DAE units as well as at academic institutions. It is<br />

envisaged that the outcome of the deliberations would provide<br />

the necessary thrust and direction in focusing research<br />

activities in challenging areas and reorient collaborative<br />

research activities among the participating organizations.<br />

Shri S.S. Bajaj, Chairman, AERB, in his introductory remarks,<br />

indicated that events at Fukushima have changed the perspective<br />

of nuclear communities' in responding to such events and<br />

evolving mitigating measures. Shri S.K. Chande, Vice Chairman,<br />

AERB delivered the key note address highlighting the shift<br />

in focus and practices in safety subsequent Fukushima. A<br />

total of twenty lectures were delivered by eminent invited<br />

speakers from various R&D organizations and academic<br />

institutions, on a wide range of issues relating to R&D on<br />

severe accidents in thermal as well as fast reactors. The<br />

theme meeting was concluded with a panel discussion chaired<br />

by Shri S. K. Mehta, Former Director, Reactor Group, BARC.<br />

Shri S.K. Chande, Vice Chairman, AERB delivering the key note address<br />

Reported by Seik Mansoor Ali, SRI, AERB<br />

22


Conference/Meeting Highlights<br />

IGC Newsletter<br />

Theme Meeting on Robust Instrumentation and Control <strong>for</strong> Nuclear Facilities (RINF-2012)<br />

May 29, 2012<br />

Dr. P. R. Vasudeva Rao, Director, Chemistry Group, IGCAR inaugurating the theme meeting. Shri S. A. V. Satya Murty, Director,<br />

EI&RSG, IGCAR, Shri C. K. Pithawa, Head, Electronics Division, BARC and Shri D. Thirugnanamurthy, EID, IGCAR are on the dais<br />

A one day theme meeting on "Robust Instrumentation and<br />

Control <strong>for</strong> Nuclear Facilities" (RINF-2012) was organised<br />

by <strong>Indira</strong> <strong>Gandhi</strong> <strong>Centre</strong> <strong>for</strong> <strong>Atomic</strong> <strong>Research</strong> at Sarabhai<br />

Auditorium, Homi Bhabha Building, Kalpakkam on May 29,<br />

2012. The theme meeting started with welcome address by<br />

Shri S. A. V. Satya Murty, Convenor, RINF-2012 and Director,<br />

Electronics, Instrumentation and Radiological Safety Group,<br />

IGCAR.<br />

Shri S. A. V. Satya Murty highlighted the importance of the<br />

theme meeting particularly in the context of development of<br />

robust instrumentation <strong>for</strong> nuclear facilities and welcomed<br />

the eminent speakers, delegates from IGCAR, BARCF,<br />

BHAVINI and MAPS.<br />

Dr. P. R. Vasudeva Rao, Director, Chemistry Group<br />

inaugurated the theme meeting. He highlighted the vital<br />

role of instrumentation and control with respect to safety<br />

and availability of the nuclear reactor. He emphasized how<br />

important it is to provide robust and reliable instrumentation<br />

<strong>for</strong> nuclear facilities. He stressed the need <strong>for</strong> paying attention<br />

to design and the importance of redundancy. He mentioned<br />

the challenges faced because of fast developments in the field<br />

of electronics and computers and resultant obsolescence.<br />

Shri C. K. Pithawa, Head, Electronics Division, BARC delivered<br />

the keynote address on 'Neutron detectors <strong>for</strong> Prototype Fast<br />

Breeder Reactor'. He explained the methodology followed<br />

in designing the neutron detectors to work at very high<br />

temperatures <strong>for</strong> fast reactors, the challenges faced and their<br />

solutions to overcome.<br />

In the theme meeting, there were six invited talks by eminent<br />

professionals from IITM, <strong>Centre</strong> <strong>for</strong> Reliability, CEMILAC,<br />

BARC, ECIL and Ansh Technologies highlighting the various<br />

qualification methods to be followed in building robust<br />

instrumentation and control <strong>for</strong> nuclear facilities. The meeting<br />

was attended by more than one hundred and fifty delegates<br />

from IGCAR, MAPS, BHAVINI and BARC Facilities. There<br />

were excellent scientific interactions during the technical<br />

sessions. Shri D.Thirugnana Murthy, EID, Secretary, RINF-<br />

2012 proposed the vote of thanks.<br />

Reported by S. A .V Satya Murty, Convenor, RINF-2012<br />

23


IGC Newsletter<br />

Conference/Meeting Highlights<br />

Theme Meeting on Technological Advancement in Production of Enriched Boron<br />

<strong>for</strong> the Control Rods of Fast Reactors<br />

June 22, 2012<br />

Shri S.C Chetal, Distinguished Scientist and Director, <strong>Indira</strong> <strong>Gandhi</strong> <strong>Centre</strong> <strong>for</strong> <strong>Atomic</strong> <strong>Research</strong>, presenting the inaugural address<br />

A one day theme meeting on “Technological Advancement<br />

in Production of Enriched Boron <strong>for</strong> the Control Rods<br />

of Fast Reactors” was organized by <strong>Indira</strong> <strong>Gandhi</strong><br />

<strong>Centre</strong> <strong>for</strong> <strong>Atomic</strong> <strong>Research</strong>, Kalpakkam and Board of<br />

<strong>Research</strong> in Nuclear Sciences, (BRNS) Mumbai at the<br />

Sarabahai Auditorium, Homi Bhabha Building, IGCAR on<br />

June 22, 2012. The meeting started with the welcome<br />

address by Shri K.K.Rajan, Chairman, organizing committee<br />

and Director, Fast Reactor Technology Group. Shri K.K.Rajan<br />

highlighted the relevance of the theme meeting in the<br />

context of the Indian fast breeder reactor programme and<br />

welcomed the invited speakers, delegates and guests. He<br />

lauded the ef<strong>for</strong>ts of Shri R.Subramaniam, Former Head<br />

of Chemical Technology Section at IGCAR who laid the<br />

foundation <strong>for</strong> the boron enrichment program at IGCAR and<br />

Dr. C. Anand Babu, Associate Director, Component<br />

Development Group <strong>for</strong> his contributions in leading the<br />

research and development programme <strong>for</strong> boron enrichment.<br />

Shri S.C Chetal, Director, IGCAR inaugurated the theme<br />

meeting and in his inaugural address outlined the importance<br />

of enriched boron carbide as absorber rod material <strong>for</strong> control<br />

of fast reactors. He also in<strong>for</strong>med that boron carbide pellets to<br />

be used in the control rods of PFBR are ready <strong>for</strong> shipment at<br />

BARC. He reiterated that the development of this technology<br />

is a culmination of the combined ef<strong>for</strong>ts of BARC, IGCAR and<br />

HWB. He stressed the need to initiate research and development<br />

<strong>for</strong> recycling the enriched boron carbide from the used control<br />

rods of fast reactors. During the meeting 5 kg of 90 percent<br />

enriched boric acid powder produced at the boron enrichment<br />

plants at IGCAR was handed over to Shri K.Nagarajan,<br />

Associate Director, Chemistry Group <strong>for</strong> further processing in<br />

the inaugural session.<br />

Dr. C. Anand Babu in his key note address detailed the road<br />

map of the boron enrichment in the country. He particularly<br />

recalled the uphill challenges and hurdles that were overcome<br />

in achieving the present level of technological maturity. In<br />

the theme meeting there were eight invited lectures. The<br />

lectures were organized into three different technical sessions<br />

as process development <strong>for</strong> boron enrichment, technology<br />

development <strong>for</strong> conversion to enriched elemental boron and<br />

production and operating experience on absorber materials.<br />

The lectures were delivered by experts in this field from<br />

IGCAR, BARC and Heavy Water Board. Engineers from<br />

the various groups of IGCAR, BHAVINI, BARC facilities,<br />

academic institutions and industries like THERMAX were also<br />

participants to this theme meeting. There were a total of 90<br />

participants <strong>for</strong> the theme meeting. The scientific interactions<br />

during the technical sessions were beneficial and provided<br />

valuable inputs <strong>for</strong> the design, per<strong>for</strong>mance assessment<br />

and further improvement of the processes in the production<br />

of enriched boron <strong>for</strong> fast reactors. The meeting concluded<br />

with a vote of thanks by Dr. B.K.Sharma, Chairman, Techncial<br />

committee.<br />

Reported by G. Padmakumar, Convenor<br />

24


Awards & Honours<br />

IGC Newsletter<br />

Visit of Dignitaries<br />

Honorable Justice Shri S. Tamilvanan from Madras High Court<br />

accompanied with his wife Prof. V. Manimozhi visited the<br />

<strong>Centre</strong> on April 14, 2012. During the meeting they were briefed<br />

about the challenges and opportunities of <strong>Atomic</strong> Energy by<br />

Dr. M. Sai Baba, Associate Director, Resources Management<br />

Group. After the meeting Honorable Justice Shri S. Tamilvanan<br />

and Prof. V. Manimozhi visited the Fast Breeder Test Reactor and<br />

Madras <strong>Atomic</strong> Power Station.<br />

Honorable Justice Shri S. Tamilvanan from Madras High<br />

Court and Prof. V. Manimozhi during their visit to the<br />

Fast Breeder Test Reactor<br />

Dr. K. Gireesan and Dr. T. S. Radhakrishnan from MSG and collaborators at CIPET-Chennai, have received the<br />

2 nd National Award (2011) <strong>for</strong> Technology Innovation under the category, Polymers in Public Health Care, instituted<br />

in various fields of Petrochemicals and Downstream Plastic Processing Industry by the Department of Chemicals and<br />

Petrochemicals, Government of India, <strong>for</strong> their work on the "Design and Development of Sensor array Hemet <strong>for</strong> whole<br />

Head Magnetoencephalography System"<br />

Dr. M. Vijayalakshmi from MMG has been elected, Fellow of the Electron Microscopy Society of India in recognition of her<br />

outstanding scientific contributions in the field of "Electron Microscopy".<br />

Best Paper / Poster Awards<br />

Awards & Honours<br />

Embedded-System Based Controller <strong>for</strong> Measuring Displacement of Reactor Vessel of FBTR<br />

Shri Kalyan Rao Kuchipudi, Shri Sushant Patil, Shri S. Sridhar, Shri M. Muthukrishnan, Shri K. V. Sureshkumar,<br />

Shri S. Varadharajan, Shri B. Anandapadmanaban and Shri G. Srinivasan from ROMG<br />

8 th Control and Instrumentation System Conference (CISCON 2011) Manipal University, Manipal, November 2011<br />

Best Paper Award<br />

Effective Nondestructive Imaging of Defects in Engineering Components<br />

Dr. B. P. C. Rao, Dr. T. Jayakumar, Shri S. Thirunavukkarasu, Shri W. Sharatchandra Singh, Shri G.K. Sharma,<br />

Shri Anish Kumar and Dr. C. Babu Rao from MMG<br />

18 th World Conference on Nondestructive Testing, Durban, South Africa, April 16-20, 2012<br />

Best Presentation Award<br />

Logic Modeling and Benchmark Transients Simulation of Condensate System <strong>for</strong> Prototype Fast Breeder Reactor Operator<br />

Training Simulator<br />

Ms. Rashmi Nawlakha, Ms. N. Jasmine, Ms. H. Seetha, Shri B. Subba Raju, Shri K.R.S. Narayanan,<br />

Ms. T. L. Priyanka, Ms. T. Jayanthi and Shri S.A.V. Satya Murty from EI&RSG<br />

International Conference on Recent Advances in Engineering and Technology (ICRAET-2012)<br />

Hyderabad, April 29-30, 2012<br />

Best Paper Award


Cassia fistula (Golden shower tree)<br />

Dr. M. Sai Baba,<br />

Chairman, Editorial Committee, IGC Newsletter<br />

Editorial Committee Members: Dr. K. Ananthasivan, Shri M.S. Chandrasekar, Dr. N.V. Chandra Shekar,<br />

Dr. C. Mallika, Shri K. S. Narayanan, Shri V. Rajendran, Dr. Saroja Saibaba and Dr. Vidya Sundararajan<br />

Published by Scientific In<strong>for</strong>mation Resource Division, IGCAR, Kalpakkam-603102

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