NUCLEAR

Prime Minister Dr.Manmohan Singhwriting his message when he visitedthe Centre for Advanced Technology,Indore on December 17, 2005 torename it as “Raja Ramanna Centrefor Advanced Technology”

First front endinstalled onIndus-2 bendingmagnet

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On December 17, 2005, theHon’ble Prime Minister Dr. Man-mohan Singh dedicated the Centre forAdvanced Technology, Indore, in thememory of Dr. Raja Ramanna.Following are the excerpts of hisaddress.

“It gives me great pleasure toparticipate in this function to renamethe Centre for Advanced Technologyof the Department of Atomic Energyas the Raja Ramanna Centre forAdvanced Technology. It is also anhonour for me to dedicate theSynchrotron Radiation Source Indus-II to the nation today.

As Pandit Nehru said, scientificinstitutions are the temples of modernIndia and play a key role in the

gigantic task of national developmentand nation building. India’s atomicenergy programme has beenrecognized in the country and theworld over, as a shining example ofself-reliance and outstandingachievement.

This programme has benefitedfrom the dedication of legendaryscientists such as Dr. Homi Bhabha,Dr. Homi Sethna and stalwarts suchas Dr. P.K. Iyengar, Dr. M.R.Srinivasan, Dr. R. Chidambaram, andDr. Kakodkar, the present Chairmanof the Commission.

Dr. Raja Ramanna was a shiningstar in this galaxy of outstandingscientists. An illustrious son of India,he served the country in variouscapacities including as Chairman ofthe Atomic Energy Commission and

as Minister of State for Defence,Dr. Ramanna was a polymath. Hemastered the frontiers of science; atthe same time, he was an authority onIndia’s scriptures like the Gita andUpanishads; also an accomplishedpianist and deeply knowledgeableabout both Western and Indianclassical music. He was also a leaderwith exceptional qualities whoinspired generations of scientists. TheBARC Training School, which hehelped to found in 1957, was a turningpoint in the development of DAE.Dr. Raja Ramanna was a charmingman blessed with great spontaneity. Itwas my privilege and pleasure to haveknown him personally.

Dr. Ramanna was associated with

key milestones in India’s nuclearprogramme. He was involved withbuilding the country’s first researchreactor Apsara. At his initiative, theconstruction of the Variable EnergyCyclotron was taken up in Kolkata.He also gave impetus to the fastreactor programme in the country inthe 70’s and 80’s. As the Director ofBARC, he was the leader of the teamwhich conducted India’s first nucleartest in 1974. Between 1978 and 1981he was Scientific Adviser to RakshaMantri.

Dr. Ramanna was instrumental insetting up this Centre for AdvancedTechnology in 1984. This Centre wasestablished with a view to masteringadvanced technology, especially in theareas of lasers and accelerators. Theprogress achieved by the Centre

vindicates Dr. Ramanna’s vision, bycontributing to the nation’s needs aswell as placing India on theinternational nuclear map. The Centrehas played a pivotal role in deliveringvery high quality components andsubsystemsfor the world’s biggestparticle accelerator, the Large HadronCollider, being set up by CERN inGeneva.

The scientific and technologicalabilities of our scientists match thebest the world over. This gives us theconfidence to pursue increasedexchanges with the outside world withIndia as an equal partner with the mostadvanced countries in the world. Justlast week, India joined a select groupof countries participating in ITER –the International Thermo NuclearExperimental Reactor project and Icongratulate DAE for thisachievement.

I am optimistic that throughconstructive dialogue with theinternational community, we will soonbe part of the mainstream with fullcivilian nuclear cooperation betweenIndia and international partners. Ournon-proliferation track record and ourscientific credentials will only add toIndia’s weight in internationalcooperative endeavours to harness allthe applications of nuclear energy, forthe country’s social and economicdevelopment, for meeting ourgrowing energy needs, and for thegreater glory of global scientificadvancement as a whole. In thisjourney of excellence, this Centre, theRaja Ramanna Centre for AdvancedTechnology, will have a critical roleto play.

Let me take this opportunity toconvey to you – the members of theDAE family – the deep appreciationand gratitude of the nation for yourcommitment and your scientificaccomplishments. You have our fulland unstinted support for yourendeavours.”

High resolution x-ray diffraction beamline under installation in Indus-2

experimental hall

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Within a few years of EnricoFermi’s demonstration that nuclearenergy could be controlled in a safeand reliable manner and even beforeIndia could achieve independence,Dr Homi Bhabha formulated his grandvision for the exploitation of atomicenergy for peaceful purposes.Dr. Bhabha wanted India to be self-reliant, in this new emergingtechnology right from the beginning.In line with his vision the first researchReactor Apsara was built withindigenous efforts in the year 1956.This was followed up by theconstruction and successfulcommissioning of CIRUS researchreactor in 1960. These early gainscatapulted India into an ambitiousnuclear programme, after which therewas no looking back.

Conception of Dhruva ReactorDuring early seventies, a strong

need was felt for building a researchreactor with higher neutron flux tomeet the growing demand ofradioisotope production and advancedresearch in basic sciences andengineering. This led to the setting upof the fifth research reactor R-5 atBARC, which was later named“Dhruva” by Giani Zail Singh, thethen President of India. Theconstruction of Dhruva was animportant milestone towardsdevelopment and implementation ofindigenous nuclear reactor technologyin India.

Dhruva is an example of a viablesystem, engineered within the limitedmeans available in the country at thattime, catering to production ofradioisotopes of high specific activityas well as diverse requirements of abroad based multidisciplinary user

community. This high neutron fluxreactor was designed, constructed andcommissioned entirely by Indianscientists and engineers and it reflectsthe country’s resolve to achieve self-reliance in the nuclear reactortechnology.

Dhruva attained first criticality onAugust 8, 1985 and was dedicated tothe nation on November 11, 1985 byLate Shri Rajiv Gandhi, then PrimeMinister of India. Dhruva attained fullpower operation in January 1988.

The Reactor: Dhruva is a 100 MW

(thermal) research reactor having avertical core with metallic naturaluranium as fuel, heavy water asmoderator, primary coolant andreflector, producing a maximumthermal neutron flux of 1.8 x 1014

neutrons per cm2 per second. Heatfrom primary coolant is transferred toa secondary closed loop re-circulatingsystem of dematerialized light waterin a set of heat exchangers. Thesecondary coolant in turn is cooled byseawater. The sea-water coolant isdrawn from the Mumbai harbour bayand flows through the heat exchangers

Dhruva Completes Twenty Years of Service to the NationA. C. Tikku

Director Reactor Group, BARC

Dhruva at Trombay

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in a once-through mode. The reactorprovides facilities for basic andapplied research, material testing,production of radioisotopes andtraining of manpower.

Technological challenges anddevelopments in making of Dhruva:

Dhruva provided the right platformfor various technological develop-ments some of which were alsoadopted in the standardized Indianpressurized heavy water reactors(PHWR).

Reactor shielding design wassimplified by submerging the reactorvessel in a pool of light water thusreducing the Ar41 activity in theexhaust. This will also simplify thedisposal of solid active waste at thetime of decommissioning of thereactor.

The thermal shield on top of thereactor was designed keeping in mindthe ease of transportation from thefabricator’s premises to the reactor

site. Instead of using heavy metal slabswith cooling coils, a box type designusing a mixture of steel balls (filledat site) and water was adopted.

Coolant channels were designed assemi permanent structures to alloweasy replacement of coolant channels,if required.

In order to provide flexibility forany future changes in the fuel and thecore configuration, the positions of thefuel and shut off rods were madeinterchangeable. This requirementimposed a severe space constraint foraccommodating shut off rod drivemechanism within the coolant channeldimensions. This challenge could bemet by an innovative design of drum-cum-damper assembly.

Stainless Steel reactor vesselweighing about 30 tons was fabricatedin the central workshop of BARC.Many evolving technologies such asplasma arc cutting of thick (50 mm)

SS plates, electron beam welding etcwere developed and successfullyemployed for the fabrication ofreactor vessel. Accurate dimensionaland alignment checks for variouscomponents of the reactor vessel weredone with the help of laserinterferometre.

Challenging task of fabricating 300mm diametre zircaloy-2 re-entrantcans, for neutron beam holes, was metby rolling and seam welding zircaloy-2 plates. Since uniform thicknesscould not be achieved through hotrolling, a special cold rolling facilitywas set up at Mishra Dhatu Nigam Ltd(MIDHANI) Hydrabad. Electronbeam welding of zircaloy-2hemisphere to the zircaloy-2 tube wascarried out at DRDL Hydrabad, aftersuccessful developmental trialskeeping the weld distortions to aminimum. As zircaloy-2 is a highlyreactive material and absorbs lot ofoxygen and nitrogen at elevatedtemperatures, the welds were made in

Control room of Dhruva

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a glove box under an inert argonatmosphere.

The 300 mm diametre zircaloy-2reentrant cans were rolled into thestainless steel nozzles of the reactorvessel. Till then experience of rollingcylindrical sections of stainless steeland zircaloy up to a diametre of 125mm only was available in the country.Extensive mock-up trials were carriedout to get perfection in the quality ofrolled joint. The mock joints werequalified by pullout test. Thechallenging task of accurate alignmentof Zircaloy-2 reentrant cans with thebeam hole tubes (located in biologicalshield concrete) was achieved afterextensive mock up trials.

Design of the fuelling machine forthe safe and reliable operation, wasanother challenging work. Themachine was to be designed to handletwo nine metre long fuel assemblieswith adequate neutron and gammashielding, heavy water cooling andprovision for making a leak tight jointwith the coolant channel. For this thefuelling machine, (having lead filledcompartments for radiation shielding)

weighing over 300 Tons was designedto have alignment accuracy of± 0.25 mm.

Utilization of DhruvaDhruva has been extensively used

for basic and applied research in thefrontier areas of science andtechnology, and radioisotope

production. Besides utilization ofregular irradiation facilities for thesepurposes, some of the fuel and otherin-core positions have also been usedfor carrying out certain specificengineering experiments.

Radioisotope Production: The highthermal neutron flux, adequate excessreactivity and the large irradiationvolumes enable large-scale productionof radioisotopes with high specificactivity. This results in handling andprocessing of comparatively reducedvolume of radioactive material. Thedesign provision has been made forloading and unloading of radioisotopesamples on power. Nearly 70 differentradionuclides produced in reactor areprocessed and supplied in variousradiochemical forms. Bulk of theradionuclides prepared are used innuclear medicine, agriculturalresearch and industrial applications.CIRUS and Dhruva, working intandem, meet all the requirements ofradioisotopes. During recent longoutage of CIRUS for refurbishment,Dhruva alone met all the radioisotoperequirements.

Radioisotopes Mo99, I131, Sm153,

Fuelling machine of Dhruva Reactor

Production of radioisotopes

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P32, Cr51 for medical use are producedand supplied weekly / fortnightly.About 100TBq (~2700Ci) of theseradiochemicals are supplied to about200 nuclear medicine centres in thecountry per annum. This caters toabout 2.5 lakh patient investigationsinvolving diagnostic and therapeuticapplications in a year. I125 which has amuch better gamma merit ratio ascompared to I131 is the recent additionto the variety of radioisotopes formedical uses. I125 is used world wide

List of Major Radionuclides Produced in theReactor and their Applications

Radio nuclide Period of Applicationirradiation

Mo99-Tc99m 1 week Preparation of Tc99 radiopharma-ceuticals for diagnosis

I131 3 weeks Diagnosis and therapy of thyroiddisorders and thyroid cancer

P32 6-8 weeks Radionuclide therapy & P32- labelednucleotides

Cr51 1 week RBC labeling-for studies in biology etc.

Sm153 1 week Radionuclide therapy- treatment ofbone pain in metastatic cancer

Ho166 1week Radionuclidic therapy- treatment ofrheumatoid arthritis

I125 2 weeks RIA, brachytherapy of cancers, X-raysource etc.

Sc46 1 week Sediment transport, underground waterseepages studies

Hg203 2-3 months Mercury inventory studies

Br82 4-7 days Leak detection, residential timedistribution measurements

Au198 1 week Seepage, sediment transport studies inhydrology

Ir192 3 months Industrial radiography & brachytherapy

for radioimmunoassay (RIA) and asbrachytherapy source for treatment ofeye and prostate cancer. To meet thegrowing demand of radioisotopes andto facilitate production of I125, secondisotope production tray rod assemblywas suitably modified. This assemblyhas facility for Irradiation of Xenongas for production of Iodine-125isotope and can be handled on power.

Radioisotopes produced areused in industries in eco-benigntechnologies (e.g., Radiation

vulcanization of rubber latex,radiation sterilization of medicalproducts, radiation cross linking, etc.)and also in the treatment of domesticand industrial waste (e.g., radiationhygienisation of sewage sludge,treatment of flue gases, etc.). Radionuclides like Br82, Hg203, Au198, Sc46,La140 Na24 and others used for leakageand blockage detection in buried pipelines, Residence Time Distribution(RTD) studies in chemical reactors,sediment transport, effluentdispersion, seepage studies in canalsand dams, etc., are produced againstspecific requirements of the users.Ir192 is produced regularly for use inindustrial radiography andbrachytherapy.

Though there is no designprovision for regular production ofCo60 radioisotope in Dhruva, two fuelpositions were used for producingcobalt-60 of high specific activity inlarge quantities. Co60 is used forradiation sterilization of medicalproducts.

Reactor produced radionuclidesfor miscellaneous applications thatsupport basic research in the countryhave been an important area of focus.

Neutron Beam Research: Neutronbeam research at BARC received agreat boost with the availability ofDhruva. In Dhruva two main newfeatures are introduced, namely,through-tubes and neutron guides.Through tubes provide a clean thermalneutron beam picking almost from thecentre of the core. A Neutron Guide-Tube Laboratory (GTL) withadditional instruments having specificfeatures has been built, adjacent to thereactor hall. Two nickel coatedneutron guides, emanating from abeam port inside the reactor hall aretaken into this laboratory.

A neutron beam shielded tunnel(100 Te in weight) has been installedat neutron beam hole TT-1015 whichprovides multi-ports for neutronscattering experiment, thus expanding

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Experimental setup around Dhruva

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the scope of research facilities. ANational Facility for Neutron BeamResearch (NFNBR) has been createdas a part of the Solid State PhysicsDivision (SSPD) at BARC to cater tothe needs of the Indian scientificcommunity in the field of neutronbeam research. Scientists fromBARC, other DAE units, universitiesand national laboratories use thesefacilities through collaborativeresearch projects. SSPD scientists notonly actively participate in theexperiments and analysis, but alsohelp the visiting scientists inunderstanding the intricacies ofneutron beam research. Many of thesecollaborations are being supported byUGC-DAE Consortium for ScientificResearch,BRNS,and other agencies.

There are 8 instruments in theReactor Hall and 4 in the annexedGuide Tube Laboratory (GTL). In thereactor hall, two profile analysispowder diffractometres and the high-Q diffractometers have been providedspecifically for structure studies ofliquid and powder samples. Theseinstruments utilize one or more linearHe3 position sensitive detectors.Usage of multi detector (5 PSDs laidside by side with some overlaps)system, covering an angular range of , has improved thethroughput substantially. In fact nowit is possible to record a diffractionpattern in a few minutes time, whichwas hitherto not possible.

In the guide tube laboratory, on G2neutron guide, there are two SmallAngle Neutron Scattering (SANS)instruments-a double crystal basedand a conventional type, and a neutronreflectometre. A neutron spin echospectrometre was test-operated at theend of neutron guide G1 and now it isused in the polarised small anglescattering mode.

In the immediate aftermath of thediscovery of High-T

c oxide

superconductors in 1987, the singlecrystal diffractometre was extensively

used in powder mode to recorddiffraction patterns for a very largenumber of such compounds and thestructure parametres were refined byprofile refinement. Subsequently,several single crystal investigations,notably on ferroelectric crystals havebeen carried out.

The profile analysis unpolarisedneutron diffractometres have been theworkhorses for studies of chemicaland magnetic structures and forinvestigating phase transformations indifferent classes of magnetic and non-magnetic compounds.

The SANS (low-Q) diffract-ometres in the Guide Tube Laboratoryhave been extensively used forinvestigating spatialstructures,inhomogeneities and agglomerates,with sizes of a few tens to thousandsof nanometres. The double crystalbased SANS diffractometre has beenused to study pore size, poremorphology and pore surfaceroughness in different natural rocks,coal and porous silicon, fluidpermeability and fractal dimensionsin membranes, heat treatmenteffect on nanoparticle agglomerates,precipitates in nuclear materials andmetallurgical alloy specimens.

Neutron Triple Axis Spectrometer(TAS), Filter Detector Spectrometer(FDS) or Quasi-ElasticNeutronSpectrometer (QENS) have beenused to study several dynamicalprocesses like phonon dispersions,magnetic excitations, rotational andtranslational diffusion in molecularsystems, etc.

The lattice dynamics of severalgeologically important minerals,available as natural single crystals,have been investigated by Triple Axismeasurements.

The neutron reflectometer issuitable for vertical sample geometryand has polarized/unpolarized option.Chemical and magnetic profiles ofthin film samples, multilayer, etc havebeen studied using polarised neutronreflectometry (PNR).

Neutron Activation Analysis: NeutronActivation Analysis (NAA) isessentially a non-destructive nuclearanalytical method, capable ofsimultaneous multi element analysis.It is one of the major applications ofa research reactor. Neutron beingnon-charged particle interacts withnuclei of isotopes of all elementsresulting in nuclear reactions. Theproduct formed in such a nuclearreaction might be a radioisotope. Bymeasuring the radioactivity formed,concentration of the isotope thatunderwent nuclear reaction ismeasured. Using the isotopicabundance, elemental concentration iscalculated. NAA has been used in alarge number of areas of research likebiology, geology, agriculture,anthropology, chemistry, engineeringand industry, fisheries, forestry,medicine, oceanography, pharmacyand forensics.

Pneumatic Carrier Facility (PCF)at Dhruva is utilized for irradiation ofshort-lived isotope samples whichrequire minimum transit time betweenthe completion of irradiation andcounting, for NAA. With higherneutron flux level in Dhruva PCF,elemental detection limits haveimproved and scope for studying shortlived isotopes is also enhanced.

Prompt Gamma Ray NeutronActivation Analysis (PGNAA) usingthermal neutron beam at Dhruvareactor has provided an avenue for theon-line analysis of various materials.A dedicated beam line for PGNAA isbeing developed. PGNAA and PCFwould enlarge the scope for activationanalysis as well as basic studies likenuclear spectroscopy.

Material and fuel testing: In order todevelop various fuel and structuralmaterials for Indian pressurized waterreactors, a facility has been installedin one of the 300 mm diametre radialbeam holes which would enableneutron irradiation of samples of fuel

3γ ≤ 2θ ≤ 140γ

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cladding, pressure tubes, end fittings,end shield etc. at controlledtemperature to assess the effect ontheir fracture toughness, impact andother mechanical properties at variousneutron fluences.

Dhruva core has provision forinstalling a facility for testing ofadvanced reactor fuels. An In PileLoop (IPL) Facility with high heatremoval capacity is being provided inDhruva. This facility can accom-modate fuel bundles of 500 MWePHWR and AHWR for testing. Thefacility will be commissioned soon

Man Power Training: During the last20 years a large number of Engineers,Scientists, operators and technicianshave been trained at Dhruva reactor.This trained manpower is contributingto our nuclear programmes in variouscapacities.

Special Experiments Carried Outat Dhruva

Validation of Thermal Hydrauliccodes: An instrumented Dhruva fuelassembly was irradiated in the reactorfor validating the thermal hydrauliccode used for estimating fuel cladtemperatures.

Study of Irradiation growth inZircaloy: The manufacturing route ofthe Zircaloy calandria tubes for theIndian PHWR was to be changed fromsheet rolling, bending and seamwelding to hot extrusion and coldpilgering to obtain seamless calandriatubes, for reasons of economy andfaster production rate. Samples ofwelded and seamless Zircaloycalandria tubes were test irradiated inDhruva reactor to study theircomparative in-pile growth behavior.These studies resulted in finalizationof manufacturing route for the PHWRcalandria tubes.

Study Of Applicability Of NeutronNoise Measurement Technique ForCondition Monitoring Of In-CoreComponents For Heavy WaterReactors: The neutron flux signal is

composed of a steady or meancomponent of neutron flux producedby the power operation of the reactorand a very small fluctuatingcomponent called noise. Analysis ofthe neutron noise from suitablylocated sensors is a proven techniqueto monitor the condition of the in-corecomponents of a light water reactor.However, it is generally felt that itsapplicability to a heavy water reactorwill be limited due to the unfavorabletransfer characteristics of thesereactors. An attempt was made tocheck the applicability of thistechnique for PHWRs. An experimentwas carried out at Dhruva using incore neutron detectors housed in aspecially fabricated assembly. Theresult of this experiment showed thesuitability of this technique to identifythe change in condition of reactorinternals which are otherwiseinaccessible.

Accelerated Life Testing Of Ion-Chambers: Neutron detectors ofvarious types and sensitivities aredeveloped by Electronics Division ofBARC and Electronics Corporaton of

India Ltd. (ECIL) Hydrabad. Beforethese detectors can be used for variousreactor regulation or protectionsystems they have to be tested for theirperformance under simulatedconditions. One of the Dhruva beamholes is being utilized for acceleratedlife testing of newly developed ionchambers.

Conclusion: Dhruva has completedtwenty years of operation withexcellent safety record. It hascontributed immensely to the nuclearscience and technology in general andneutron beam research andradioisotope production in particular.Utilisation of Dhruva, both in termsof quantity and quality, has been of avery high standard. The safety andavailability records for 20 yearsoperation proves the soundness of thebasic design and dedication ofoperations and maintenancepersonnel. The gains accrued with theconstruction, commissioning andoperation of Dhruva certainlyoverweigh the efforts invested in itsmaking and subsequent operation.

Research reactors Dhruva & Cirus at Trombay: A 3-D model mouldedin thermocol, created by Shri S.B. Jadhav, DCSE&M, DAE

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Jaduguda Uranium Mine, Singhbhum, Jharkhand :Some facts on Radioactivity, Radiation and Environmental Impact

A.C. KunduExecutive Director, UCIL

Jaduguda, with its uranium mineand mill, epitomizes the team effortof India's self reliance in nuclear fuelwith sustainable and environment -friendly development. Fears ofadverse radiation effects have no sci-entific basis and are fictitious.

Jaduguda, the magic place, sonamed by the discoverers in 1951because of the anomalous radioactiv-ity encountered in some of the rocksflanking the hill slopes about 2 kmfrom the historic copper workingsnear Rakha, is very special in manyways. India's first uranium mine andmill are located here epitomizing thesuccessful indigenous efforts at lo-cating and proving a deposit followedby mining and extracting uranium foruse in our nuclear reactors. The pio-neering scientific and technologicalefforts are of a very high order com-parable to those achieved byadvanced nations like USA , Russiaand others. Each facet of this greatendeavour being the first of its kindin India and represents the culmina-tion of a team effort that began afterIndia's independence under the greatvisionary and founder of India'satomic energy programme Dr. HomiJehangir Bhabha and carried for-ward with zeal by illustrious scientistsand engineers.

Prior to the discovery of radioac-tivity by Henri Becquerel in 1896 andnuclear fission in 1939 uranium wasbeing used as colouring agent in por-celain ware to provide the beautifulcanary yellows, a feature commonto water- bearing secondary uraniumminerals which infact help in locat-ing uranium deposits. Once the powerof the uranium atom was realised,things about uranium became secret.

Knowledge on processing materialswith radioactivity, radiations and theireffect on workers as well as envi-ronmental effects were also notshared. The first Geneva Conferenceon the Peaceful use of AtomicEnergy in 1955 at Vienna, presidedover by Dr. Bhabha and subsequentmeetings under IAEA provided aforum for sharing information on avariety of topics related to atomicenergy including the natural radiationenvironment and health related as-pects. The International Commissionon Radiological Protection (ICRP)founded in 1928, provides safetynorms for radiation workers and mostUN members including India adoptsuch norms for workers in uraniummines and other places where ionisingradiations are part of the workingenvironment.

Radioactivity and RadiationWhen we talk of radioactivity of

uranium, it pertains to ionizing radia-tions comprising alpha, beta andgamma during its decays through dif-ferent elements such as radium,radon and polonium to form radiogenic

lead. Unlike light or heat radiations,the radiations related with radioac-tive decay, as in the case of U, Thand K are 'ionising' i.e. they canremove electrons from an elementand thus can effect changes in livingcells. Such ionizing radiations arealso produced by cosmic rays thatcome from space and varies formplace to place depending on locationand also altitude. The penetrating pow-ers of radiations also vary dependingupon the type of radiation (Figure 1).

Thus radiations are omnipresentand are part of our environmentwherever such radioactive elementsare present even in trace quantities.The intensity of which, however,varies depending upon the amount ofuranium and other radioactiveelements like thorium and potassium.Thus the rock and soil that surroundsour home, office and other placescontribute to the radioactivity. Thefood we consume also gives us someradiations. Thus the average dose thata person receives from backgroundradiation in nature amounts to 1 to 2mSv per year. In some areas of highnatural background radiations such as

Figure 1

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the monazite-rich thorium bearingmineral sands of Kerala coastaltracts, radiation levels can reach upto20 mSv per year. Radon gas ema-nated from building materials contain-ing U and Th in trace quantitiesinside homes can add 1 to 3 mSv peryear (Figure 2).

In poorly ventilated home in a coldcountry radon contributions can behigh up to 20 mSv. The food chainlike milk and other items contain ra-dio elements like potassium and polo-nium in trace levels and also contrib-ute to the radioactivity. X-ray diagno-sis give a radiation dose ranging from0.2 to 5 mSv per examination is notuncommon. Thus radiations are ubiq-uitous and are part of life. A healthyadult of 70 kg, in fact, gives outradiation of some 7000 Bq.

Radiation Levels at JadugudaAirborne and ground radiometric

instruments in and around Jadugudaindicated that the rocks and soil cov-ered areas give a range of radiationlevels varying from 0.04 to 0.46 mGy/hr. The lower values representnatural background radiation whereasthe higher readings represent feebly

mineralized to ore zones with lowgrades (0.03 to 0.06% U3O8) whichare mined at Jaduguda. Because ofthe excellent recovery of uranium fromJaduguda ores (>90%) the tailingsproduced contain very low levels ofradioactivity. In comparison uraniumores processed by other countries like

Australia (> 0.1% U3O8) and Canada(1-18% U3O8) are of higher gradeand hence they need to take morecare in their mining and processing.The most positive aspect of process-ing such low grade ores is that radia-

tion hazards from gamma activity andradon levels are lower and the tail-ings produced contain wastes withvery low radioactivity. InternationalCommission for Radiological Protec-tion (ICRP) recommends that occu-pational exposure to radiation work-ers should not exceed 50 mSv in anyone year with a stipulation of 100 mSvover a period of five years which hasbeen adopted by the Atomic EnergyRegulatory Board (AERB) with arestriction to maximum dose limit of30 mSv in any one year. TheJaduguda mine is well ventilated toavoid the accumulation of radon. AtJaduguda, monitoring is done on bothexternal and internal radiation levelsthat the mine and other workersreceive (Figures 3 & 4 ). It can beseen that the radiation doses receivedby individual workers had ranged fromabout 1 to 10 mSv/yr which is far be-low the limit prescribed byICRP (50 mSv/yr) and significantlybelow the annual average dose of20 mSv set by AERB.

The uranium ores that are pro-cessed in the mill to extract uraniumintroduces airborne radio-nuclide dueto dust generation while crushing andgrinding the ore. The radon progenyproblem, as encountered in the minesdoes not exist here as most of theoperations take place in well venti-lated areas. The use of scrubber and

Figure 2

Figure 3

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waterspray avoids the dust and theuse of HEPA filters prevents airbornepollution.

Waste ManagementMining operations at Jaduguda

result in both ore and waste rockbesides ground water that is contami-nated by mine dust and seepage.Waste rock is used within the miningpremises for filling low-lying areas,and excess quantities are stored inan area earmarked for storage. Minewater is reclaimed for use in the millafter clarification. After extraction ofuranium, the mill produces two typesof wastes namely slimes or slurryand liquids depleted in uranium fromion exchange columns. Both areneutralised with lime so as to removethe remaining radio nuclides such asRa, Po, Pb along with heavy metalslike manganese, iron, copper etc. thatcan pollute the environment. Theslurry is then classified and the sand-sized fraction is pumped back to themines for back filling the space leftafter the removal of ore. The remain-ing part of the slurry is pumped intothe tailing pond where the slimesettles and the clear water isdecanted through wells and processedagain at the effluent treatment plant

(ETP) before discharging into thepublic domain. The ETP takes careto keep the levels of undesired ele-ments like U (<300 mg/m3), Ra(< 900Bq/m3),Cl (< 600 ppm) and SO4(<1000 ppm) and Mn ( < 2 ppm) atlevels prescribed by the pollution con-trol board. The tailings pond is a wellengineered containment structurehaving an earthen dam on one sidewhile the other three sides are pro-tected by hills. The seepage waterfrom the pond is also monitored byobservation wells for ascertaining sta-tistical variations in the ground wateras compared to the background con-centrations.

Water from the Jaduguda mine andtailings pond is collected, clarified andreused in the ore processing plant(mill). Any remaining water is re-treated with barium chloride and lime,clarified, and checked for their ura-nium, radium, chloride, sulphate andmanganese levels and after ensuringthat the norms of discharge prescribedby the various statutory bodies likethe Pollution Control Board andAERB are complied, it is released tothe public domain. The company'sISO-9001:2000 and ISO-14001 cer-tification ensures that these protocolsare followed strictly.

The Health Physics Unit (HPU)and the Environmental Survey Labo-ratory of BARC, independently carryout environmental monitoring of thedifferent units comprising the mine,mill, tailings pond, effluent treatmentplant, and the areas around theJaduguda for a radius of some 25 km,since inception. The HPU evaluatesand ensures overall safety of the work-ers and public in accordance with thestandards prescribed by AERB andICRP. The HPU monitors the radio-activity and radiation levels in differ-ent samples such as water, soil, grass,vegetables, food stuff and aquatic or-ganisms like fish, algae etc. Such apractice helps in maintaining a healthyenvironment and a better understand-ing of the impact of uranium miningand extraction on the environment.

The gamma radiation at 1 metrelevel above the tailings surface at dif-ferent places vary from0.8 to 3.3 µGy/hr averaging about 1.4 to 2.0 µGy/hr. Radiation levels decrease to back-ground values of 0.10 to 0.15 µGy/hrat about 20 m from the embankment.The average annual exposure levelsin and around 25 km radius ofJaduguda observed over the yearsrange from 790 µGy/yr to 2490 µGy/yr, the maximum being near the pond(Figure 5 a)

The radon concentrations at thetailings ponds are varying from 23.0to 30.0 Bq / m3 and it reduces localbackground of 10 to 15 Bq / m3 closeto the tailings pond boundary(Figure 5b)

Thus the annual radiation exposurelevels in the public domain aroundthe uranium mine, mill and the tailingpond compares well with thenatural background radiations whichclearly points out that UCIL's opera-tions have been very environment-friendly (Table-1).

Radiation Safety and HealthAspects

Effects of natural and man madeionising radiation on living things

Figure 4

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including humans have been the sub-ject of study ever since uraniumbecame an energy element ofimmense potential. Lack of properknowledge on radiation is the maincause of fear and unfounded appre-hensions, aggravated further by mis-information. Radiations are thus aspart of life as we breathe air, and is apermanent feature. It is natural thatquestions arise as how much radia-tion one can take safely, and whatkind of dose levels become danger-ous.

The ICRP norm is to keep the ra-diation dose levels in working environ-ments as low as reasonably achiev-able (ALARA). It is here that elabo-rate studies on radiation effects havebeen completed and norms set for thedose levels for the persons working

in radiation environment like an X-ray machine, a uranium mine, mill ora nuclear power plant.

The natural background radiationaverages 1-2 mSv per year and mayreach upto 20 mSv per year in someplaces. However, there are areas inthe world where background radia-tions have been unusually high, as atRamsar in Iran where backgroundradiation levels reach up to 260 mSv.Thus lifetime doses from such highnatural background radiations rangeupto several thousand mSv. However,in these parts there is no evidence ofincreased cancer or other health re-lated problem. Even with higher dosesof radiations as encountered by theworkers at the time of nuclear acci-dent, direct correlation between a highdose and cancer is yet to be proved.Nevertheless the practice in nuclearenergy related activities, caution istaken to avoid higher doses and theALARA principle of ICRP applies.

In fact radiation level with less than100 mSv/yr do not produce anydetectable difference in exposed vs.non-exposed patients as per DonaldHunters Occupational Diseases

Figure 5 (a) and (b)

Table-1

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Manual. At Jaduguda surface radia-tion levels average 2.66 mSv/yr whichis far below the limit mentionedabove. Even the mine workers andothers working in the plant area re-ceive less than 10 mSv/yr. Thus theallegations of deformed or mentallyretarded children attributed to higherradiation levels due both natural orman made is not justified at Jaduguda.The cases have been thoroughly in-vestigated by expert doctors as wellas independent agencies. Such casesmay be due to neonatal jaundice,difficult labour during child birth,repeated abortion, malnutrition,encephalitis and meningitis. Care,however, must be taken to protectfrom unwanted risks. Hence the pre-cautions to avoid areas where wastes,such as the tailings ponds and wasterock dumps are located. These havebeen fenced and clearly marked asareas to be avoided. It is like avoidinggarbage dumps and sewer water inday to day life. Health hazards relatedto radiation need to be understoodproperly. Such an understandingbetween the public and authorities en-gaged in development work can leadto the welfare of all. Public aware-ness in such matters is essential toavoid baseless fears and we need topersevere with educating people.

Workshop on Planning, Preparedness & Responseto Radiation Emergencies

The 15th Training Workshop on ‘Planning, Preparedness & Responseto Radiation Emergencies for Medical Officers’ was conducted byBARC’s Local Working Committee (LWC) for Radiation EmergencyMedical Response (REMR) at AERB Auditorium, Mumbai duringSeptember 20-23, 2005. It was attended by 37 doctors from various unitsof DAE medical colleges, and the units ofArmed Forces Medical Services.

Dr. P.R. Bongirwar, Medical Officer Incharge, Trombay & VashiIndustrial Dispensary, welcomed the chief guest, invitees and delegates.

Dr. Nair, Head, Medical Division & Chairman of LWC, REMR, in hisintroductory address said that the knowledge gained by medical officersthrough this workshop should percolate down to other medical and nursingstaff at their work places.

Dr. D.N. Sharma, Head, RSSD, in his remarks enumerated variouscauses of radiation accidents and their consequences. He also spoke about17 Emergency Response Centres (ERCs) being developed all over thecountry with the nodal centre at BARC.

In his inaugural address Shri S.K. Sharma, Chairman, AERB,congratulated the organizers on conducting such workshops. He describedAERB’s mandate and its working through various committees to achieveits goal. He also exemplified concept of defence-in-depth which is usedin construction of nuclear power plant, and emphasized on the need fortraining and emergency preparedness at all times.

Faculty for the training course was drawn from BARC, AERB andDAE. Apart from lectures and discussions on various aspects ofmanagement of radiation emergencies the training course also includedvisits of delegates to the Radiation Medicine Centre, Tata MemorialHospital and BARC.

Dr. H.M. Haldavnekar welcomed the invitees for the Valedictoryfunction held on September 25, 2005. Dr. P.R.Bongirwar, coursecoordinator, summarized the deliberations of the workshop.

Shri K. Muralidhar, Secretary, AEC & Head, MSG, DAE, presidedover the valedictory function and distributed certificates of participation

and CDs containinginformation about medicalpreparedness formanagement of radiationemergencies, to thedelegates.

During the Inauguraland Valedictory functions,votes-of-thanks wereproposed by Dr. S.S.Galinde and Dr. Ravi S.Jammibal respectively.

Invitees and delegates

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International Collaboration: IGCAR experience

Dr. Baldev RajDirector Indira Gandhi Centre for Atomic Research

The mission of IGCAR is to rendercomprehensive Research, Develo-pment and Design support to theIndian Fast Reactor Programme.Over the years, comprehensiveexpertise has been developed in allthe relevant fields, including reactorengineering, safety, materials, andreprocessing. In the process, IGCARhas established itself as a nationallyand internationally reputed researchcentre not only in the primary areasof its activities but also in manyassociated areas. This has resulted ina gradual increase in the number ofinternational interactions andcollaborations. In deed, in severalcases, the proposals for collaborationhave originated from the foreignlaboratories, a testimony to theoverwhelming and clear strength ofIGCAR in the relevant areas.

IGCAR has been an activepart icipant in the InternationalWorking Group on Fast Reactors, andother International Atomic EnergyAgency (IAEA) activities of interestto fast breeder reactor (FBR)programmes. IGCAR hosted during13-17 January 2003, the IAEATechnical Meeting on “PrimaryCoolant Pipe Rupture Event in LiquidMetal Cooled Fast Reactors”, inwhich international experts fromseveral interested member countriesparticipated. IGCAR has also beenactively participating in internationalcooperative research programmes ofIAEA in the areas of reactorengineering, reprocessing, and safety.IGCAR has actively participated,along with France, Japan, Korea andRussia on the investigation of thermalstriping damage of the expansion tankof Phoenix reactor. The thermalhydraulic as well as structuraldamage predictions made by IGCAR

scientists matched very well with in-plant data. In another cooperativeresearch programmes in whichIGCAR contribution was greatlyappreciated was on intercomparisonof computer codes to predict seismicbehaviour of liquid metal fast breederreactor cores. In the cooperativeresearch programmes on coremechanics of FBRs, the predictionsby IGCAR scientists were found tobe in good agreement with theexperimental observations. IGCARis actively participating in severalcurrent cooperative researchprogrammes of IAEA. One examplein the area of reactor physics is onupdated codes and methods to reducecalculated uncertainties in reactivitycoefficients in liquid metal fastbreeder reactors; China, France,Japan, Korea, Russia and USA arecollaborating in this project. Anotherexample in the area of reprocessingis on the separation efficiencies forLa, Ce and Nd in the oxide electro-winning process using MgCl2 basedelectrolyte, in collaboration withChina, Czech Republic, Japan, Koreaand Russia. IAEA has initiated anInternational Project on InnovativeNuclear Reactors and Fuel Cycles(INPRO) with a view to ensuringsustainable nuclear energy towardsfulfilling energy needs for the twenty-first century. India is a member ofthis project. As part of this project,IGCAR is actively participating in ajoint case study on assessment, usingthe INPRO Methodology, for anInnovative Nuclear Energy Systembased on a Closed Nuclear FuelCycle with Fast Reactors (CNFC-FR). The objectives are to assess thelong term viability of technologyoptions and innovations, and identifyareas where research and

development is required. Theparticipating countries are China,France, India, Korea and Russia, andJapan as observer. IGCAR is anactive member in the TechnicalWorking Groups on nuclear fuel cycleoptions and nuclear data evaluation,and Standing Advisory Group onnuclear energy.

As a part of the protocol betweenDAE and the ‘OrganisationEuropéenne pour la RechercheNucléaire (CERN)’, Geneva, so farfive scientists have been deputed fromIGCAR to CERN, each for a periodof one year, for carrying out testing,evaluating, and training the 1200 hugesuper-conducting di-pole magnets forthe Large Hadron Collider (LHC);this is a giant underground acceleratordesigned for accelerating protons to14 TeV and lead nuclei to 1150 TeVfor basic studies in particle physics,the next major project of CERN.

IGCAR has also been activelyparticipating in the collaborativeresearch programmes with thepremier R&D institutes in Germanyunder the aegis of Indo-GermanBilateral Agreement. In the earlyyears, the areas of collaborationincluded sodium chemistry, hightemperature mass spectrometry, hightemperature calorimetry, and solidstate physics including radiationdamage and low temperature physics.Subsequently, the range ofcollaboration has considerablyexpanded to include many other frontline areas of common researchinterest in science and technology,including vibration noise monitoringand analysis for diagnostic purposesin nuclear power plants, and micro-meteorological studies using acousticSOnic Detection And Ranging(SODAR) system for prediction ofdispersal of radionuclides. Theseprojects also fostered closecollaboration between Indian andGerman scientists, including mutualvisits. The experience and expertisethus generated have been valuable notonly to IGCAR, but also to the host

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institutions in Germany. An importantarea of direct interest is that of hightemperature mechanical properties,namely, creep, fatigue and theirinteraction, and also fatigue andcreep-fatigue crack growth behaviorin liquid sodium. Over the yearsseveral projects have focussed onhigh temperature components: creep-fatigue interactions and fracturemechanics properties and theircorrelation for high temperaturematerials, including steels and theirweldments, and also Ni-basesuperalloys; methodology for hightemperature component lifeassessment; and monitoring & repairwelding of high temperaturecomponents. The results from thesestudies have clarified many basicissues, and enhanced capability in lifeprediction of engineering components.An extensive project addressed theissue of environmental degradation ofstainless steels and their welds andthe effect of nitrogen content thereon,and corrosion properties of spun-meltribbon and bulk metallic glasses of Zr-based systems with superior corrosionresistance. Another such extensivestudy has been on the science ofoxidation of high temperaturematerials, a topic of perennial interestto power plants. Indo-German

Collaborative Programme on NonDestructive Evaluation (NDE) is anextensive collaboration that chartedseveral new paths - including

development of ultrasonic andmicromagnetic techniques withinnovative approaches forcharacterization of microstructuresand deformation process, anddevelopment of eddy currentimpedance imaging for quantitativecharacterization of defects and alsoknowledge based systems for NDEapplications. Two IGCAR scientistsobtained their doctoral degrees froma German University based on theinvestigations carried out under thisprogramme. This interaction hasconsiderably enhanced IGCARimpact and recognition as one of thepremier NDE research centre in theinternational NDE community, and isa fine example of the importance andimpact of such collaboration withpremier international institutions.

The early collaboration of IGCARwith the French Atomic EnergyCommission (CEA) dates back to

European Organisation for Nuclear Research, Geneva, Switzerland

Dr. Placid Rodriguez is Indian Nuclear Societypresident

Dr. Placid Rodriguez, former Director, Indira Gandhi Centre forAtomic Research (IGCAR), Kalpakkam, has been elected president ofthe Indian Nuclear Society for a period from 2005 to 2007 He succeedsDr. R. Chidambaram, former Chairman, Atomic Energy Commission.

Dr. Rodriguez has had a career long association with the Departmentof Atomic Energy. After his retirement as Director, IGCAR, he becamethe Chairman of the Recruitment and Assessment Centre, DefenceResearch and Development Organisation.

He is currently a Raja Ramanna Fellow and a Visiting Professor at theIndian Institute of Technology (lIT), Chennai.

Previous chairmen of the Indian Nuclear Society includeDr. P.K.lyengar, former Chairman, Atomic Energy Commission, andC.V. Sundaram, former Director, IGCAR.Other Members of Governing Body

Vice President: Dr. V. Venugopal, Secretary: Shri G.D. Mittal,Joint Secretary: Shri R.K. Singh, Treasurer :Shri R.P. Singh,Joint Treasurer: Dr. Gursharan Singh, Members: Shri S.A. Bhardwaj,Shri R.K. Sinha, Shri H.S. Kushwaha, Shri M.L. Joshi, Shri S.K. Agarwal,Dr. S. Kailas, Shri A.K. Srivastava, Shri Jagdish Sharma andShri S.K. Malhotra.

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1969, when the fast breeder testreactor (FBTR) was conceived to bebuilt by adaptation from the Frenchfast reactor Rapsodie, with severaldesign modifications. IGCARreestablished collaboration with theFrench Atomic Energy Commission(CEA) in 1989 to exchange computercodes in the field of thermal hydraulicsand structural mechanics. Under thiscollaboration, from CEA IGCARreceived CASTEM 2000, PLEXUSand TEDEL codes for structuralmechanics analysis. Recently, DAEhas established collaboration withCEA in wider spectrum of areasrelated to safety of fast reactors.

IGCAR is a partner in some of theinternational collaborative projectsunder the aegis of Department ofScience and Technology. Anambitious DST-DAAD collaborativeproject is aiming at comprehensiveunderstanding and quantita tivecharacterization of thermo-mechanical fatigue in power plantmaterials, and IGCAR andUniversität Siegen, Germany, havebeen identified as the principalpartners. Under the above project sofar 4 Indian scientists visited Germanyand 4 German scientists visited India.University of Science and Technology,Beijing and IGCAR are collaboratingon a project on remnant creep lifeprediction model for power plantcomponents. Another project is onyield criterion for superplastic metalsand alloys, with Moscow StateUniversity, University of Hyderabad,and IGCAR as the collaborators;recently a Russian scientist visitedIGCAR for carrying out experimentalwork for this project.

Mention must be made here ofcollaboration between IGCAR andsome internationally reputedlaboratories, another reflection of theprestige of IGCAR as a researchcentre. In an Indo-FrenchCollaborative Programme onFerrofluids, a device has beendeveloped that can measure forces ofthe order of 10-13 N between colloidal

particles, and it has been effectivelyutilized for synthesizing ferrofluidsand their emulsions with long termstability. The programme led to filingof four patents that include forceapparatus, ferrofluid based magneticflux leakage measurements for NDEand optical filters. The technology isnow being adapted to developdynamic seals for sodium pumps usedin fast reactors. In collaboration withCentre for NDE, Iowa StateUniversity, a three dimensionalboundary element model has beendeveloped and validated for detectionand quantitative evaluation of surfaceand subsurface cracks in structuralcomponents. In collaboration withMichigan State University, EastLansing, modelling of response ofSQUID sensors developed in IGCARfor detection of defects through fluxleakage measurements has beentaken up for optimization of the sensordesign.

The contribution to expertise poolof IGCAR from personal initiatives

deserves a mention here. A few ofour scientist have been awarded theprestigious Alexander von HumboldtFellowship, which gave them theopportunity to work in premierlaboratories in Germany. Many of ourscientists have spent between one totwo years as Post-Doctoral fellows,or shorter periods, in many leadinglaboratories in Japan, USA, Europe,and Australia. The areas of researchfor such visits have invariably beenin the frontiers of current or near-future interest to IGCAR. Similarly,several scientists from foreignlaboratories have visited IGCAR forperiods ranging up to 1 year, to workon projects of common interest.These interactions promote inter-laboratory co-operation and cross-fertilization of ideas, and benefit theprogrammes of both the IGCAR andthe concerned foreign institution.

Dr. A.K. Kohli did his graduation in Mechani-cal Engineering from Delhi University in 1974.He joined Reactor Engineering Division ofBhabha Atomic Research Centre (BARC) aftercompleting one year course with 18th batch ofBARC’s Training School. He did his M.Tech. inDesign of Mechanical Equipment from IIT, Delhiin 1982 and Ph.D. on Radiation Resistant SolidLubricants from IIT, Delhi in 1998. He has

served as Head PFBR F/H & Shipping Cask Group in RefuelingTechnology Division and as Engineer-in-Charge Consultancy Services& Mechanical Technologies of Technology Transfer and CollaborationDivision of BARC. He was involved in design and development ofdifferent components & sub-systems of PHWR fuel handling systemand later PFBR fuel handling system.

He joined Board of Radiation and Isotope Technology in the year2001 as Senior General Manager – Engg. Design, QA & CustomerSupport. He has served in various committees in different capacities.He has taken various new initiatives in furthering the activities of BRIT.

He has now taken over as Chief Executive, Board of Radiation andIsotope Technology with effect from January-2006. *****

BRIT’s New Chief Executive

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Science & Technology Exhibition “Pride of India” of the 93rdIndian Science Congress at Hyderabad

Science & Technology Exhibition “Pride of India” of the 93rdIndian Science Congress at Hyderabad

In the Science & Technology Exhibition“Pride of India” of the 93rd Indian Science

Congress held during January 3-7, 2006 atAcharya N G Ranga Agricultural University,

Hyderabad, the Most Interactive PavilionAward was bagged by the DAE pavilion.

Picture shows Head, Public AwarenessDivision, DAE receiving the Award.

EDITORIAL GROUP: Dr. R. B. Grover, Director, Strategic Plng. Group, DAE, Director, HBNI and Group Director, Knowledge Management, BARC,K. Muralidhar, Secretary, AEC, Dr. K S Parthasarathy, Raja Ramanna Fellow, SPG, DAE, Dr. Vijai Kumar, Head SIRD, BARC, P.V. Dubey, Company Secretary, UCIL,G.Srihari Rao, Executive Director (IT&TG) ECIL, N. Panchapakesan, Manager (L&IS), NFC, S.K. Malhotra, Head, Public Awareness Dn, DAE, ArunSrivastava, SPG, DAE

EDITOR : R K Bhatnagar, Head, Publication Dn, DAE (e-mail: rkb@dae.gov.in, Fax: 022 - 2204 8476)

Edited and published by R K Bhatnagar, Hd. Publication Dn, Dept. of Atomic Energy, Govt. of India, Mumbai-1, and printed by him at M/s Indigo Printing Press, Byculla, Mumbai-400 027.

R.No. 9002/62