Kamala Balakrishnan - Bhabha Atomic Research Centre

32
Availableat URL:http:/Iwww.barc.ernet.in No. 183,' April 1999 Kamala Balakrishnan ALTERNATE FUEL CYCLES IN THE INDIAN PHWR I. INTRODUCTION The Indian Pressurised Heavy Water Reactor (PHWR) has so far been working on the natural uranium once through cycle. But this reactor, with its advantages of on,load refuelling and short bundle length, is a versatile system which admits of many other fuel cycles. Every fuel cycle has its own distinct advantages and its own constraints. The selection of a fuel cycle for a reactor will depend upon the time and place, the economics and politics. Some of the performance criteria based on which fuel cycles are designed are (a) fuel utilisation, (b) shrinking of spent fuel inventory, (c) reduction of long'lived actinide wastes, (d) operational ease for high burnup cycles, (e) retrofittability into existing systems, (I) fuel cycle flexibility, and (g) dispositioning of weapons plutonium. In the international arena, fuel cycles designed for non'proliferation and safeguards considerations, and inert matrix cycles for plutonium destrnction are also receiving attention. These cycles will however. not be addressed in this paper. From the Indian perspective, the most important characteristic of any fuel cycle is the energy obtained per ton of uranium mined. From this point 01view, a number of fuel cycles have been examined. These include (i) slightly enriched uranium (SEU), (ii) natural uranium with self,generated plutonium, (iii) recovered uranium with self,generated plutonium, (iv) natural uranium with dismantled weapons plutonium, (v) recovered uranium with dismantled weapons plutonium, (vi) thorium, U233 self,sustaining cycle witli U235 makeup, (vii) thorium,U233 self,sustaining cycle with reactor grade plutonium makeup,(viii) tliorium, U233 self,sustaining cycle with weapon plutonium makeup, (ix) thorium with U235 in high hurnup cycle, (x) thorium with reactor plutonium in high bumup cycle, CONTENTS I. Altemativefuel cycles in the Indian PHWR.. ..,.. I ~~~~~~~t;;;H~~i;hS;;:;i~~S~h;;;';. I~ I Facility for integral system behaviour experiments (F/SBE) """""""'" 19 Digital imaging of neutrons and its Applications':................... 37'htraining course on radio, immunoassay and its clinical applications """""""""""", Technology transfer from BARC.. BARC scientists honoured .. 2. 3. 4. 5. 6. 231 7. 8. 30 31 321

Transcript of Kamala Balakrishnan - Bhabha Atomic Research Centre

Page 1: Kamala Balakrishnan - Bhabha Atomic Research Centre

Availableat URL:http:/Iwww.barc.ernet.in No. 183,' April 1999

Kamala Balakrishnan

ALTERNATE FUEL CYCLES IN THE INDIAN PHWR

I. INTRODUCTION

The Indian Pressurised Heavy Water Reactor(PHWR) has so far been working on the naturaluranium once through cycle. But this reactor,with its advantages of on,load refuelling andshort bundle length, is a versatile system whichadmits of many other fuel cycles. Every fuelcycle has its own distinct advantages and itsown constraints. The selection of a fuel cyclefor a reactor will depend upon the time andplace, the economics and politics. Some ofthe performance criteria based on which fuelcycles are designed are (a) fuel utilisation,(b) shrinking of spent fuel inventory,(c) reduction of long'lived actinide wastes,(d) operational ease for high burnup cycles,(e) retrofittability into existing systems,(I) fuel cycle flexibility, and (g) dispositioningof weapons plutonium. In the internationalarena, fuel cycles designed for non'proliferationand safeguards considerations, and inert matrixcycles for plutonium destrnction are alsoreceiving attention. These cycles will however.not be addressed in this paper.

From the Indian perspective, the mostimportant characteristic of any fuel cycle is theenergy obtained per ton of uranium mined.From this point 01view, a number of fuel cycleshave been examined. These include (i) slightly

enriched uranium (SEU), (ii) natural uraniumwith self,generated plutonium, (iii) recovereduranium with self,generated plutonium,(iv) natural uranium with dismantled weaponsplutonium, (v) recovered uranium withdismantled weapons plutonium, (vi) thorium,U233 self,sustaining cycle witli U235 makeup,(vii) thorium,U233 self,sustaining cycle withreactor grade plutonium makeup,(viii) tliorium,U233 self,sustaining cycle with weaponplutonium makeup, (ix) thorium with U235in high hurnup cycle, (x) thorium withreactor plutonium in high bumup cycle,

CONTENTS

I. Altemativefuel cycles in the IndianPHWR.. ..,.. I

~~~~~~~t;;;H~~i;hS;;:;i~~S~h;;;';. I~IFacilityfor integral system behaviour

experiments (F/SBE) """""""'" 19Digital imaging of neutrons and its

Applications':...................37'htraining course on radio,

immunoassay and its clinicalapplications """""""""""",

Technology transfer from BARC..BARC scientists honoured ..

2.3.4.

5.

6. 231

7.8.

3031

321

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Ever since the Three Mile Island accident

in 1979, considerable work has been done in

many countries of the world to develop areactor system with inherent safety features.This effort has resulted in a number ofdesigns of both Pressurised Water Reactorsand Boiling WalerReactors. In India a

unique reactor system designated AdvancedHeavy Water Reactor (AHWR) has evolved.From the safety point of view the mostnoteworthy feature of AHWR design is itsability to remove all the heat from the fuelchannels by natural circulation withoutcoolant circulating pumps. In fact, the AHWR

design does not have coolant pumps.from the reduction in the cost and comthat is achieved due to the absence of coolant

pumps, the ability to remove all the heatin the coolant channels natural

full power to downarkahle achievement. TheWater Reactor has the

the exceptionally goodwater as a neutrone the need to handle

water in the coolant

heavy water with

pressure cvolantits

Editorialit was felt desirable to develop a thermalreactor system which can exploit the energypotential from the vast thorium reservesavailable in India. The neutronic design ofthe AHWR core has been optimised in such away that about 75% of the energy produced inthe reactor comes from thorium.

AHWR, by all means, is an exceedinglybeautiful concept both from the ofengineered safety features and theneutronic design that allows the generation ofabout three-fourths of the energy fromthorium. Once the prototype AHWR is builtand successfully operated, I am sure thatit will be recognised as a major achievementin the symbiosis of ingenousconcepts, and ideas in reactobe internationally acclaimed.

It

The Facility for Integral SystemBehaviour (FISBE) is a versatile

that has been set up toall relevant conditions that will

exist in the coolant system - the Primary HeatTransport (PHT) system - in the PressurisedHeavy Water Reactor (PHWR), both of the220 MWe and of the 500 MWe designs.FISBE will be used to study a number ofsafety related features of the PHWR. Anotherexperimental facility is being planned todemonstrate the feasibility of removing theheat from the AHWR without any coolantpump by means of thermo syphon experimentsboth in single phase and with partial boiling.It must be noted that while PHWR hashorizontal coolant channels, the AHWR hasvertical channels.

This month's Newsletter covers, amongothers, the different fuel cycles that arepossible with the PHWRs. It also features anarticle on FISBE, which brings us closer toexperimental demonstration of the safetyfeatures of the PHWR design.

~z~

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(xi) thorium with weapon plutonium in highbumup cycle. Then there are the variouscombinations that can be clubbed together asdifferent versions of the once through thorium(OTT) cycle, viz., (xii) unenriched thorium andSEU in segregated channels, (xiii) unenrichedthnrium and natural uranium with reactorplutonium in separate channels, (xiv)unenriched thorium and natural uranium withweapon plntonium in separate channels, (xv)unenriched thorium and recovered uraniumwith reactor plutonium in separate channels,(xvi) unenriched thorium and recovereduranium with weapon plutonium in separatechannels. Finally, we have also made a study ofa BWR-PHWR tandem cycle.

In this paper, we describe all these cyclesand the results of the studies. As mentioned, themajor emphasis will be on the maximisation ofenergy from any given quantity of fissilematerial. But wherever a cycle offers otherbenefits, these have been pointed out.

The BWR-PHWR tandem cycle has beendescribed in some detail. This has been done

with the intention of showing the kind ofstudies that are needed before a cycle canactually be introduced into a reactor. Some of

the problems that arise are pointed out andpossible solutions discussed.

2. DESCRIPTION OF THE REACTOR

The Indian PHWR is a tube type reactornsing heavy water as both coolant and

moderator. The coolant is physically separatedfrom the moderator by being contained inside

the pressure tube where it is maintained at hightemperature (- 270 °C) and pressure (-92 bar).

The moderator heavy water is at relatively lowtemperature (- 55 "C) and is unpressurised.

The reactor core consists of 306 pressuretubes arranged along a square lattice of 22.86em pitch. The fuel pins and the coolant arecontained within these pressure tubes. The

direction nf coolant flow in adjacent channels isin opposite directions. The fuel is in the form ofa string of 12 bundles. Each bundle is a 19-rodcluster of49.5 em length. Of the 12 bundles, 10arc in the active portion of the core, theremaining 2, onc on each cod, are outside thecore

Refuelling is done on-power by simplypushing out 8 bundles from a channel on oneend, while 8 fresh bundles are inserted from theother end. The direction of the bundlemovement is the same as that of the coolantflow, so that alternate channels are fuelled inopposite directions. This helps in maintainingoverall axial symmetry.

Table I gives a general description of someof the important physical parameters of the coreof the Indian PHWR.

Table 1

DESCRIPTION OF THE PHWRREACTOR CORE

3. NATURAL URANIUM BASEDCYCLES

Using natural uranium fuel as the base andincreasing the fissile content by addition ofexternal fissile material, a number of cyclesarc possible. The added fissile material couldbe self-generated plutonium or weapon

Numbe, of fuel channels 306

Lattice pitch, cm 22.86

Calandria inner radius, cm 299.8

Calandria leneth, em 500.0

Number of bundles per channel inside the 10active oortion of the core

Extrapolated core radius, em 303.3

ExtraDolated core length, cm 508.5

Number of absorber rods (fDr xenon 4Dvenide)

Number of regulating rods (for reactor 2regulation)Number of shim rods (to provide backup 2fa, regulation)

Number of mechanical shutoff rods (SDS- 14I)Number of liouid Doison tubes (SDS-2) 12

Total thermal power to coolant, MWth 756Maximum cbannel power, MW 3.2Maximum bundle power, kW 440Maximum coolant outlet temperature, 297"C

Reactivitv worth of SDS-l, mk 31.9Reactivity worth of SDS-2, mk 32.1

Coolant inlet temoerature, "C 249

Average fuel temDerature, "C 625Average coolant temperature, "C 271Specific power, kW/kg 19.2

Page 4: Kamala Balakrishnan - Bhabha Atomic Research Centre

plutonium (in which case the fuel is MOX), orU235 itself, leading to the most popularalternate cycle, viz" slightly enriched uranium(SEU). We consider SED here in once throughmode, and MOX is restricted to one recycle ofplutonium.

Even though the correct way to evaluateresource utilisation is to express the results interms of energy obtained per ton of uraniummined, the following difficulty arises. In thecase of SED, this conversion depends upon theamount of U235 lost in the enrichment planttails. This value is sometimes quoted as 0.2%,sometimes as 0.1%, or at times even lower. Inthe case of weapon plutonium, one does notknow how to make any assumptions on how itwas produced or how much natural uraniumwas used to create it. It is only in the case ofself-generated plutonium that any definitivenumbers can be assumed. We obviate thisdifficulty by expressing our results in terms ofenergy per kg of U235 or plutonium. To makea meaningful comparison between SED andMOX, we assume that the quantity ofplutonium in the MOX is the sum of a certain"real" plutonium and "virtual" plutonium. This"virtual" plutonium is computed as theequivalent of the U235 content of naturaluranium. It is defined as that amount ofplutonium which would give a bumup equal tothat of oatural uranium.

Figure I shows this as a function ofdischarge bumup. Discharge bumup has beenchosen as the independent variable since it isone of the most important performance criteriaof any fuel cycle. The highest fuel utilisation isjust above 1,700 MWD/kg fissile and is moreor less the same for U235, reactor plutonium,or weapon plutonium. This comes in theneighbourhood of 27,000 MWDrr dischargebumup for SED, and 20,000 MWDrr forplutonium. For high bumups, SED gives muchbetter utilisation than plutonium. This is onlyto be expected since higher initial enrichmentwill be needed for higher bumups. With thehigher cross-section of plutonium, the MOXends up burning more of the initial fissilematerial, while the SED manages to convertmore U238 to plutonium and bum it. Thereisn't much difference hetween the twoplutoniums, but surprisingly, the reactor

plutonium seems to have an edge over theweapon plutonium.

~.\ ""

L~~;-= :::~;:,::' """-

Fgure I .. Fuel cycles in PHWR with naturaluranium base.

Again, may be it need not be such asurprise since the reactor plutonium containsPu24I and also Pu240 which gets convertedinto Pu241, and Pu241 is a better fissilematerial than Pu239. All these numbers may becompared to the value obtained for thereference cycle, i.e., the natural uranium oncethrough cycle, which has a discharge bumup of6,270 MWDrr and can he said to have a fissilematerial utilisation of 896 MWD/kg fissile.This point is indicated in the figure by anasterisk. One can see that all the cases

presented here have fuel utilisationcharacteristics superior to tbe natural uraniumonce through cycle.

4. RECOVERED URANIUM BASEDCYCLES

Similar studies can be made for fuel withrecovered uranium as base. The discharged fuelfrom the PHWR natural uranium once throughcycle contains 0.255% U235. Since this isconsidered as discarded material in thereference cycle, only the added fissile contentis used in the calculation of energy fromfissile material. The SED cycle in whichrecovered uranium is base, thus shows a higherfissile utilisation than the one with naturaluranium base. Obviously this is because theresidual U235 in the discharged fuel is beingburnt. Once again, all three curves lie totallyabove the asterisk representing our referencecase. This can be seen from Fig. 2.

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Figure 2: Fuel cycles in PHWR with recovereduranium base.

5. THORIUM CYCLES

The PHWR is one of the best reactors to usethorium, second probably only to tbe MSBRPossible thorium cycles fall into threecategories, which can be called the self-sustaining equilibrium thorium cycles (SSET).the high bumup open cycles, and the oncethrougb tborium (OTT) cycles.

5.1. THE SELF-SUSTAININGEQUILIBRIUM THORIUM CYCLE(SSET)

The fuel in this cycle is thorium-U233. Thedischarged fuel should contain enough U233 toprovide the fissile content for the next fuelcharge. Thus this cycle, once initiated, can goon indefinitely without any external fissileinput In the limit, its energy potential istheoretically infinite until thorium runs out

There is the question of how the SSET is tobe initiated. There are two ways of doing this.The first is to enrich the thorium with U235,extract U233 from the spent fuel and use it forthe first charge of the SSET. About 250 tonsof natural uranium will be required to place onePHWR on the SSET. The alternative route isthe plutonium rout", in which the reactor is firstfuelled with natural uranium. The plutoniumextracted from the discharged fuel is mixedwith thorium and fed back into the reactor.This fuel when discharged, will contain U233,which can be retrieved and used to initiate theSSET. This route will require about 500 tons ofnatural uranium for one PHWR.

The discharge burnup possible with theSSET is rather low being about 11,000MWDrr. For a cycle that depends on repro-cessing and refabrication of highly active U233bearing fuel. this is too Iowa value to beeconomical. The burnup can be improved byadding a certain amount of makeup fissile in thenew fuel along with the extracted U233. Wehave carried out studies with U235 makeup,reactor grade plutonium makeup, and weaponplutonium makeup. Figure 3 gives the resultsobtained with all the three. The weaponplutonium gives results that are marginallysuperior to reactor plutonium, while U235 issuperior to both plutoniums.

i"

~'

:.1

~"

.

"'-~

j"! ",

] ". . '-.-.-rb' ", .., ;;-,-.:-<8~~._,_,.__,_-""

" ,o-"""',:;"m";:,~~';6o-.-.-Figure 3 : Utilisation of makeup fissile materialin SSET

Some safety related parameters of interestare as follows. The positive void coefficient ofreactivity (on complete voiding) is 5.98 mk ascompared with the value of 10.84 mk for thenatural uranium core. The effective delayedneutron fraction is 2.75 mk (6.91 mk for thenatural uranium core). In the event of a LOCAfollowed by over power trip, the peak powerreached is 2.005 times full power (ef. 2.15),peak fuel temperature is 866"C (cf. 864 "C).

As for operational parameters, the adjustorrod worth reduces from 8.25 mk for the naturaluranium core to 6.28 mk for the SSET core.

5.2. THE HIGH BURNUP OPEN CYCLE

Here we do not close the cycle, and theIntent is to get as high a bumup as possible. Ifdirect disposal of spent fuel is contemplated,this cycle assumes importance in shrinking5

Page 6: Kamala Balakrishnan - Bhabha Atomic Research Centre

the spent fuel inventory. This cycle is alsosuitable for destroying the accumulated civiland military plutonium. The economics of thiscycle is very favourable as compared to that ofthe SSET. Fuel utilisation is significantly lower.One possible way to improve resourceutilisation is to store the spent fuel so that if atany time in tbe near or distant future there is achange in the position of cheap uranium. thisfuel can be reprocessed to recover U233.

Figure 4 : Energy from thorium fuel withoutrecycling.

Whether one prefers U235 enrichment orplutonium enrichment will, among other things,depend on the objective. If shrinking the spentfuel inventory is the objective. U235 enrich-ment is more advantageous in that it givesbetter fissile utilisation. This can be seen fromFigure 4 where the energy obtained from I kgof fissile material is compared for U235 andplutonium. On the other hand, if plutoniumdispositioning is sought, this cycle is a veryeffective one. Figure 5 shows that this cyclecan destroy up to 95% of the fissile plutonium.

5.3. THE ONCE THROUGH THORIUM(OIT) CYCLE

This scheme is based on reasons not reallyrelated to either fuel utilisation or fuelling costs,but rather on operational acceptablity. Twomain argumentscan be advanced for this cycle.

I. Because of a general slowing down ofthe nuclear power programme the world over.it is difficult today to persuade utilities to loadthorium. In the OTT scheme, we have a way of

introducing thorium that causes the leastdisruption in the normal fuelling of the reactor.

Figure 5 : Plutonium destruction in thorium-plutonium fuel

2. One of the advantages of the thoriumcycle over the uranium cycle has been the levelof long-lived actinides which pose a wastedisposal problem. This is orders of magnitudelower in the thorium cycle. But to takeadvantage of this. there is a need to keepthorium from being "contaminated" by theuranium cycle, i.e.. direct mixing of the thoriumwith any part of the uranium cycle, e.g.. U235or plutonium. should be avoided.

The principle of this cycle therefore is touse plain unenriched thorium along with SEU insegregated channels of the PHWR. Being indifferent channels. their bumup can be variedindependently. The presence of thorium acts asa load on the SEU. which will therefore have tobe discharged at a lower bumup. The totalenergy extracted will be the sum of the energy

", '-,.

Figure 6: Once through thorium (OIT) CYclein PHWR

Page 7: Kamala Balakrishnan - Bhabha Atomic Research Centre

obtained from the thorium and the SED. As theresidence time of thorium in the core increases,

the energy obtained from unit mass of mineduranium will first decrease, then increase, and

finally become higher than it would have beenhad no thorium been present in the core. Figure

6 shows this graphically. Similar results are alsoseen when thorium is combined with MOX,

i.e., natural uranium with eithe'r reactor or

weapon plutonium.

6, THE LWR-HWR TANDEM CYCLE

Some work is being done in India on the

possibility of using thc discharged fuel fromLWR as feed for the PHWR. At present, India

has only two units of light water reactors of160 MW(e) capacity each. They are boilingwater reactors. The proposal is to subject the

discharged fuel from the BWRs to aknown as coproccssing, in which the

products arc removed, hut all the actinidesare precipitated together. There is thus no

ion of plutonium and uranium, a factenhances the of this process from

the point of view non-proliferation. This

mixture of heavy metals is then fahricatcd intothe 19 rod handles of the Indian PHWR. and

introduced into the heavy water reactor. A hriefdescription of the BWR lattice is given in

Table 2. The isotopic composition of the fuelwhich is discharged at a humup of 21,000MWDrr is as given in Table 3. Fuel of thiscomposition, fabricated into 19 rod clusters andloaded intn the PHWR can give a discharge

bumup of 37,200 MWDrr.

1I

fl

I ThIS means a support ratio of about 1.7,

which means that I GW(c) of BWR can supportthe fuelling requlremcnts of 1.7 GW(e) installed

capacity of PHWR. This ignores losses durIng7

Table 3

fabrication, coprocessing, etc., but if all thosefactors were also taken into account, one can

still expect a support ratio of 1.5.

The void coefficient of this lattice is about6.7 mk (positive). This is lower than the value(+10.8 mk) for natural uranium. However, thedelayed neutron fraction is 4.12 mk as opposedto 6.5 mk in the case of natural uranium. Anapproximate LOCA was carried out toevaluate the effect of It was assumed thatthe PHT voiding at least in so far as thereactivity effect concerned, is complete in1 sec., so that the total void coefficient can beconsidered to have been added to the reactivityin ] sec. Blowdown is supposed to last for 10secs., during which period there is improvedheat transfer. Thereafter, the ECCS will comein. However, in this ca!culation, this has beenneglected and so beyond ]0 secs. the heattransfer has been assumed to be negligihle.

The shut down in this LOCA calculation is

initiated by the over-power trip. Shut down isby moderator dumping. Among Indian PHWRs,there are four units built in the early days,which have shut down by moderator dumping.Later units have two independent fast actingshut down systems. The tandem cycle whichwe are examining is supposed to be introducedinto one of the earlier reactors. Hence the use ofmoderator dumping for reactor shut down in thestudies presented here.

The peak power in the tandem fuelledPHWR under LOCA reaches 1.93 timesnominal power and peak fuel temperature of862°c. This may be compared with peak powerof 1.6 times nominal power and peak fueltemperature of 856"C in the case of the naturaluranium equilibrium core and peak power of2.] 5 times nominal power and peak fuel

Page 8: Kamala Balakrishnan - Bhabha Atomic Research Centre

temperature of 864"C for the fresh naruraluranium core.

The PHWR has a set of cight rods calledadjuster rods (AR) to providc xenon override.A set of four rods called regulating rods (RR)are used for reactor regulation. In. the naturaluranium core, the ARs have a reactivity worth01.8.2 mk, and the RRs have a worth of 4.8 mk.In the tandem fuelled core, the AR worth is5.2 mk, aod the RR worth is 3.2 mk. Thisreduced AR worth is however, compensated bya change in xenon worth. Whereas the 8.2 mk inthe natural uranium core could give a xcnonover-ride time of 30 minutes, the 5.2 mk in thetandem fuelled core gives an over-ride time ofabout one hour. So the AR worth reducing to5.2 mk is of no concern.

The reduction in RR worth may have someimplications for operability. but with somebackup worth provided by boron in themoderator, this can be managed.

The reactivity of the initial core will be veryhigh, of the order of 200 mk. It is possiblc tosuppress this either by loading a number ofthorium bundles, or by using boron in themoderator. The boron level will have to be veryhigh. But the major disadvantage of boron willbe that power peaking in the initial core willnecessitate the derating of the reactor. As corebumup proceeds, the flux will tend to flatten.By about 90 effective full power days, bothbundle power and coolant outlet temperaturewill have reached acceptable values. Refuellinghowever, will be required only after about 900EFPD and continued bumup will worsen thepower distribution, because the low flowchannels towards the periphery of the core willnow produce marc power than can be removedby the flow which has been designed to cater tothe power distriburion of thc natural uraniumequilibrium core.

Studics have shown that while the m"ximumbundle power in tbe core gocs on decreasinguntil tbe core reactivity falls to zero at about925 EFPD. the maximum coolant outlettcmperature reaches a lowest value of 295.0"Cat 116 EFPD, and thereafter starts increasingagalll. At 925 EPPD, it has touched 311.9'c.The three conslramts on power are the bundlepower, channel power, and coolant outlet

temperature. Figure 7 shows, as a lunction ofEFPD, three quantities, which we have chosento call bundle ratio (B), channel ratio (C), andtemperature ratio (T). The bundle ratio isdefined as the ratio of the highest bundle powerin the core to the maximum permitted bundlepower. C is a similar quantity for channelpower, and T for coolant outlet temperature.

I.~

\, "-, '": ", -,;:...,

---- "

, ,,"Ij'"!! '"

"""""""""-'

---"".. "'-"""

! U"""""""""""""""m"""..w~"mU ."'. "", ,~., .'" ""~-~--Figure 7 ; Voriation of power constraints wthhurl/up

For full power to be possible, all three ofthem should be less than unity. When any ofthem exceeds unity, it also is the factor bywhich the reactor power needs to be derated inorder to stay within design constraints. We seefrom Figure 7 that whereas Band C start fromvalues exceeding unity at zero EFPD, anddecrease consistently right up to the fin;trefuelling at 925 EFPD, T goes through aminimum and then rises again, reaching quitehigh values towards the end. The reason for thisis that weare retrofitting the tandem fuel into acore originally designed for natural uranium, inwhich the coolant flows have been already fixedthrough appropriate orificing to suit the naturaluranium fueL Over the extremely long pre-fuelling life of the tandem core, bumnpinduced power flattening reaches suchproportions that the low flow channels at thecore periphery end up producing much morepower than they were designed to cater to.

Figure 8 shows the variation of maximumcoolant outlet temperature with effective fullpower days of operation in the core withoutany thorium bundles. AI,;oshown in Figure 8 isa similar curve for a core in which thoriumbundles have been deployed to give full power

8

Page 9: Kamala Balakrishnan - Bhabha Atomic Research Centre

i '".

j'"1'00!j'"

~.::..: =

'00

Figure 8: Variation of maximum channel outlettemperature with burnup

in the beginning. (This loadingis shown inFigure 9). While in the cure without thoriumbundles, the coolant outlet temperature crossesits pennitted limit again by about 180EFPD. inthe core of Figure 9 this never happens. Thecore can give full power right up to the timethat fuelling starts. beyond which of course, thepower distribution is controlled hy properfuelling.

Figure 9 : Thorium bundle distribution in thetandem loaded core.

7, THE ADVANCED HEAVY WATERREACTOR (AHWR)

While the thorium cycle in the PHWR offers

many attractive possiblilies, the fact remainsthat all of them are retrofits into the PHWR

which was designed with the uranium cycle inmind. The AHWR was designed to takeadvantage of the specific nuclearcharacteristics of thorium.

If we look at the SSET as a starting pointfor a thorium cycle, we should address its mainweakness, viz., its low bumup. The humup canbe increased by adding plutonium makeup. Thecapture-to-fission ratio of Pu239 is rather highin the soft spectrum of the PHWR. A harderspectrum and tighter lattice are therfore

Table 4

DESCRIPTION OF AHWR AT THE PRESENTSTAGE OF EVOLUTION

Reactor power, MWthReactor power, MWeFuel description:

Number of pinsNumberofPu bearing pinsNumber of thorium-U233 pinsNumber of water tubes for

ECCS injectionPlutonium conrent in MaX, %U233 content in thorium

Coolant water density,

(varies in the range)

Total numbee of channels

Number of seeded clusters

Number of clusters with all

"thorium-U233" pins

Number of fuelling zonesNumber of reconstitutions

Thocium pins discharge bumupMworr

MaX pins discharge bumup,MWOrr

Lattice pitch, emActive fuel length, emModemtoc and ,'eflectocScatterer balls in the moderatorCalandria radius, emNo. of adjustor cadsWorth ofadjustorcods, mkNo. of regulating rodsWorth of regulating cads, mkNo. of SDS-I cadsWorth ofSOS-I, mk

Performance data in the equilibriumcore Radial fonn factor

Hot spot factor in the seeded clusterHot spot factor in the thorium-U233

cluster

Maximum channel power, MWthMaximum-to-minimum channel

power factorFraction of power fcom thocium, %

750220

5220328

2.7self

sustaining0.50-0.55

42834484

2I20,000approx.20,000appcox.29.4350020

pyrocarbon43045.7744.533254.5

1.411.42

1.362.45

1.8875.4

Page 10: Kamala Balakrishnan - Bhabha Atomic Research Centre

advisable. In a uranium sysrem, the harderspectrum will be to the detriment of the U235,but the eta of U233 is almost flat and so it doesnot matter.

Thermal absorption of thorium is aboutthree times as large as that of U238. Soparasitic absorption is less of a problem inthorium systems and one could try light watercoolant. With light water coolant, it is possibleto have boiling coolant and direct cycle. Sincethe spectrum is bard, things could be somanaged that the coolant void coefficient isnegative.

With boiling coolant, the reactor has to bevertical. 111this case, it can be designed to have

100% heat removal by natural circulation andalso to have passive safety.... -

q.' -~~~~~~ ~,=

These are broadly the characteristics of theAHWR. A description of the core at its presentstage of evolution is given in Table 4.

8. CONCLUDING REMARKS

The natural uranium once through cycle wasthe first natural cycle for the PHWR, but maybe it is now time to look at other cycles moreseriously. Both plutonium recycling andthorium cycles yield much better fuelutilisation, high bumup cycles help il1shrinking spent fuel inventory for thosecountries for whom direct disposal is aconstraint. These cycles are also very efficientin constraining plutonium where that is ofimportance. The choice of a cycle will dependupon the compulsions of any country orcompany or utility, hut an array of options isavailable to choose from.

HISTORY

CONTRIBUTORY HEALTH SERVICE SCHEMEMedical Division

-..:I"-.....

The history of our medical services datesback to 1955 when the Health Division ofthe then Atomic Energy Establishment,Trombay (AEET) was founded. To start withDr P.D. Dame was looking after clinical work,with Dr (Mrs.) c.y. Lavande doing pathologywork.

By 1958, the Division started expandingwith the recruitment of Dr K. Sundaram,Dr RD. Ganatra. and Dr V.R. Shah. Thosedays initial medical examination of newrecruits, periodical medicalexaminations of thestaff members and outdoor treatment given tothe employees constitutedmuch of the work.

By 1959more clinical work was started andthree <lispensaries were set-up: one at theTraining School Hostel at Bandra. the maindispensary at the Old Yacht Club, and onedispensary at South Site, Trombay. Therewere no hospital facilities of our own and therewas no facility for treatment of familymembers of the employees.

It was during 1960-61Dr Homi Bhabha, theperfectionist and visionary, implemented a

separate scheme of our own - the presentCHSS. His idea was tltat a well run medicalscheme will make the employees feel secureand with their families heing looked after, theycan concentrate better on their work.

Several administrative hurdles had to beovercome and in 1962 sanction was obtainedfor a separate scheme, different from thegeneral Central Government scheme.. By 1963 indoor facility at J.J. Hospital in

Byculla, Mumbai and a dispensary in thehospital premises were started, and thefamily members of tlte staff startedreceiving treatment at OYC dispensary andU. Hospital dispensary. The expansion ofCHSS continued with opening of new<lispensariesin various locations -

. Chernbur (1964). Anand Bhavan (1965). Bandraand Ghatkopar (1966). Matunga (1967). Deonar(West)(1969). Deonar(East)(1975). Vashi (BRIT)(1985). Vashi(1987)10

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. Andheri (1992. Mandala (1999)

As the numher of heneficiaries increased, sodid the staff strength of Medical Division. Theindoor facilities at the J.J. Hospita] were nownot enough and in ]976 the BARC Hospitalwas shifted to the present premises atAnushaktinagar. The beneficiaries are offeredvarious facilities and medical treatment withthe help of many advanced investigations inour hospital. It is a fulfilment of Dr Bhabha'sdream. At present Medical Division andRadiation Medicine Centre cater to the medicalneeds of about 72,200 beneficiaries with thehelp of ]2 dispensaries and a 250 bed hospital.

". First Hepatic transplant performed inMumbai was on our beneficiaries, costingRs 1 million.

". Three bone marrow transplants have beenperfonned on our patients, each costingRs 700,000.

". 330 Angiographies, 80 angioplasties and 70

bypass surgeries were done in ] 998 alone.

". Five kidney transplant patients are on

immuno-suppression therapy - costingRs 3000/- month/patient, apart from thetransplant cost.

CHSS DISPENSARIES

At present, the ]2 CHSS dispensaries,spread all over Mumbai, are rendering medicalservices to 72,200 beneficiaries. Thesedispensaries are run by 38 doctors and areimportant and strong pillars of our healthscheme. These dispensaries are engaged in thefollowing activities:

I. Prompt and efficient initial care of all

patrents;

2. Regular follow ups of Drabetcs,Hypertension, Coronary Heart Disease,Pulmonmy Tuberculosis and Asthmapatients;

Antenatal care, Well Bahy ca" d,",es,

4. Immunozation,

5. Disp]aying educative posters and lectures -to provide infonnation and positivemessage regarding health care.

These dispensaries are going to be updatedwith equipment like g]ucometer, nebuliser,ECG machine and computers. The dailyattendance of CHSS beneficiaries is about1820, with more than 45 patients/day/doctor.

TROMBAY DISPENSARY

Apart from the 12 peripheral CHSSdispensaries, there are two special medicalunits for the health care of employees inrelation to their work.

Trombay Dispensary is playing animportant role in this field. It is especiallyinvolved in the practice of occupational healthmedicine and also de.als with curative,preventive and emergency medical care. Itcarries out initial medical examination of newrecruits and trainees; periodical medicalexamination; examination of over exposurecases from DAE and all over India;Management of radiation injuries all overIndia; and consultancy on radioactivityproblems all over India.

VASHI INDUSTRIAL DISPENSARY

Vashi Industrial Dispensary, Turbhecarries out periodic medical examinations ofstaff of Board of Radiation and IsotopeTechnology working with radioisotopes; andstaff of Powder Metallurgy Division andBeryllium Machining Facility. It also conductsannual spirometry evaluation of Berylliumemployees; routine medical care for illnessand injuries; motivation of employees togive up alcohol/smoking/tobacco chewing;ergonomic advice for proper methods of liftingweight for prevention of backache; safetyeducation of employees; m,d emergencymanagement and transfer of patients afterstabilisation,

II

The dispensary is equipped with Electro-cardiograph, Spirometer, Computer andOxygen cylinder. Ambulance is availableround the clock for transfer of serious cases.

Record keeping is uptodate and details about

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past/present illnesses along with theirpathology and radiology reports aremaintained on the computer for easy retrievaland reference. The follow up for patientssuffering from chronic diseases is doneregularly.

BARC HOSPITAL

-*~-Frantview of BARC Hospital

E.N.T.

The department has widened its scope fromdiagnosis and management of diseasedconditions of the ear, nose, throat, head and

neck, by including also preventive and

rehabilitative medicine. At-risk patients such asthose working in noisy areas, aged patientsand children are regularly screened for hearing

problmes. Early detection of such cases helpsin their proper management and rehabilitation.

Patients are trained in proper use of hearingaids. Patients with speech defects and chronic

conditions like allergies and giddines requireconsiderable training, support and follow upin addition to medications. A great deal ofstress is laid on these aspects.

Tbe ENT department is equipped with stateof the art diagnostic aids such as the flexibleand rigid endoscopes, a sophisticatedoperating microscope and an ENT work unit.

Thc Audiology set up at the department isrelatively new, but very good with a soundtrcatcd room, modern audiometer and

impedence1\udiometer. All these are invaluable

in cffectivc diagnosis and management of thepatients. The departcnt not only caters toroutine ENT surgical conditions but also headand neck malignancics, plastic surgery of noseand conditions like sleep apnoea. Lasers in

12

ENT and functional endoscopic sinus surgeryare two other fields of rapid dcvelopment to thegreat satisfaction of ENT surgeons

Dr Nalini Bhut, ENT SpecU/list, examines apatient

"~ PATHOLOGY

In 1976 the Pathology laboratory wasshifted from Richardson & Cruddas buildingand JJ.Hospital to the BARC Hospital. TheLaboratory is equipped with a range ofsophisticated equipment procured to performlatest blood investigations possible in thecentralised laboratory located in the BARCHospital, with two extensions at AnandBhavan Diagnostic Centre and at TrombayDispensary.

The Pathology unit has a team of threedoctors, 30 technicians, one administrativestaff and six Helpers fully engaged inperforming approximately 300,000 bloodinvestigations each year The laboratoryfunctions on round-the-clock shift basis.

KeeplOg pace with changing times, the

laboratory geared up to accept the latest

technologies and techniques and therebyintroduced investigations like ELISA testingfor AIDS, Hepatitis, TORCH, Blood GasAnalysis and other tests like Fine Needle

Aspiration Cytology (FNAC), etc. We alsogot our Blood Bank approved from Food aod

Drug Administration and opened a newCytogenetic Laboratory. Our latest acquisition

was the two fully automated BiochemistryAnalyse!'s which are sophisticated equipment.With the installation of these biochemistryanalysers, we have vastly improved theaccuracy, quality and speed of investigatrons.The quality control programmes are carried

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out on these machines every day for attainingperfect, reliable and consistent results.Additionally, we have semi-automatic bio-chemistry analysers in our laboratory as well asat our Diagnostic Centres at Anand Bhavan andTrombay Dispensaries. The Blood GasAnalyser with us is a vital equipment meant forcritically ill patients whose blood gas analysisgreatly helps our doctors in assessing theprognosis of the patient and deciding the lineof treatment. Plans are afoot to haveautomated systems for Haematology,Diagnostic Molecular Biology and BloodComponent facilities.

Our blood bank has been meeting the bloodrequirements of our patients to a large extent.Topmost priority is given to screen the bloodfor diseases like AIDS, Hepatitis B & C,Malaria and Syphilis before the blood is issuedto the patient. The Laboratory has facilities forhistopathological examination of biopsies andtissues received from the Operation Theatre orSurgical OPD which helps in diagnosis ofcancers and non-cancerous diseases.Additionally we have Fine Needle AspirationCytology (FNAC) and Frozen Sectionexamination done regularly to carry out rapidandintra"operative diagnosis of cancer.

Pathology laboratory

The cytogenetic laboratory was establishedin 1994 to screen newborns and patientsattending genetic counselling clinic for anychromosomal aberrations.

Computerising of all reports, with all reportforms designed by color coding, helps ourconsultants to speedily reach the required

report in the medical file of a patient beingattended to. Aproximately 350 to 400 reports

are generated daily which are despatched to theconcerned OPDs, Wards and Dispensaries.

PAEDIATRIC

The Paediatric department has fourconsultants and three residents who offerpreventive and curative care to about 15,000children (about 20% of CHSS beneficiaries).We aspire to offer the best patient care possibleand in turn aim to achieve high patientsatisfaction.

We have a ward and neonatal intensive careunit (NICU) equipped with paediatricventilator, pulse oximeter, vital sign monitors,defibrillator, neonatal rescuscitation trollysetc.. We are ably assisted by efficient nursingstaff in offering routine as well as critical care.We run a well baby cliuic once a week and ourOPD functions 6 days a week. We alsoconduct genetic clinic and school health clinic.Most of the patients are managed in the BARCHospital. A few patients requiring superspeciality care are referred to referral hospitals.We are a referral centre for other DAB unitsand we manage their patients with complexproblems. Vaccine preventable diseases likediptheria, pertussis (whooping .cough), tetanus,and poliomyelitis are not seen for the past 15years in our set up due to our highimmunisation coverage. Incidence of diseaseslike measles, mumps and rubella also hasdrastically reduced because of the introductionofMMR vaccine for over 10 years.

Our hospital was recognised as "BABYFRIENDLY HOSPITAL" by National TaskForce in 1990. We trained our medical andparamedical staff to promote exclusive breastfeeding. We have trained medical personnel inother hospitals too. Breast feeding promotionhas resulted in increased awareness amongstmothers thus resulting in decreased incidenceof upper respiratory tract infections and gastroenteritis.

13

With optimal preventive and curative carethe neonatal, infant and under five mortality ismuch less than the national figures and iscomparable to figures in western countries.The incidence of congenital anomalies in ourpopulation is very low, thus allaying fears

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about radiation expos~re leading to mal-fOimations.

An infant in the Paediatric unit

OBSTETRIC & GYNAECOLOGY

Prenatal examination ofa patient

Over the years Obstetrics & Gynaecologydepartment has shown progress in terms ofadaptation of innovatIve changes andadditions to its field of work. Right from itsinception, a lot of emphasis has been laid onpreventive programmes like antenatalsurveillance and annual gynaec check-ups.High risk antenatal clinics are being conducted.The thrust areas in the clinic are intra-uterinegrowth retardation (IUGR) and pre-eclamptictoxemia. Intensive antenatal and intrapatummonitoring is being done with the aid ofelectronic foetal heart rate monitoring, cardio-tocography, ultrasonography - doppler andlevel II. The achievements in the obstetricshave been no eclampsia, no septic cases,decreased instrumental and complicateddelivery and decreased maternal morbidity.There has been no maternal mortality in the last10 years. Annual gynaec check-up includingpap smears, colposcopy and transvaginalsonography have helped in early detection ofpelvic disease!cancer. Hormone replacement

therapy clinics are being conducted. This hasdrastically improved the quality of life inpostmenopausal wnmen. Facilities like electroand cryo surgery and CO2 laser are available inthe outpatient department

The department has a fully equippednperation theatre. The use of endoscopy(laparoscopyand hysterscopy) has extended tooperative procedures from the diagnostic one.Video assisted endoscopic surgeries arepresently heing performed, which areminimally invasive and has definitely reducedthe operative morbidity and hospital stay.

The challenges being faced now arecongenital abnormalities and metabolicdisorders and this has called for theintroduction of genetic counselling clinic andprenatal diagnosis. With the strict ante andintranatal surveillance and the back up facilityof intensive neonatal care, the perinatalmortality is comparable with internationalstatistics. The small family norms are beingencouraged and modern methods ofcontraception are being advocated.

PHYSIOTHERAPY

Of the 60-70 cases daily attending thedepartment (including ward patients)approximately 50% are for management ofpain and musculoskeletal disorders. The goal isto evaluate and to reduce impairments anddisabilities. For pain management, apart fromusing usual modalities like short wavediathermy, ultrasound, transcutaneus electroneuromuscular stimulator, techniques ofmanual therapy are applied. Manual therapyintroduced since the last three years is used to

A patient bemg treated ill pln.","hempy uhit14

Page 15: Kamala Balakrishnan - Bhabha Atomic Research Centre

restore fonctions of joints and spine and reducepain.

Manipulations for cervical spondylosis andlow frequency currents in peripheral nerveinjuries and facial palsy are importantprocedures performed in the department.

Various sets of exercises and procedures arecarried out in different conditions anddisorders.

Follow up of patients depending uponcourse of disorders is done regularly

It is proposed to start the following

.:. Pain clinic,.:. Obesity clinic, and.:. Computerisation of the patients data,

SOCIAL SERVICES

Since its inception in 1965, this departmenthas been engaged in psychosocial diagnosis,treatment ancl rehabilitation of variegated

social problems and medico social problemsdue to various illnesses. Appropriatesocial and counselling

methods arc for resolving these

problems to a maximum possible extent torestore their functioning and to

alley anxiety stress by mobilising humanas well as material resources, A number of

were organised by theunit.

Work related to Benevolent Fund and

Family Relief Scheme is also carried out bySocial Service unit.

PSYCHIATRY

The Psychiatry deparatment has two fulltime Psychiatrists, one Psychiatric Social-

Worker, one Part time Clinical Psychologistand one Panel Psychologist handling anaverage of 600 patients every month.

The Department has extended its servicesin area of occupational health on preventivebasis by undertaking the Preliminary AptitudeTest (PAT) as a part of pre-recruitmentanalysis for Trainees and Post-Graduate

Trainees recruited every year. As an extension

of this programme, the recruited Trainees arefollowed up regularly for guidance and supportsince the last five years,

RADIOLOGY

The Radiology department of BARCHospital provides diagnostic radiologicalservices to the beneficiaries of CHSScomprising of employees of DAE and theirdependants.

The department provides the followingservices:

.:. Radingraphy,

.:. Ultrasonography, and

.:. Colour Doppler Studies.

The department is equipped with threeX-ray machines including Image Intensifierfor daylight fluoroscopy and five Mobile X-rayUnits for bedside and Intra-OperativeRadiography. The department works round theclock and one technician is always availableafter OPD hours. One X-ray Unit is installedin Casualty department for immediate attentionof patients coming to Casualty.

Dr Sabhash Narang, Radiologist supervises theinvestigation of a patient

The services provided are ConventionalRadiography i.e. X-Rays of all types andspecial investigative diagnostic procedurescomprising of oral and intravenous contraststudies viz. Barium Studies like BariuruSwallow for evaluation of patients havingproblems of swallowing and tumors of thefood-pipe: Barium .meai & Follow Throughstudies for diagnosis of diseases like ulcers

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Page 16: Kamala Balakrishnan - Bhabha Atomic Research Centre

and growth in the stomach, tuberculosis of thesmall intestine and malabsorption syndrome,etc. Barium Enema studies for the evaluationof patients suffering from diseases of largebowel and rectum like long standingconstipation,ulcerative colitis, growths andtumors of. large bowel. Intravenouspyelograms for evaluation of patients ofailments of kidneys, hysterosalphingograms forevaluation of patients of infertility anddiseases of the uterus, and fistilographies forpatients suffering from fistula-in-ano beforeundergoing surgical procedure for its treatmentare some of the services rendered by this unit.

1.The Ultrasonography Unit is equipped with:

Two Ultrasonography Machines forRoutine Sonography and Colour DopplerStudies for Whole Body applicationsincluding 2 D echocardiograpby

2. One Portable Ultrasonograpby Machinefor bedside sonography.

Studies are carried out for assessment ofdiseases of liver, gall bladder, pancreas andspleen and other mass lesions in abdomen.Ultrasonography of chest for evaluation andfollow up of patients having accumulation ofwater or blood in chest cavity, andgynaecolgical studies to visualise and assessdisease of uterus and ovaries, are also done.

SURGICAL

The surgical services consisting of General

Surgery, supported by the Anaesthesiologyunit deal with surgeries like Hernia,

Hydrocele, Swelling excisions, Gall bladderand Renal stone surgeries, breast tumors and

other Urological work. There were fewer casesof benign and malignant tumors of various

organs. Emergency cases such as Appendicitis,Bowel Perforations and obstructions and other

Urological cases were an occasional problemwhich were handled. The Minor Surgical

Operation Theatre handle cases of Vasectomywith other minor excisions.

Fracture and Trauma cases were handled bythe unit, with major trauma cases of hip andlong bones. Except for cardiac and neuro-surgical operative procedures, this unit

16

undertakes it!! surgical procedures pertainingto general surgery, urology, plastic surgery,cancer surgery, maxilla-fascial surgeries etc.The unit regularly carries out endoscopicprocedures, involving upper gastro-intestinalarea, urinary system and abdnmen. As this unithas updated urological instrumentation,endourological procedures like endoscopicresection of enlarged prostate, bladder tumours,crushing of bladder stones and removal ofrenal stones by PCNL are routinely carriedout.

The C.H.S.S population has been increasingwith many of the employees aging anddeveloping chronic diseases like Diabetes,Hypertension and Respiratory Diseases. Henceto cater to the needs of these high risk groupsthe surgical unit has developed strict protocolsand has also been laying emphasis on day caresurgeries with the help of key hole surgeriesand other interventional surgeries. This hascontributed in reducing the morbidity and thenosocomial infections with strict asepticprecautions and a rigid and ethical antibioticpolicy.

The surgical unit has four full-timeconsultants, four residents and two honsesurgeons. The Surgical Unit is recognized totrain post-graduates for the national board ofexaminations.

A view of action in the Operation Theatre

ORTHOPEDIC

Besides treating routine fracture and traumacases, orthopaedic problems like chronicarthritis, backaches and neckaches, congenitalbone defects and bone deformities and boneinfections and tumors are also being handledby this uni..

Page 17: Kamala Balakrishnan - Bhabha Atomic Research Centre

The monthly outpatient attendance of thisunit has increased to about 700-800 from about80-90 during the earlier years. Whereas themajor Orthopaedic Surgical procedures in themain theatre in a month were about 3-4. we areperforming now about 15-20.

Keeping in touch with the latest techniquesof operative treatment of fractures, which layemphasis on faster mobilization of the patient,reduction of morbidity and reduction of bedoccupancy by way of extensive physiotherapy,we have acquired operative instrumentationsets for various fractures of the long bonesand have used them successfully in a series ofpatients achieving results which can comparewith those of any trauma management centre.

This unit undertakes major orthopedicprocedures like partial hip replacements,interlocking nailings, external fixat"rs, spinalsurgeries, and arthroscopies with the help of animage intensifier system. With the increase inthe geriatric population among the CHSSbeneficiaries, the occurences of trauma in theelderly has been on the rise leading to manycases of hip, knee, ankle, shoulder, elbow andwrist joint fractures along with long bones.This unit carries out major challengingoperative procedures successfully on patientseven beyond 90 years of age, giving themquality of life with independence in activitiesof daily life.

With a complement of two orthopedicsurgeons, a part time consultant and oneresident and a house-surgeon, this unit has tenbeds for inpatients and a regular OPD.

ANESTHESIOLOGY

With a strength of five experienced andqualified anesthesiologistsand a resident traineein anesthesia, this unit caters to therequirements of surgical operative proceduresand intensive care.

Anesthesia unit offers its expertise tovarious units which include surgical,orthopedic, ophthalmology, ENT, dental,psychiatry and gyaenacology & obstetricsunits. The unit renders pre operativeassessment, planning and administration of

anesthesia and analgesia requirements, andpost operative management.

This unit handles about 3,500 patients whorequire surgical care. Besides catering to meelective and emergency operative procedures;it conducts day time anaesthetic procedures,for ECT's in Psychiatry O.P.D. and for Dentalpatients in its O.P.D.

The hospital has four major and four minoroperating rooms. These areas are wellequipped with all the mandatory safetymonitoring devices In recent yeafs, byacquiring latest equipments, such as ventilatorsand patient monitoring devices, the anesthesiaunit is meeting the International mandatorymonitoring Standards.

Recently the unit has acquired twosophisticated Multi parameter patientmonitoring systems for the intra-operativemanagement of the patients. From this yearAnesthesia unit started offering "Labouranalgesia services" to the young expectantmothers. Service offered is optional hence willrequire patient acceptance and availability ofmanpower in the unit.

Dr Balbir Singh attends to a patient in theICCU

The Intensive Cardiac Care Vnit has eightbeds which takes care of acute cardiacemergncies like different cardiac arrhythmias,LVF, cardia genic shock, different types ofheart blocks and bradycardia.

Invasive procedures like CVP monitoring,Trans Venous Pacing, etc. are also being donein the ICCV. Cardiac arrhythmias are treatedwith Cardirone and DC Defibrillation.

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Page 18: Kamala Balakrishnan - Bhabha Atomic Research Centre

Thrombolytic agents like Streptokinase andUrokinase are very frequently used to dissolvethe thrombus. Many acute complicated cases ofcardiogenic shock and malignant arrhythmiaswere treated by the above measures.

Coronary angiograms are regularlyreviewed with the help of DACARNO whichis available in the ICCU.

Facilities for ABP Monitoring and HolterMonitoring are also available.

As preventive cardiology work up. averageof 8-10 stress tests are being penonned in theICCU. This helps us in detecting CoronaryHeart Disease at the very early stage and cantake preventive measures

A Bombay Heart Brigade 105 is alsostationed in the ICCU which takes care ofacute cardiac emergencies in the near vicinity.A fully equipped ambulance with a doctor andnurse is being sent to the house of the needycardiac patients on receiving a call on 105.Emergency medical treatment is being given athome and the patient is transferred to thenearest hospital of their choice.

OPTHALMOLOGY

The Ophthalmic departament is well-equipped. The outpatients eye department andthe Ophtbalmic thheatre are situated next toeach other. This helps in the smooth runningof the department especially in case ofemergencies where surgery is required.

In the OPD mostly patients complaining ofvisual disturbances are seen along with patients

complaining of redness, irritation, itching, etc.Referrals from other OPD's and dispensariesare seen daily on appointment basis.

The Ophthalmic Department receivesreferral from units of DAE all over India fordiagnosis of complicated cases, surgeries andspecialised eye investigations like automatedperimetry, indirect opthalmoscopy and 'A' scanbiometry.

In the operation theatre besides routinecases like cataract extraction with intraocularlens implantation other surgies like anti-glaucoma surgery, squint correction, lacrimalsac surgeries are done

" ~Dr V. Karira, Opthalmologist, examines apatient

DENTISTRY

With the commissioning of the BARCHospital in 1976, the then Dental facilityconsisted of total four units -two of them at thehospital and one each attached to Trombay andAnand Bhavan Dispensaries.

With the ever-increasing demand on the unit,in the span of a short period, three moreoperatories were commissioned within theDental OPD Complex at the hospital. Hence,today the expanded facility has grown to sevenfull-fledged operatories. A full-time DentalHygienist is available at the hospital takingcare of patients needing Dental prophylaxisand guidance on the maintanance of oralhygiene procedures. A highly experiencedMaxillo-facial and oral surgeon has also beenappointed on the panel for specialised surgicalprocedures.

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Page 19: Kamala Balakrishnan - Bhabha Atomic Research Centre

The employees as well as their familymembers are distributed zonewise to eithertbe hospital or Anand Bhavan & Trombaydental facilities in order to ensure maximumconvenience to the large population ofbeneficiaries.

Most of tbe Dental operatories are equippedwitb a state of the art instrumentarium and tbe

rest are expected to be upgraded in the nearfuture. The Department of Dentistry has always

been and more so today, a model of efficiencyand one of the most well-run units in the

Division. It is comparable to the best anywhereand offers the latest procedures in the variousDental specialities such as :

Restorative Dentistry, Endodontics, Cosmetic

Dentistry, Orthododntics, Prosthetics andCrown & Bridge, Oral and Maxillofacial

Dr K.R. Munim, Dental Surgeon, working on apatient

Surgery, Orthognathic Surgery, Pedodontics,Periodontics, Dental Radiography end DentalImplants.

The Dental Unit is a self sufficient unit,having all treatment modalities available in-house, thus negating any external referencerequirements.

INFORMATION MANAGEMENT

To keep pace with growing patientsinformation it was decided to induct moderninformation management technology forprocessing of hospital information. Theadvantages of such a system would beavailability of an orderly set of patientinformation, faster retrieval of documents,decentralised access to data bank, systematicarchival, uniformity in information format,reduced duplication, better clarity, higheraccuracy, etc. Computer Division of BARC,was entrusted with installation andcommissioning of computer system. Thecomputer system comprises of Landmark-486CPU with 16 MB RAM, 27 terminals, 15local printers, UNIX Operating System andORACLE Data Base Managaement System, Inconsultation with the end-users, more than 80computer screen forms has been developed andintegrated to the patients' database for use inthe hospital. Various user departments havebeen provided with the computer terminal &local printer for their daily use.

"1:1IillIlF=~===~~~==~- ~==,=====,~i1!iI'!Io."'111\1!1"' "'111\1!1"'

FACILITYFOR INTEGRALSYSTEMBEHAVIOUREXPERIMENTS(FISBE)

Introduction

Reactor Design and Development Group

The collrse of events during accidentscenarios and operational transients IIIPressurised Heavy Water Reactors (PHWRs)involves complex single-phase and two-phasethermal hydraulic phenomena like flow coast-down, thermosyphon, blowdown, refluxcondensation, rewetting etc, The effect of suchphenomena occurring in isolated componentscan be..studied by making a model of thecomponent and conducting appropriateexperiments on it. Theoretical models can then

be developed based on the results of suchexperiments, Such tests are termed as separateeffects tests, Separate effects tests have beenconducted to study some of the phenomenamentioned above and theoretical models have

been developed. Such component/subsystemmodels are integrated into system models/codes for complex systems like nuclearreactors, The response of such a multi-component system could be different from theresponse of individual components studiedseparately, because of interaction effects,

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Page 20: Kamala Balakrishnan - Bhabha Atomic Research Centre

Hence, it becomes necessary to have integraltest facilities for carrying out studies on multi-component systems like reactot loops. Anumber of integral test facilities have beenconstructed, mainly in advanced countries. Theintegral test facilities in countries like the USA,France, Italy, Germany, Japan and Hungary arerelated to Light Water Reactors. For PHWRtype of reactors, integral test facilities havebeen built in Canada, where, presently theRD-14M facility is operational. To generatedata related to Indian PHWRs, an integral testfacility, the Facility for Integral SystemBehaviour Experiments (FISBE) has been setup in the Annexe to Hall-7 at Trombay. Thisfacility closely simulates the Primary HeatTransport System and associated componentsof the secondary system of the IndianPressurised Heavy Water Reactor. This facilitywill be used for Loss Of Coolant Accident

(LOCA) and other operational transientexperiments in a phased manner over a periodof time. Fig. I depicts the huilding housingthe facility.

Fig I An""xe to Hull 7 that ho",e.' FlSBE

Ohjectives

Thc object"es can be """l11ansed as follows:

I. To understand the phenomenathat occur during conditionsand operational transocnts.

2. Creation of data base for the assessmentand validation of thermal hydrauliccomputer codes used for predicting thetransient behaviour during accidents and,operational transients.To test recovery methods and operationalprocedures to bring prototype PHWRs toa safe shut down state following possibleabnormal situations.

3.

Scaling

Appropriate scaling philosophy is adopted,maintaining the same elevations as in thereactor. Because of this, the total loop height is39 m. Power to volume scaling philosophy isfollowed in the design of the facility. Volumescaling in respect of 220 MWe PHWR units is1:76.5. For the 500 MWe unit, the volumescaling is I :98 with respect to one of the twoFigure of Eight loops of the Primary HeatTransport (PHT) system. The design pressureand temperature of the facility enablesobtaining initial operating conditions same asin the PHWRs. Time scale is preserved.

Description

Flow sheet of the facility is shown in Fig.2. The facility consists of the following mainsystems:(I) Figure of Eight Primary Coolant Loop,(2) Feed and Bleed System,(3) Emergency Core Cooling System (ECeS),(4) Steam Generator (SG) Feed Water System(5) Break Flow System.

20

The Figure of Eight loop comprises thetest sections/Fuel Channel Simulators, feeders,

headers, pump simulators, steam generatorsand the pipe lines connecting the pumpsimulators and steam generators with theheaders. The feed and bleed system is providedto maintain the PHT system pressure andinventory. The components in the feed and

bleed system include the PHT system storagetank, primary feed pump, bleed cooler and ionexchange columns. The emergency core

cooling system consists of the high pressureaccumulator, the nitrogen tank and the ECCS

pump. The SG feed water system is provided tofeed water into the secondary side of the

coolers. The break flow system is provided for

Page 21: Kamala Balakrishnan - Bhabha Atomic Research Centre

I

r

simulating breaks of different sizes as part ofLOCA studies and to conect ! discharge thebreak flow. Components like .feed controlvalves, bleed control valve, instrumented reliefvalve, motorised valves, ASDV etc. areprovided at appropriate locations in the facility,as in the prototype, for effective simulation ofthe transients. Also, the electrical power supplysystem of the facility is designed to simulatethe effects like power setback in the prototypereactor.

The test facility is extensivelyinstrumented to measure temperature, flowrate, pressure! differential pressure, level,density etc., at various points in the loop.Provisions have been made in FISBE forpressure measurements at 33 locations andtemperature measurements at 230 locations.The transients that are to be measured are veryfast. Hence, a Fast Data Acquisition System(FDAS) with a capacity of 256 channels and ascanning speed of 10000 channels per secondis provided for FISBE. The FDAS hasprovision for programming different scanningrates for different parameters as well as duringdifferent phases of the transient underinvestigation.

Description of FISBE Flow Sheet

f:

The heat input is given to the TestSections/Fuel Channel Simulators through theDC power supply. The water gets heated upand nows up to the outlet headers. The outletheaders are connected to the SGs wherein theheat is transferred to the secondary side of theloop. The primary coolant leaving the SGs isled through the pump simulators to the inletheaders. From the inlet headers, water nowsback to the Test Sections thus completing theloop. The primary side of the loop is providedwith a Feed and Bleed system. Under normaloperating conditions, a constant bleed now ismaintained through the purification system forchemistry control which is put back into theloop through the storage tank. A bleed cooler isprovided to cool the bleed to lowertemperatures acceptable to the purificationsYStem. Depending on the outlet headerpressure. the syStem inventory is adjusted bythe bleed and feed control valves. The feed ispumped from the storage tank to one of the

21

outlet headers. An Emergency Core CoolingSystem is provided as in the prototype reactor.It consists of a High pressure Accumulatorwhich, in case of LOCA experiments, wouldinject water into both the inlet headers.Actuation of HPA is through a motorisedvalve. Provision for simulation of injection ofwater from fire-fighting system, as in theprototype reactor, is also provided. For thispurpose, water from a storage tank is pumpedinto the SGs in case depletion of inventoryoccurs in the secondary side of the SG. Thesecondary side feed is from a reciprocatingpump, drawing water from a Storage tank. Abreak now system is also provided in thefacility to enable carrying out LOCAexperiments simulating different break sizes. Itconsists of an orifice whose size simulates therequired break size and a valve, the opening ofwhich simulates a 'break' in the system. Thedischarge from this break can be collected andcooled in a storage tank.

Experiments Planned

Experiments planned in the facility in thefirst phase include:I. Single-phase natural circulation,2. Two-phase natural circulation,3. Renux condensation behaviour,4. Station black-out and5. LOCA with single-phase natural circulation

as initial condition.

It is planned to further augment the facilityduring the ninth plan period. The range andtype of experiments will be enhanced in theaugmented facility.

MAIN PARAMETERS

(a) Primary SideDesign Pressure .Design Temperature:Fluid handled

125 kg/cm'343'CDemineralisedwaterMaximum of3MWDC

Power supply

(b) Secondary SideDesign Pressure .Design Temperature:Fluid handled

70 kg/em'285'CDemineralisedwater

Page 22: Kamala Balakrishnan - Bhabha Atomic Research Centre

W><I<!L

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s~. "" , SOUTH."""", INlETHEADERSSOO. NOli, SOUTH."""", 0IJTlETHEADERSBC , Bl£EDCOOlERPS , PUMPSlMUlAlURWV . """'R!SED""-lIE

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FIG.2

PHT SYSTEM (RG. OF EiGH1)

PHT SYSTEM (FEED .. Bl£ED)

SECONDARY SIDE

ECCS .. RRE RGHTING SYSTE"

BREAK FLOW SYSTEM

SCHEMATIC OF FISBE FLOW SHEET

Page 23: Kamala Balakrishnan - Bhabha Atomic Research Centre

DIGITALIMAGING OF NEUTRONS AND ITS APPLICATIONS

Amar Sinha

Condensed Matter Physics Division

Introduction

Neutron imaging finds applications inmany branches of science and industry such asin nondestructive testing, material science etc.Conventional imaging of neutrons has beencarried out mostly using analogue technologysuch as screen film imaging. Making transitionfrom analogue to digital could bring severaladvantages such as fast image acquisition anddisplay, implementation of image processing,quantitative interpretation of data etc. Suchdigital imagmg techniques also open uppossibility to carry out certain new class ofexperiments such as dynamic imaging whichare quite difficult or impossible to carry outwith the conventional analogue technology.

We have been working on digitalimaging of neutrons for various applicationsusing'Charge'Cou!,led Device (CCD) baseddetectors. A number of such systems have beendeveloped at BARC for applications like twoand three dimensional neutron tomography,two phase flow visualization and void fractionmeasurement inside metallic pipes, neutronradiography with non reactor sources etc. Inthis article we describe some of the prototypesystems developed using CCD based digitalneutron imaging techniques.

Electronic imaging technique of neutronradiography

Conventionally neutron radiographyhas been carried out using film basedtechniques. However with the advent of digitalimaging technique, the film based techniqueshave been complimented with digital CCDbased imaging method. One of the techniquesof electronic imaging of neutrons is to use alarge area image intensifier tube with neutronsensitive material directly deposited onto thephotocathode of intensifier. However such acamera system is at present quite costly and not

easily adaptable for different types ofapplications. We have adopted a relativelycheaper approach of using an imageintensifier/CCD combination coupled through alens to a large area neutron scintillator. A realtime neutron radiography system based on thisapproach has been developed and tested atAPSARA reactor. The schematic diagram ofthis setup is shown in Fig.l. The neutron beampassing through the sample is absorbed in ascintillator screen made up of 6LiF+ZnS (NE-426). The optical photons generated by thescintillating screen are reflected at 90 degreesand focussed onto the input fibre optic face ofan image intensifier tube. The scintillation lightis intensified by the image intensifier tube andthe output of intensifier is optically coupled toa CCD camera. The output of CCD carnera isdigitized and processed using a frame grabbercum processor and simultaneously displayedon a video monitor[I].

""""'~."H",""""~mcr..

Fig./ Schematic diagram of a prolotypeeleclronic imaging system al APSARA

23

Some of the radiography images obtained usingthis setup are shown in Figs 2 &3. Fig.2 showsthe image of a carburetor and Fig.3 that of anexperimental fuel pin. These images areobtained after few seconds of integration time.In fact this imaging system is so sensitive thateven real time movement of objects can bevisualized on video screen. This opens up thepossibility of examining moving parts of theobject or visualizing flow pattern of a fluid.

Page 24: Kamala Balakrishnan - Bhabha Atomic Research Centre

Fig2 /iodwgml'h, image "/0 C!lrhoreiOi

(b) Two phase flow visualization insidemetallic pipes

Visualization and analysis of water/air orwater/vapour two phase flow inside metallicpipes under high temperature and pressure is ofconsiderahle importance in thermal hydraulicsdesign of nuclear reactors. Conventionallyvisualization experiments on two phase floware conducted using transparent glass sectionswhich do not permit simulation of highpressure and temperature conditions. Similarlyother methods like conductance probe orgamma ray based techniques do not permit realtime visualization of flow pattern. Neutronshave the unique property that they can

penetrate inside dense material such as steelbut get attenuated easily by water. This makesthem an unique probe to visualize water/airflnw or water flow condition inside

metallic pipes. property of neutrons hasbeen utilized for developing an electronicimaging setup for real time two phase flowvisualization and void traction measurementinside SS or aluminum pipe (optically opaquechannels).

Culibmtioll test loopfor study of tworeactor

This system has rhe capability to computeonline void fraction for air/water two phaseflow using image processing techniques. Theaccuracy of this method of void fractioncalculation has been tested by using several testpieces of perspex having a number of holessimulating varying void fractions. A test loopto simulate various flow conditions likeannular, slug or bubbly inside aluminumlSSpipe has been fabricated. The schematicdiagram of this test loop is shown in FigA. Theimaging system for two phase flowvisualization has been successfully tested atAPSARA reactor using this test loop. Fig.Sshows images of different flow patterns ofwater/air flow inside aluminum pipe. Fig.6shows result at online computer plot of voidfraction measured over a small section of pipe.

24

Page 25: Kamala Balakrishnan - Bhabha Atomic Research Centre

The dashed curve shows instantaneous valuesof measured void fraction over this smail

section of pipe. The instantaneous values areexpected to !luctuate as the flow of mixture ofair and water passes over this section. We have

also plotted moving time averaged void

fraction values which are shown in the plot assolid lines. In collaboration with Reactor

Engineering Division. a second test loop tosimulate flow condition in a natural circulation

loop like tbose envisaged for Advanced HeavyWater Reactor has recently been fabricatedwhich contains various other sensors such asconductance probe for void fraction

measurement. This loop is presently beingassembled and tested. This experiment is

designed to tes! the neutron radiographymethod of two phase flow visualization andvoid fraction calculation and its inter-

comparison with other methods under realistic

conditions of hIgh temperature and pressure.

Two dimensional (2D) tomography

Though radiography is being routinelyused for nondestructive evaluations, computedtomography is a relatively recent addition toNDE. It overcomes many of the limitations ofradiography and makes possible visualizationof physical structures in their relative spatialpositions and orientations. Conventionallytomography has been carried out using firstgeneration translate-rotate system consisting ofphotomultiplier based detectors. However suchsystems are not especially suited for neutronsas the time taken in obtaining just one scan(slice image) is in hours. It also results in usinga small part of neutron beam (only a pencilbeam) which is otherwise quite costly toproduce. We have developed [I] a neutrontomography system based on CCD techniqueand successfully used it at APSARA reactor forobtaining neutron CT scan of several test andindustrial samples. The main advantage ofCCD hased tomography system overconventional translatc-rotate tomography is the

of data acquisition as even for fairlysamples only rotation steps are required

sample manipulation.

Neurron CT scan of the object described

25

Page 26: Kamala Balakrishnan - Bhabha Atomic Research Centre

In this method, the sample to be imaged is

placed on a stepper motor controlled rotaryplatform, Images of the sample are obtained atvarious angles by rotating the sample. Theneutron tomography system developed for thispurpose is fully automatic with integratedimage acquisition using electronic imagingtechnique and stepper motor control. These

images are preprocessed and subjected toreconstruction algorithm developed in housefor obtaining CT scan images. Fig.7 showspicture of an object made up of aluminum of60mm diameter and containing 9 SS rods of3mm diameter and 10 brass rods of 3mm

diameter. Fig.S shows CT scan of this object.We have been able to distinguish between SS

and brass rods. This is shown in Fig.9 byadjusting the contrast and suitably thresholdingthe CT scan image.

The spatial resolution obtained withthis CT system is better than fmm. Testsamples made up of different materials andcontaining holes and rods of various sizes aslow as 300 micron in diameter have been usedfor characterization of this tomography system.The resolution of this technique is limited bycharacteristics of CCD and demagnificationused and can be further improved by usinghigb resolution cooled CCD. Care has also tobe taken in minimizing or correcting for tbeeffects of scattering wbicb resulis in crosscorrelation of different imagingelements.

Three dimensional (3D) tomography:

In recent years witb the advent of CTscan systems capable of giving multiple slicesin sbort time and availability of fast computers,reconstruction tecbniques of obtaining 3Dimages from 2D tomograpby slices is at theforefront of investigation in medical imagingand bas a become a very powerful simulationtool for surgeons. It is now possible tointeractively examine and see through theinterior of an object in three dimension bycombining 2D CT scan data into a 3D volumedata. Applications of such techniques forindustrial purpose bave been rather limited. Wehave extended this technique to the threedimensional visualization of the interior ofindustrial Tbe CCD technique oftomography particularly suitable for thispurpose as multiple slices of an object can beobtaIned in very short time.

[Stj- .-

Aluminum

'.- --~. ole

C ~-- ~~' Co.Brass Holder

of the object at

26

Page 27: Kamala Balakrishnan - Bhabha Atomic Research Centre

To test this technique, we have used a testobject in the form of an off centered cone madeup of stainless steel (SS) embedded insidealuminum matrix of diameter 500101.Fig.1Oshows schematic diagram of this test object.The base diameter of the cone is 340101andlength 350101.At the base of the cone there is a3 0101diameter hole extending upto 100101along its length. At the lower end of the samplethere is also a brass ring for hoiding the object.Fig.11 shows some of the CT scan images ofthis object taken at various distances from thebase of cone. Fig.12 shows a 3D volumerendered image of this object obtained bycombining the multiple 2D CT scan imagesinto a volume data. The transparency of outerlayer has been increased for the visualization ofSS cone inside aluminum matrix. Fig.13 showsa vertical view of this object showinghalf aluminum and half 5S cone.

Cur away view 10 show the hole inside

This helps in examining interior of object suchas the length of hole inside SS cone. The objectcan be opened layer by layer or cut at any angleusing such a visualization technique withoutphysically cutting the material. This is likedoing reverse engineering to an object. Theexample shown here is only a representativeone to demonstrate the powerful features of the3D tomography technique.

Neutron radiogruphy with small neutronsources

Neutron radiography has been shown to bean excellent tool for many nondestructiveevaluation purpose. Unfortunately makingimages from neutrons using conventional filmradiography technique requires large thermalflux. Therefore practical neutron radiographyhas heen mostly carried out at nuclear centershaving nuclear reactors with high thermalneutron flux. This has limited the ofneutron technique ISotherwise an too] and in some casesonly tool for of the NDT applications.Neutron can be developed for fieldapplications a mobile neotron sourcecan be and a more sensitIve methodof neotron be used so that the effect oflow neutron strength of mobile sources can tosome extent be mitigated by more efficientdetection technique. To develop imagingtechniques for a portahle neutron radiographysystem, we have developed a high sensitivityneutron Imaging system which can makeimages by detecting each individual neutronscintillation.

To test the of this detector, we

have assembled a neutron radiography

assembly using Pu-Be sources of total strength107 nls [2-4]. The collimated thermal neutron

flux from this assembly is ~70 nlcm'ls at a LIDratio of 10. Fig.]4 shows radiography Image ofa glass test tube half filled with water which

has been ohtained using this small neutron

radiography assemhly. Fig.IS shows image of abroken piece of hydrogen loaded zircaloy tube.The darker portion in this image indicatepresence of hydrogen. These images have beenmade hy accumulating individual neutronscintillation for a few minutes. The somewhat

27

Page 28: Kamala Balakrishnan - Bhabha Atomic Research Centre

poor quality of these images is mainly due tolow neutron flux (=5 orders of magnitudelower than those available in radiographybeamholes of nuclear reactors).

Though the radiography assembly describedhere is meant only for demonstration of smallsource neutron radiography usi~g a sensitiveneutron detector. it can still be used for manyqualitative radiography applications such aschecking the filling level of charge insideammunition shells and for applications likeexamining blockages in pipes located ininaccessible areas.

Fig. 14 1I""ge '!I a glass ",be half JUied with",ulrr

Fig.15 Image of a broken piece of hydrogenlooded zirealoy tube.

We have also used this detector system toobtain images from a small neutronradiography assembly designed especially forthe 14 MeV neutron gencrator located atPurnima Lab, BARC[5]. The aim of this workis to develop tools and techniques which can beextrapolated for designing imaging system fora mobile neUlron radiography system usingIransportable 14MeV generators (sealed tubes)or other small accelerator based neutrongcnerators. Such mobile systems are beingextensively used abroad particularly for

28

military applications such as the detection ofcorrosion in the structure of military aircraft.

Position sensitive detection of neutrons

Position sensitive detection of neulrons

finds applications in many areas of physicssuch as in neutron diffraction studies, fusionplasma diagnostic, neutron beam profilemonitoring, radiography ctc. Though there arefew offline position sensitive detectionmethods such as Irack etch detectors,photographic method etc. these are quite slowand in many cases difficult to interpretquantitatively. Similarly there are a fewmethods of online position sensitive neutrondetection such as multiwire proportionalcounters, CCD. based detectors etc. Multiwireproportional counters though have an excellenttime resolution, their spatial resolution islimited. In this context CCD based detectionmethod offers a relatively cheaper, easy toassemble, position sensitive online neulrondetection technique with a moderate timeresolution but with a high spatial resolution.We have assembled a position sensitiveneutron detector using a neulron scintillatorcoupled to an image intensifier/CCD and framegrabber. The digitized neutron scintillationimages are displayed online on a video monitorand can be recorded on PC or a VTR forfurther analysis. We have used various kinds ofscintillators for this purpose ranging from

Elastic scintillator for fast neutron detection toLiF+ZnS (NE-426) based detector for tbermal

neulrons One or two image intensifiers areused depending upon the neutron detectionefficiency required and the type of scintillatorused. We have been able to detect individualscintillation images of neulrons from neutronsources of low slrength such =103 nlsec (mCfneutron source) on real time basis. Fig.16shows images of individual thermal neutronscintillations on a 25mm detector area from atbermalized Pu.Be source[6]. In case theneutron detection efficiency is required to beincreased, a large size neutron scintillator canbe lens coupled to intensifier input face. TheCCD/intensifier based thermal neutron detectorusing 6LiF+ZnS is relatively insensitive togamma and x-ray radiation and can be used inplaces of high gamma or x-ray background

Page 29: Kamala Balakrishnan - Bhabha Atomic Research Centre

Fig.16 Neutrou scintillation images

One of the potential applications of thisdetector is in the field of pulsed neutronmonitoring. In this application a hurst of theneutron pulse bunched within a few nanoseconds which are otherwise difficult toseparate electronically. arc detected by usingtheir spatial separation. Feasibility of the CCDdetector for such pulsed neutron detection hasrecently been tested. Further work in this areais cominuing.

Concluding Remarks

In this artiele, we bave presented some ofthe work being carried out at BARC in the fieldof digital imaging of neutrons and theirapplications. The techniques developed forneutrons can also be used for imaging othertypes of radiations such as x-ray and gammaray. We have indeed used these techniques forapplications such as CCD based gammatomography[7], x-ray diffraction imaging[8-9]and medical imaging. The techniquesdeveloped here is being applied to several newareas such as emission tomography which canhelp in providing three dimensional map ofradiation emitting source such as fusionplasma, coded aperture imaging techniquewhich can map neutron emission from laserfusion targets or imaging related to shockedtargets.

ACKNOWLEDGEMENTS

The author would like to thankDr. S. K. Sikka for encouragement and

. 29

suggestions given during the course of thiswork. The contributions of several of mycolleagues in various aspects of this workis acknowledged in particular toDrs. BD. Bhawe, A. M. Shaikh, P.K.Vijyan,Shri CG. Panchal, LV. Kulkarni,Drs. A. Shyam, S. B. Degweker, T.K. Basu,R.P. Anand and V.M. Joshi. The author alsoacknowledges the suggestions given byDr S.K. Kataria for pulsed neutron detection.The author wishes to thank Shri S.C Ojha andhis staff at NPD workshop for fabricating mostof the precision components required in thiswork.

References

I. ASinha, A.M.Shaikh, A.Shyam Nuc/.lnstrum. Meth. B 142 (1998) 425A.Sinha, BD. Bhawe, C.G.Panchal,AShyam, M.Srinivasan, V.M. Joshi, Nuc/.lustrum. Meth. B 108 (1996)408CG.Panchal, A.Sinha, B.D. Bhawe,AShyam, M.Srinivasan, V.M.Joshi, Rev.Sci. lustrum. 67 (1996)2775

A.Sinha, B.D. Bhawe, CG.Panchal,AShyam, M.Srinivasan, V.M. Joshi, Nuc/.lustrum. Meth. Bill (1996)171A.Sinha, B.D. Bhawe, CG.Panchal,A.Shyam, M. Srinivasan, V.M.Joshi, Proc.of "Second International topical meetingou neutron rudiography:system design andcharacterization ", held at RikkyoUniversity, Japan, Nov. 12-18, 1995

2.

3.

4.

5.

6. A.Sinha, BD. Bhawe, CG.Panchal,A.Shyam, M.Srinivasan, V,M. Joshi, Nuc/.Instrum. Meth. A 377 (1996)32A. Sinha, AM.Shaikh, AShyam,LV. Kulkarni, Prac. of twelfth nationalsymposium on Radiation Physics, held atDRDO laboratary, Jadhpur, Jan.28-30,1998.

7.

8. A.Sinha, A.B, Garg, V,Vijay Kumar,B.K.Godwal, S.K.Sikka, paper presentedat the lUMRS-lCA-98 conference held atBangalore, Oct.12-16, 1998A.sinha, Invited paper presented at theSolid State Physics Symposium held at

- Kurukshetra,Dec.27-31,1998

9.

Page 30: Kamala Balakrishnan - Bhabha Atomic Research Centre

..------------.....-----------------..37TH TRAINING COURSE ONRADIOIMMUNOASSAY AND ITSCLINICAL APPLICATIONS

The 37" course on "Radioimmunoassay(RIA) and its Clinical Applications" was

condncted by the Isotope Division at theInstitute of Medical Technology (IMT),

Surat from 8" to 27" Fehruary 1999.Dr. (Mrs.) A.M. Samuel, Director Bio-Medical

Group, inaugurated the course. Dr. Girish Kazi,

Chairman, Sarvajanik Education Society,Surat, presided over the inaugural function. DrP.K. Desai, Director, Institute of Medical

Technology welcomed the participants of thecourse On behalf of Bhabha Atomic Research

Centre and the Institute of 'Medical

Technology. Dr. Meera Venkatesh, Course

Co-ordinator gave an overview about thegenesis of the RIA training course and Itsmetamorphosis into the present form. She alsomentioned that it was for the first time the

course is conducted exclusively for medical

doctors. Of the twenty-four participants,eighteen had post graduate degree in one of the

specialities such as pathology, endocrinologyor microbiology. Dr. S.M. Rao, Head, IsotopeDivision remarked on the importance of theRIA course and the keen interest shown by themedical fraternity towards the establishmentof RIA practice in their laboratories.

Dr (Mrs.) A.M. Samuel in her inauguraladdress gave a glimpse of the history of theRIA technique and the great advances inmedical research and diagnosis that were madepossible thanks to the RIA. She also touched

upon the simplifications that has come in the

RIA technique over the years, which has madeRIA one of the most widely used medicalradioisotope technique in the world. Dr.Samuel also mentioned about the future

techniques such as the multianalyte micros potimmunoassays, which will have the capability

of analysing multiple analytes in a singleautomated assay. Dr Kazi in his presidentialaddress spoke about the need for conscientiousmedical practice that the doctors have to

perpetuate in order to give quality service to30

the patients. He also emphasised the need forjudicious application of RIA training by theparticipants so that needy patients will derivemaximum henefit from this sophisticated tool.

The course included lectures onradioimmunoassay, immunoradiometric assay(IRMA), radioactivity, radiation detection andradiation safety. The participants also carriedout several practicals on RIA and IRMA.At the end of the course both theory andpractical examinations were conducted.Prof. S.D. Bhandarkar, Fonner Head,Department of Endocrinology and Diabetes,G.S. Medical College and K.E.M. Hospitalpresided over the valedictory function.Dr. N. Ramamoorthy, General Manager, BRITspoke on the efforts taken by BRIT in makingthe RIA and IRMA kits available in India at avery competitive price. Dr. M.R.A. Pillai,Head, Radio-pharmaceuticals Section, IsotopeDivision congratulated all the participants forsuccessfully completing the training coursewhich will enahle them to get a license forstarting Radioimmunoassay laboratory in anappmved premise.

-~'"

',.

Dr. (Mrs.) A.M. Samael, Direct"" Bio-MedicalGroup addresses the trainees of the 3th RIAcourse. Dr. P.K. Desai, Director, Institute'Medical and Dr. Girish KcChairman, Socien'. Suratare also seen.

Page 31: Kamala Balakrishnan - Bhabha Atomic Research Centre

The Isotope Division conducts the trainingcourse on "Radioimmunoassay and its ClinicalApplications" twice a year for the benefit of themedical and paramedical professionals. In thepast 19 years, around 850 candidates have beentrained in this course and almost all the 500

RIA laboratories in India are managed byBARC trained RIA professionals. Over the past19 years, nearly 30 fellows from different

developing countries of Asia and Africa regionsponsored by the IAEA also underwent thistraining course.

~-------...."P" ~~~W'

TECH:-IOLO(;Y TRA'iSFER FROMBARC

BARC has translened the technologies onFoldable Solar Dryer and Triode Sputter IonPumps to Mis Chinar Enterprises, Pune andMIs Technovac Corporation, Pune respcctively.The Technology Transfer Agreements weresigned on 12'"February, 1999 in the office ofDirector, Technical Coordination andInternational Relations Group.

Foldable Solar Dryer; This technology wasdeveloped by Food Technology Division(FTD) and was patented io October 1994. Thesolar dryers are useful for accelerated sundrying of grapes, jack fruits pulp, ginger, greenpepper, herbal medicines, etc. These dryers arewith input capacities of 25,50,75 and 100kg.

The technology transfer ceremony wasattended by Mr A. K. Anand, Director,TC&IRG; Dr Paul Thomas, Head, FTD;Mr K.K.V. Nair, FTD; Mr AKKohli, TT &CD and Mr S. Nawathe, IT & CD from BARCand Mr Sudl"" Raje, Proprietor and Mr PKShilotri from Mis Chinar Enterprises. MisChinar Enterprises have paid Rs 50001- asTechnology Transfer Fee.

Triode Spuller loll Pumps; This tcchnologywas developcd by Technical Physics &Prototype Engincering DIvision (TP & PED).These pumps ;ue usee! to crcate Ultra HighVacuum tUHV) III charged particle

accelerators, surface analytical spectrometers,mass spectrometers, etc. This technology is formanufacture of 35, 70, 140 and 270 LPScapacity pumps. These pumps provide vcryclean operation and have no moving parts orpumping fluids. The operating pressure rangeis 10.3 to 10.10 torr.

Thc Technology Transfer Agreementsignmg ceremony was attended hyMr A.K. Anand, Director TC&IRG;Dr Vc. Sahni, Head, TP&PED;Mr S.R. Halbe, Mr A.N. Garud, andMr Korgaonkar, TP&PED; Mr A.K. Kohlr, and

Mr S. Nawathe, IT&CD; BARC ane!

Mr M.J. Bhidc, Proprietor and Dr AS. Bhavefrom Mis Technovac Corporation, Pune.

Mis Technovac have paid thc firstinstalmenl of Technology Transfer Fcc

(Rs 62,5001-) as per the terms and condilionsof the agrccment. The tolal transfer fee isRs 250,000/-.

A Memorandum of Understanding (MoU)has been signed between BARC and Mis NiccoCorporation Ltd., Calcutta on 24'" March 1999for "Development of Indigenous technologyfor the manufacture of radiation cross-linkedcables and heat shrinkables accessories,Mis Nicco Corporation Ltd. Is an establishedmanufacturer of variety of cables such asPUFT, XLPE, PVC & other cables and has anumber of manufacturing facilities in India.

The MoU has been signed with theobjective of achicving self sufficiency inmaterials of vital importance to the industry.

In Electro-Beam Processing of wires &cables, E-beam radiation brings polymermodification in the fonn of cross-linking insuitable insulation or sheath materials. Thisresults in improved properties for example,increased tensile strength, increased fonnstability at higher temperatures, improveddeformation resistance, reduced swellingbehaviour, increased abrasion resistance etc.Furthcr, EB processing has a number ofadvantages over conventional chemical crosslinking technology such as very high through-puts, no use of chemicals sn environment

31

Page 32: Kamala Balakrishnan - Bhabha Atomic Research Centre

friendly, simple, reliable and better qualityproduct with minimum or no start up scrap andthere will be absolutely no radioactive rcsiducs

BARC will providc technical consultan')in the area of EB curable formulations. EB

process and product dosimetry, shiclding.underbeam equipmcnt, layout for installation

and other related areas, Ind[gcnousdevelopments of this technology will be vllalfor several sectors of Indian Industry.

The technology for the manufacture ofTLD Badge Reader (TLD BRi has beentransferred on non-exclusive basis to Mis

Kaustubh Industrial Pvt. Ltd., Mumbai nn 12'"

March, 1999. The technology of TLD BadgeReader has been developed by RS&ID ofBARe. TLD Badge Reader is exclu.sivelydesigned to measure the radiation dose

absorbed on BARC make TLD Badge which IS

used for routine personnel monitoring ofradiation workers. The reader ba.sicallyprovides controlled heat to TLD disc, sensesthe instantaneous light coming out of TLD(glow curve signal) and displays the tutal

integrated light output in terms of R (Rontgen)on a panel meter. TLD-BR covers vide

disimetrie range from 10 m Rem to 1000 Rem.It features auto readout cycle and safe inter-

locking operations.

An agreement has been signed on March12[". 1999 between Bhabha Atomic ResearchCentre and Orion Electronics, Mumbai (0

Transfer Technology for "MinilMicro SteppingControl Drive and Associated Algorithms andSoftware,"

TIlLS technology is useful rn any servocontrol or c'lecteonic applICation. The

"tlve 01 [his 10 rotor

the slel'pe[ motor at micro stepsfor a norn,," stepper motor. whICh rs not Ideallysuitable for Mrni/Mrcro Slepprng. Analgorithm makes tu move slepper motor upto

1/50 of its full step wlthoot any rotor poSItionalerrors achieving the re.sulution uplO 0.036degrees in poSItIon control TechnologyTransfer covered circuit software

and detailed algollthms. can beincorporated in OEM Products

This technology has heen developed byReactor Control D[visiun uf BARC and used

successfully rn d[llcrem servo control and

eleetrolllc gearrng applications with normalstepper motors.

TT&CD guided preparation of technology

transfer documents and co-ordinaled completeTechnology Transfer procedure.

........~- --.......

BARC SCIENTIST HONOURED

Dr V.K. Madan of Electronics Divisionhas been appointed as an Adjunct Professor byBirla Institute of Technology and Science,Pilani. He is a recognised guide for M.S. andPh,D, degrees from BITS,

R, 8alakrishnan, Head, Library & Information Services Division,Mumbai 400 085, 'Editorial Assistance, Mr V, L Kalyane

IFor Private Circulation)