Author/Authors :
R.K.Sinha، نويسنده , , A.Kakodkar، نويسنده ,
Abstract :
Indiahaschalkedoutanuclearpowerprogrambasedonitsdomesticresourcepositionofuraniumandthorium.ThefirststagestartedwithsettingupthePressurizedHeavyWaterReactors(PHWR)basedonnaturaluraniumandpressuretubetechnology.Inthesecondphase,thefissilematerialbasewillbemultipliedinFastBreederReactorsusingtheplutoniumobtainedfromthePHWRs.ConsideringthelargethoriumreservesinIndia,thefuturenuclearpowerprogramwillbebasedonthorium–233Ufuelcycle.However,thereisaneedforthetimelydevelopmentofthorium-basedtechnologiesfortheentirefuelcycle.TheAdvancedHeavyWaterReactor(AHWR)hasbeendesignedtofulfillthisneed.TheAHWRisa300MWe,vertical,pressuretubetype,heavywatermoderated,boilinglightwatercoolednaturalcirculationreactor.Thefuelconsistsof(Th–Pu)O2and(Th–233U)O2pins.Thefuelclusterisdesignedtogeneratemaximumenergyoutof233U,whichisbredinsitufromthoriumandhasaslightlynegativevoidcoefficientofreactivity.FortheAHWR,thewell-provenpressuretubetechnologyhasbeenadoptedandmanypassivesafetyfeatures,consistentwiththeinternationaltrend,havebeenincorporated.Adistinguishingfeaturewhichmakesthisreactorunique,fromotherconventionalnuclearpowerreactorsisthefactthatitisdesignedtoremovecoreheatbynaturalcirculation,undernormaloperatingconditions,eliminatingtheneedofpumps.Inadditiontothispassivefeature,severalinnovativepassivesafetysystemshavebeenincorporatedinthedesign,fordecayheatremovalundershutdownconditionandmitigationofpostulatedaccidentconditions.ThedesignofthereactorhasprogressivelyundergonemodificationsandimprovementsbasedonthefeedbacksfromtheanalyticalandtheexperimentalR&D.ThispapergivesthedetailsofthecurrentdesignoftheAHWR.
