^(233)UBreeding in Accelerator driven Sub critical Fast Reactor

^(233)UBreedingin Accelerator driven Sub critical Fast Reactor

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摘要 Accelerator driven Sub critical Fast Reactor (ADFR) is chosen as fissile material breeding reactor. (U Pu)Oxischosen asfuelinthe core and ThO2 asfertile materialinthe blanketzoneto breed 233U.Moltenleadis chosen as coolant because ofits better neutronic and chemicalcharacteristics over sodium .The program system usedforneutronicsstudy consists of:LAHET,forthe simulation oftheinteraction between the proton with medium energy andthe nuclei ofthe target;MCNP4A,forthe simulation ofneutrontransport with energy below 20 MeVin the sub criticalreactor;CONNECT1 ,forthe processing ofsometallies provided bythe outputof MCNP4Ain order to prepare micro cross sectionsfor elements used for burnup calculation;ORIGEN2 ,used for multi region burnup calculation;CONNECT2 ,forthe processing ofatom densities ofsome elements providedinthe outputof ORIGEN2 in orderto prepare inputto LAHETcalculationfor nexttime step.The calculated results show thatthe proposed caseisfeasible for breedingfissile materialconsideringthe criticality safety,power density,burnup,etc. Accelerator driven Sub critical Fast Reactor (ADFR) is chosen as fissile material breeding reactor. (U Pu)Oxischosen asfuelinthe core and ThO2 asfertile materialinthe blanketzoneto breed 233U.Moltenleadis chosen as coolant because ofits better neutronic and chemicalcharacteristics over sodium .The program system usedforneutronicsstudy consists of:LAHET,forthe simulation oftheinteraction between the proton with medium energy andthe nuclei ofthe target;MCNP4A,forthe simulation ofneutrontransport with energy below 20 MeVin the sub criticalreactor;CONNECT1 ,forthe processing ofsometallies provided bythe outputof MCNP4Ain order to prepare micro cross sectionsfor elements used for burnup calculation;ORIGEN2 ,used for multi region burnup calculation;CONNECT2 ,forthe processing ofatom densities ofsome elements providedinthe outputof ORIGEN2 in orderto prepare inputto LAHETcalculationfor nexttime step.The calculated results show thatthe proposed caseisfeasible for breedingfissile materialconsideringthe criticality safety,power density,burnup,etc.

作者杨永伟安宇

出处《Tsinghua Science and Technology》 SCIE EI CAS 1999年第4期1638-1641,共4页 清华大学学报（自然科学版（英文版）

关键词 fuelbreeding ACCELERATOR sub critical breedingreactor fuelbreeding accelerator sub critical breedingreactor

分类号 TL37 [核科学技术—核技术及应用]

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Tsinghua Science and Technology

1999年第4期

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^(233)UBreeding in Accelerator driven Sub critical Fast Reactor

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