233UBreeding in Accelerator driven Sub critical Fast Reactor

被引：0
|
作者：
杨永伟
安宇
机构：
来源：
TsinghuaScienceandTechnology | 1999年 / 04期
关键词：
fuelbreeding; accelerator; sub critical; breedingreactor;
D O I：
暂无
中图分类号：
TL37 [反应堆设计、建造、安装、实验与测量];
学科分类号：
082701 ;
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.
引用
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页码：1638 / 1641
页数：4
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