Neutronic Calculation Analysis for CN HCCB TBM-Set  

作　　者：曹启祥 赵奉超 赵周 武兴华 栗再新 王晓宇 冯开明 

机构地区：[1]Southwestern Institute of Physics

出　　处：《Plasma Science and Technology》2015年第7期607-611,共5页等离子体科学和技术（英文版）

基　　金：supported by the Major State Basic Research Development Program of China(973 Program)(No.2013GB108000)

摘　　要：Using the Monte Carlo transport code MCNP, neutronic calculation analysis for China helium cooled ceramic breeder test blanket module （CN HCCB TBM） and the associated shield block （together called TBM-set） has been carried out based on the latest design of HCCB TBM-set and C-lite model. Key nuclear responses of HCCB TBM-set, such as the neutron flux, tritium production rate, nuclear heating and radiation damage, have been obtained and discussed. These nuclear performance data can be used as the basic input data for other analyses of HCCB TBM-set, such as thermal-hydraulics~ thermal-mechanics and safety analysis.Using the Monte Carlo transport code MCNP, neutronic calculation analysis for China helium cooled ceramic breeder test blanket module （CN HCCB TBM） and the associated shield block （together called TBM-set） has been carried out based on the latest design of HCCB TBM-set and C-lite model. Key nuclear responses of HCCB TBM-set, such as the neutron flux, tritium production rate, nuclear heating and radiation damage, have been obtained and discussed. These nuclear performance data can be used as the basic input data for other analyses of HCCB TBM-set, such as thermal-hydraulics~ thermal-mechanics and safety analysis.

关 键 词：MCNP HCCB TBM-set neutronic calculation nuclear performance 

分 类 号：O571.5[理学—粒子物理与原子核物理]