原子能科学技术Issue(5)：893-897,5.DOI:10.7538/yzk.2014.48.05.0893
退役反应堆放射性活化源项计算
Calculation of Radioactive Activated Source Term for Decommissioned Reactor
摘要
Abstract
The calculation model of radioactive activated source term for decommissioned reactor was set up ,and the validity of the model was verified by critical calculation .The significance of layering calculation and stepping calculation for the area far from the reactor core was analyzed by MCNP code .Using the combination of MCNP and ORIGEN codes ,the specific activities of 60 Co of reactor core components ,such as the reactor sup-port skirt ,the samples of the inner and outer steel plates of the lead support barrel and the pre-installed sample on the outer part of the primary water barrel ,were calculated specifically .The deviation between the calculation value and measurement value meets the engineering design requirements ,and this show s that the model and the calculation method for calculating the radioactive activated source term for such a decommissioned reactor are adequate .关键词
源项/临界计算/深穿透/分步计算/60 Co比活度Key words
source term/critical calculation/deep penetration/stepping calculation/specific activity of 60 Co分类
能源科技引用本文复制引用
王小胡,胡一非,李江波,李全伟..退役反应堆放射性活化源项计算[J].原子能科学技术,2014,(5):893-897,5.基金项目
核废物与环境安全国防重点学科实验室（西南科技大学）开放基金资助项目 （）
