摘要
高温气冷堆包覆燃料颗粒的包覆层是阻止放射性裂变产物释放的第一道屏障。本文在简介ＦＲＥＳＣＯ 模型的基础上， 采用ＦＲＥＳＣＯ２ 程序， 计算了１３７Ｃｓ、９０Ｓｒ、１１０ｍＡｇ 从包覆颗粒和燃料元件的释放份额， 分析比较了包覆层和石墨基体对这几种核素的滞留性能， 肯定了ＴＲＩＳＯ 包覆层对金属裂变产物的滞留作用。
The coated layer of fuel particle for high temperature gas cooled reactor (HTGR) is primary barrier for the release of fission products On the basis of FRESCO model,fractional releases of 137 Cs, 90 Sr and 110m Ag from coated partrele and fuel element are calculated with FRESCO2 program The retaining performance of coated layers and graphite matrix for these nuclides are analyzed and compared with each other The importance of TRISO coated layers is emphasized
出处
《核动力工程》
EI
CAS
CSCD
北大核心
1999年第5期440-443,共4页
Nuclear Power Engineering
关键词
高温气冷堆
燃料元件
包覆颗粒
裂变产物
滞留性能
High temperature gas cooled reactor Fuel element Coated particle Fission product Retaining performance
