摘要
研制开发了长春命放射性废物转化的中子学计算和分析程序系统,其中废物核燃耗计算对空间作一维近似,能量作多群近似,采用矩阵指数技术求解核密度平衡方程,并计算各种废物核的放射性、BHP和质量变化过程。利用所研制的程序系统对长寿命锕系元素在聚变-裂变混合堆中的转化进行了探索性研究。
This paper developed the neutronic computation and analysis code system for transmutation of long-lived radioactive wastes, which uses 1-D spacedependent. multi-group energy-dependent and matrix exponent technique for solution of nuclide density equilibrium equation. The neutronic computation and analysis is performed to assess the technical feasibility of transmutation of long-lived actinides using fusion-fission hybrid reactors by the above code system.
出处
《中国科学院研究生院学报》
CAS
CSCD
1995年第2期132-138,共7页
Journal of the Graduate School of the Chinese Academy of Sciences
关键词
锕系元素
转化
中子学
放射性废物
actinide, transmutation, fusion-fission hybrid reactor, neutronics