三维六角形组件压水堆堆芯燃料管理计算及程序系统研究

介绍所研制的WWER型压水堆堆芯燃料管理计算程序系统TPFAP-H／CSIM-H，六角形组件均匀化计算程序TPFAP-H是在压水堆正方形组件程序TPFAP的基础上，采用穿透概率法与响应矩阵方法相结合计算六角形组件内中子能谱分布，并考虑六角形栅元特点改造开发而成的CSIM-H是以先进六角形节块扩散程序为基础．参照SIMULATE程序功能而研制的物理-热工水力耦合的三维六角形节块PWR堆芯燃料管理程序两者通过接口程序LINK连接起来，可以考虑燃耗，功率、慢化剂密度变化．控制棒、氙等参数的多种反馈效应对IAEA的WWER-1000型Kalinin核电厂基准问题的校算的结果表明，临界硼浓度、功率和燃耗分布等结果与国际各研究机构的结果吻合良好，偏差均在工程要求之内。

Development of the Method and Code System for Three Dimension Hexagonal PWR Core Fuel Management Calculation

The calculation method of three dimensional Hexagonal PWR core fuel management and an integrated code system TPFAP-HEX/CSIM-H possessing engineering practical value have been developed in this paper. The transmission probability method combining with the respond matrix method is adopted to calculate the neutron flux distribution in the hexagonal assembly, and is used to modify and reform the PWR quadrate assembly code TPFAP to the TPFAP-H with the capability of hexagonal assembly calculation, and keeping all the original functions of TPFAP. Based on the advanced 3D hexagonal diffusion nodal code SIXTUS-3, the hexagonal PWR core fuel management code CSIM-H is developed. Both codes have been linked together to form the integrated code system TPFAP-HEX/CSIM-H, which considers the all feedbacks of burnup, power distribution, moderator density, control rod insertion, and etc. The verification and validation of proposed model and code system has been examined by the calculation of benchmark problem of IAEA WWER-1000 PWR reactor in Kalinin NPP. The numerical results are in good agreement with those of other international institutes. The errors of critical boron concentration and power distribution all are within the permissible limits of engineering requirement.