摘要:
为了验证SuperMC软件系统对装载MOX燃料压水堆的临界计算能力,采用国际经合组织核能署(OECD/NEA) 2001年发布的三维VENUS-Ⅱ国际基准模型对SuperMC3.1版本进行了测试验证.本次测试包括栅元和堆芯两个部分,分别计算了栅元无限增殖因数、重核反应率、堆芯有效增殖因数、堆芯轴向裂变反应率等关键物理参数.将SuperMC计算结果与基准模型实验测量值以及MCNP计算值作了对比.结果显示:在测试范围内,SuperMC计算值与参考值吻合得较好,表明SuperMC可应用于含MOX燃料堆芯的临界计算.
Abstract:
Super Monte Carlo Program for Nuclear and Radiation Simulation (SuperMC),a general,intelligent,accurate and precise simulation software system for the design and safety evaluation of nuclear systems,is developed by FDS team of key laboratory of neutronics and radiation safety.In order to validate the accuracy of SuperMC in calculating MOX-fueled system,it was benchmarked with the VENUS-Ⅱ MOX-fueled core model released by OECD/NEA.Both cell and core calculations were performed.A series of key parameters of cell infinite multiplication factor,reaction rates per heavy isotope,core effective multiplication factor,and axial fission rate distribution of six fuel pins were calculated.The computational results are compared with measured data and the MCNP calculated results,showing that the SuperMC results agree well with the experimental results and the MCNP calculated results.The correctness and reliability of SuperMC calculating neutron transport in MOX-fuelled system are preliminarily verified.
首页
登录
注册
下载: