【摘要】 燃耗计算在反应堆设计、分析研究中起着重要作用。一维、二维耦合燃耗程序因其几何限制难以满足先进反应堆精细设计分析的要求。本文研发了基于蒙特卡罗方法与指数欧拉法耦合的三维燃耗程序。程序采用编写耦合MCNP与FISPACT的接口程序的方法,结合了MCNP处理复杂几何能力强,FISPACT计算核素全面、能谱多样的特点,实现了考虑燃耗自屏效应的各种复杂能谱的燃耗计算。采用IAEA基准校核例题测试的结果符合各国计算趋势,证明了程序的正确性。更多还原

【Abstract】 Burnup analysis plays a key role in fuel breeding,transmutation and post-processing in nuclear reactor.Burnup codes based on one-dimensional and two-dimensional transport method have difficulties in meeting the accuracy requirements.A three-dimensional burnup analysis code based on Monte Carlo method and Exponential Euler method has been developed.The coupling code combines advantage of Monte Carlo method in complex geometry neutron transport calculation and FISPACT in fast and precise inventory calculation,meanwhile resonance Self-shielding effect in inventory calculation can also be considered.The IAEA benchmark text problem has been adopted for code validation.Good agreements were shown in the comparison with other participants’ results.更多还原