摘要:
由于加速器驱动次临界堆存在外中子源，堆芯结构复杂，中子注量的各向异性严重，所以相关燃耗计算在次临界系统设计中起着重要作用。为实现次临界系统的燃耗计算，结合粒子输运程序MCNP 处理复杂几何和燃耗程序LITAC 处理核素全面的特点，开发了接口程序MCADS耦合MCNP 和LITAC。然后选取IAEA-ADS 基准题对耦合程序进行了验证计算。结果表明，燃耗、外源强度、空泡效应、初始功率分布等方面的计算结果和其他国家的计算结果相比有很好的一致性，证实了MCADS在次临界模式计算中的可靠性。Burnup analysis plays an important role in the design of ADS since subcritical reactor has complex geometry structure as well as anisotropic ux distribution caused by external source. In order to simulate burnup, a Monte-Carlo Activation and Depletion Code System (MCADS) has been developed combining advantages of MCNP in complex geometry neutron transport calculation with LITAC in fast and precise inventory calculation. Then, IAEA ADS-Benchmark (stage1) is worked out, verifying that the code can be used to deal with subcritical reactor with an external source. Also, burnup, source evolution, void reactivity, initial spatial power density distribution are gured out with the code, showing good agreement with results from other countries.
Abstract:
Burnup analysis plays an important role in the design of ADS since subcritical reactor has complex geometry structure as well as anisotropic ux distribution caused by external source. In order to simulate burnup, a Monte-Carlo Activation and Depletion Code System (MCADS) has been developed combining advantages of MCNP in complex geometry neutron transport calculation with LITAC in fast and precise inventory calculation. Then, IAEA ADS-Benchmark (stage1) is worked out, verifying that the code can be used to deal with subcritical reactor with an external source. Also, burnup, source evolution, void reactivity, initial spatial power density distribution are gured out with the code, showing good agreement with results from other countries.
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