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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。
Due to the accelerator-driven sub-critical heap existence of neutron sources, complex core structure and serious anisotropy of neutron fluence, the related fuel consumption calculation plays an important role in the design of subcritical system. In order to realize the burnup calculation of subcritical system, an MCADS-coupled MCNP and LITAC interface program was developed based on the comprehensive characterization of LITAC-treated radionuclides by particle transport program MCNP. Then we choose the IAEA-ADS benchmark to verify the coupling program. The results show that the calculated results of fuel consumption, external strength, cavitation effect and initial power distribution are in good agreement with those of other countries. The reliability of MCADS in sub-critical mode calculation is confirmed.