MCNP-ORIGEN耦合通用程序(MOCUP)的基准验证与实用化

本文的目的是将MOCUP程序实用化，以用于燃耗分析。选取了2个资料完整的基准问题以验证MOCUP程序本身和应用方法。一个基准题是压水堆的栅元燃耗问题(含3种状况)；另一个是快堆的燃耗问题。适当选取程序的有关参数后．将MOCUP的计算结果同实验结果和／或其它程序计算结果相比较．可得如下结论：①除极个别特例外，MOCUP程序计算得到的同位素成分结果处于其它程序计算结果的范围之内；②与实验测量数据相比。MOCUF程序计算得到的锕系元素浓度的误差均小于11％，绝大多数小于5％；裂变产物浓度的误差小于10％，除^149Sm之外；③MOCUP程序计算得到的反应性随燃耗变化的结果与所报告的其它结果吻合很好。

Validation of the MCNP-ORIGEN Coupled Utility Program (MOCUP)

The purpose of this work was to validate the MOCUP program for burn-up analysis. Two well-documented benchmarking problems were used to validate MOCUP itself and the application way. One benchmark consists of three PWR pin-cell burn-up cases. The other benchmark is a fast reactor (burner) burn-up problem. From the comparisons of our MOCUP results by using appropriate program parameters with those obtained from measurement and/or other computer codes, it has been concluded that: (a) with few exceptions, the MOCUP results of isotopic compositions fall within the range of those calculated by different codes; (b) MOCUP results for the actinide concentration are in agreement with the measurement values to within 11% (for most of the actinides, the deviations are less than 5%) and for all fission products studied, the deviations are less than 10%, except for 149Sm; and (c) the MOCUP predictions of reactivity change with burn-up are in good agreement with the reported values.