CAJ | 학술논문

本文介绍了开发的蒙特卡罗燃耗计算程序MCNTRANS。MCNTRANS的中子学计算参数直接采用MCNP5程序的反应率计算值，燃耗计算方法采用图论算法跟踪燃耗链，同时，对实际燃耗过程进行详细分析以提高计算精度与程序适用性，并使用预估-校正方法以获取较大的燃耗计算步长。程序计算结果通过OECD/NEA与JAERI燃耗基准题实验结果进行验证，并与其他程序的计算结果进行比较。结果表明，MCNTRANS程序在不同燃耗深度下的计算结果和实验值与其他程序的计算值符合较好，部分锕系核素与裂变产物的计算精度更高。
본문개소료개발적몽특잡라연모계산정서MCNTRANS。MCNTRANS적중자학계산삼수직접채용MCNP5정서적반응솔계산치，연모계산방법채용도론산법근종연모련，동시，대실제연모과정진행상세분석이제고계산정도여정서괄용성，병사용예고-교정방법이획취교대적연모계산보장。정서계산결과통과OECD/NEA여JAERI연모기준제실험결과진행험증，병여기타정서적계산결과진행비교。결과표명，MCNTRANS정서재불동연모심도하적계산결과화실험치여기타정서적계산치부합교호，부분아계핵소여렬변산물적계산정도경고。
A new nuclear fuel burnup calculation code MCNTRANS based on MCNP was introduced in this paper .The neutronics calculation parameter was extracted from the MCNP5 reaction rate tally result ,while a graph theory algorithm was implemented to track the burnup chain and the analytic solution of the Bateman equation was given . At the same time ,the detailed physical process was considered to improve the accuracy and serviceability of this code ,and prediction-correction method was used to allow a large burnup step .The OECD/NEA and JAERI pin cell benchmark problems were used to validate the code MCNTRANS while a reference result was given by other code .It can be concluded that the calculation results of MCNTRANS are generally consistent with the experimental result and that of the other burnup codes , and part of the actinides and fission products calculation result show better accuracy .