原子能科学技术2018，Vol.52Issue(2)：204-209,6.DOI:10.7538/yzk.2018.52.02.0204
基于CRAM的压水堆燃耗程序开发及验证
Development and Verification of PWR Burnup Code Based on CRAM
成昱廷 1周琦 1朱庆福 1于超2
作者信息
- 1. 中国原子能科学研究院 反应堆工程技术研究部,北京 102413
- 2. 中广核研究院有限公司,广东 深圳 518031
- 折叠
摘要
Abstract
A burnup calculation code MCRAM based on the Cinder90 burnup database was developed in this paper.The reaction cross sections of some important actinides and fission products were modified by coupling with the MCNP code.The OECD/NEA Takahama-3 PWR fuel assembly benchmark problem was used to validate the MCRAM code while a reference result was given by other codes.The results show that the rela-tive deviation of MCRAM code calculation results for important fission products and ma-jor actinides is less than 5%.The precision of MCRAM code reaches an equivalent level of ORIGEN2 code.Meanwhile,the calculation efficiency of MCRAM code is nearly 200 times faster than MCNTRANS code while calculating the same case.关键词
燃耗方程/切比雪夫有理近似方法/燃耗计算Key words
burnup matrix/Chebyshev rational approximation method/burnup calcula-tion分类
能源科技引用本文复制引用
成昱廷,周琦,朱庆福,于超..基于CRAM的压水堆燃耗程序开发及验证[J].原子能科学技术,2018,52(2):204-209,6.
