原子能科学技术2025，Vol.59Issue(10)：2222-2232,11.DOI:10.7538/yzk.2024.youxian.0958
气冷快堆核数据敏感性与不确定性研究
Research on Sensitivity and Uncertainty of Nuclear Data for Gas-cooled Fast Reactor
摘要
Abstract
Nuclear data as a fundamental input for reactor physics calculations,its sensitivities and uncertainties significantly impact core simulation accuracy.At present,some research results have been achieved in the research on the sensitivities and uncertainties of high-temperature gas-cooled reactor(HTR)in China,these research results mainly illustrated the need to pay special attention to the uncertainty caused by the elastic scattering cross-section of graphite in HTR.Gas-cooled Fast Reactor(GFR)usually use He and CO2 as coolants,and almost no moderators,this is different from HTR.Furthermore,there has been no systematic work on GFR in China.It is necessary to conduct sensitivity and uncertainty research on GFR.In this paper,GFR such as ALLEGRO and GFR2400 were used as research objects.The sensitivity of keff to key nuclides such as Pu,U,Re,and W in ALLEGRO was calculated using the RMC code and the MCNP code respectively.Comparing the sensitivity calculation results of different programs,it is found that the relative deviations of the sensitivities of most nuclide-reactions calculated by RMC and MCNP are very small,but for the sensitivity of elastic scattering of some nuclides,the calculated results of the two codes are significantly different.Therefore,for nuclides with high sensitivity to elastic scattering cross-section,such as 238U(the relative deviation is-184.73%),239Pu(the relative deviation is-20.60%)and 240Pu(the relative deviation is-50.32%),the sensitivities were re-performed using the direct perturbation method.The sensitivity calculations using the direct perturbation method show that the calculation results of MCNP are more accurate.The calculation method of RMC to calculate the sensitivity of elastic scattering cross-sections in GFR may need to be further improved,which verifies the sensitivity calculation ability of RMC in GFR.The RMC was used to calculate the sensitivities and uncertainties of key nuclides such as Pu,U,Re,and W in GFR2400,and compared with the results in the public literature.It is found that due to the differences in models,the sensitivity calculation results of some nuclides-reaction have significant deviations,but the uncertainty calculation results are in good agreement,which verifies the uncertainty calculation ability of the RMC in GFR.The results of this paper verify the application of the RMC in calculating nuclear data sensitivity and uncertainty,and can provide support for GFR design and nuclear data research.关键词
气冷快堆/敏感性/不确定性/RMC程序Key words
gas-cooled fast reactor/sensitivity/uncertainty/RMC code分类
能源科技引用本文复制引用
张梦森,刘仕倡,周亚婧,张乐瑞,卢迪,王连杰..气冷快堆核数据敏感性与不确定性研究[J].原子能科学技术,2025,59(10):2222-2232,11.基金项目
国家自然科学基金(U2330117,12175067) （U2330117,12175067）
北京市科技新星计划(20240484596) （20240484596）
中央高校基本科研业务费专项资金(2024MS046) （2024MS046）
