作者机构：
[赵鹏程; 刘紫静; 李捷; 于涛] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment, University of South China, Hengyang
作者机构：
[赵鹏程; 余红星; 夏榜样; 陈宝文] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China;[衣峰; 王天石] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[石巍] Department of Engineering and Applied Physics, University of Science and Technology of China, Hefei
作者机构：
[邓声文; 朱恩平; 赵鹏程; Zhai, Pengdi; 刘紫静; 余清远] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment, University of South China, Hengyang;[邓声文; 朱恩平; 赵鹏程; Zhai, Pengdi; 刘紫静; 余清远] 421001, China;[赵鹏程] 421001, China<&wdkj&>Cooperative Innovation Center for Nuclear Fuel Cycle Technology & Equipment, University of South China, Hengyang
通讯机构：
[Tao Yu] S;School of Nuclear Science and Technology, University of South China, Hengyang 421001, China<&wdkj&>Hunan Engineering&Technology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang 421001, China
摘要：
There is an inevitable uncertainty in the coupled neutronic/thermal-hydraulic calculations, which are used for simulating the performance of nuclear reactors, due to the influence of design parameters and initial conditions. The application of uncertainty analysis methods in such calculations can reduce the "uncertainty zone" of calculation results as well as the unnecessary safety margin of the reactor. In this study, based on the combination of user-defined function (UDF) of FLUENT, a computational fluid dynamics (CFD) code, with the neutron dynamics model, fuel pin heat transfer model, and SIMLAB software, an uncertainty analysis platform called CFD/PFS is developed. The CFD/PFS platform is used to simulate the unprotected transient overpower (UTOP) accident in the small modular natural circulation lead-bismuth alloy cooled fast reactor-10MWth (SNCLFR-10) reactor, which is followed by uncertainty quantification. The results of uncertainty and sensitivity analysis justify the good reliability and accuracy of coupled neutronic/thermal-hydraulic calculations. The titular values of transient parameters, such as peak reactivity and peak fuel temperature, are within the bilateral tolerance limits, and the relative deviation between these values and the limit values is less than 3.95%. As far as UTOP accident, Doppler coefficient is found to be the main source of uncertainty, which has the most significant effect on reactor safety. (C) 2021 Elsevier Ltd. All rights reserved.
作者机构：
[陈宝文; 邓坚] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China;[凌煜凡; 胡宝珑; 王天石; 朱恩平; 王婷] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[陈宝文; 邓坚] 610213, China
作者机构：
[苑旭东; 马辉强; 陈珍平; 郭树伟; 谢金森; 杨超; 于涛] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang;[苑旭东; 马辉强; 陈珍平; 郭树伟; 谢金森; 杨超; 于涛] 421001, China<&wdkj&>Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, Hengyang;[苑旭东; 马辉强; 陈珍平; 郭树伟; 谢金森; 杨超; 于涛] 421001, China
作者机构：
[徐士坤; 于涛; 谢金森; 姚磊] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Hunan Engineering & Technology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang;[李满仓; 夏羿] Nuclear Power Institute of China, Chengdu;610213, China
作者机构：
[杨超; 于涛] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[邓力; 程汤培] CAEP Software Center for High Performance Numerical Simulation, Beijing;100094, China;[杨超; 于涛] 421001, China
作者机构：
[雷济充; 谢金森; 于涛; 陈珍平; 赵鹏程; 谢超; 倪梓宁] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Virtual Simulation Experiment Teaching Center on Nuclear Energy and Technology, University of South China, Hengyang;[周剑东] Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai;200000, China
作者：
Wan Shun-kuan;Lu Bo;Zhang Hong-ming*;He Liang;Fu Jia;...
期刊：
光谱学与光谱分析,2021年41(10):3111-3116 ISSN：1000-0593
通讯作者：
Zhang Hong-ming
作者机构：
[Lu Bo; Fu Jia; Wan Shun-kuan; Wang Fu-di; Zhang Hong-ming; Li Yi-chao; Bin Bin; He Liang] Chinese Acad Sci, Inst Plasma Phys, Hefei Inst Phys Sci, Hefei 230031, Peoples R China.;[Wan Shun-kuan; Li Yi-chao] Univ Sci & Technol China, Hefei 230026, Peoples R China.;[Ji Hua-jian] Univ South China, Sch Nucl Sci & Technol, Hengyang 421001, Peoples R China.
作者机构：
[赵鹏程; 余红星; 夏榜样; 陈宝文] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China;[朱恩平; Zhai, Pengdi; 邓声文] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;Cooperative Innovation Center for Nuclear Fuel Cycle Technology and Equipment, University of South China, Hengyang
作者机构：
[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] Hunan;[姜庆丰; Zeng, Wenjie; 于涛; 谢金森; 陈乐至] 421001, China
作者机构：
[姜庆丰; Zeng, Wenjie] School of Nuclear Science and Technology, University of South China, Hengyang;421001, China;[姜庆丰; Zeng, Wenjie] 421001, China
通讯机构：
School of Nuclear Science and Technology, University of South China, Hengyang, China
作者机构：
[于涛; 刘金聚; 谢金森; 谢芹; 陈珍平; 赵鹏程; 刘紫静; Zeng, Wenjie; 徐士坤] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;Hunan Engineering andTechnology Research Center for Virtual Nuclear Reactor, University of South China, Hengyang;[于涛; 刘金聚; 谢金森; 谢芹; 陈珍平; 赵鹏程; 刘紫静; Zeng, Wenjie; 徐士坤] Hunan
作者机构：
[张泽寰; 宋英明; 毛婕] School of Nuclear Science and Technology, University of South China, Hengyang;Hunan;421001, China;[卢川; 唐松乾; 肖锋; 吕焕文; 杨俊云] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu;610213, China
