期刊论文

Zhao, P.

中文

核技术

0253-3219

2022

45

8

89-98

10.11889/j.0253-3219.2022.hjs.45.080604

国家自然科学基金(No.1 1905101 )、国家级大学生创新与实验研究计划(No.S202010555037)资助 第一作者：余清远，男，2000年出生，现为硕士研究生，研究领域为快堆热工水力、热管冷却反应堆 通信作者：赵鹏程，E-mail：zhaopengcheng1030@163.com 收稿日期：2022-01-26，修回日期：2022-05-27 Supported by National Natural Science Foundation of China (No.1 1905101 ), National University Student Innovation Program (No.S202010555037) Firstauthor:YUQingyuan,male,bornin2000, masterstudent,focusingonfastreactorthermalhydraulicandheatpipecoolingreactor Corresponding author: ZHAO Pengcheng, E-mail: zhaopengcheng1030@163.com Received date: 2022-01-26, revised date: 2022-05-27

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典型瞬态事故对铅铋快堆安全运行具有极大挑战,将不确定性量化分析方法应用于瞬态事故计算,可降低瞬态安全参数的“不确定带”,更精确地评估反应堆安全特性。基于自主开发的快堆分析程序CFD/PFS,采用非参数统计法开展了小型自然循环铅铋快堆无保护超功率事故(Unprotected Transient Overpower,UTOP)的不确定性分析。首先,通过文献资料以及工程经验判断,考虑了三类不确定性输入参数:热工水力模型参数、中子物理模型参数以及燃料制造公差;然后,采用拉丁超立方对输入参数进行抽样,对瞬态安全参数进行不确定性量化分析,并通过相关系数分析法评估输入参数对瞬态安全参数的敏感度。分析结果表明:包壳、...

[Background] Typical transient accidents pose a great challenge to the safe operation of lead-bismuth fast reactors. [Purpose] This study aims to apply uncertainty analysis methods to transient calculations to reduce the "uncertainty band" of transient parameters and obtain more accurately assess reactor safety characteristics. [Method] Based on the self-developed fast reactor analysis CFD/PFS code, non-parametric statistical methods was employed to carry out the uncertainty analysis of the unprotected overpower accident (UTOP) of small natural...