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典型压水堆小破口LOCA参数重要度排序表开发
引用本文:熊青文,黄涛,苟军利,杜鹏,邓坚,袁鹏,周佳樾,胡文桢.典型压水堆小破口LOCA参数重要度排序表开发[J].原子能科学技术,2022,56(6):1188-1195.
作者姓名:熊青文  黄涛  苟军利  杜鹏  邓坚  袁鹏  周佳樾  胡文桢
作者单位:中国核动力研究设计院 核反应堆系统设计技术重点实验室,四川 成都610213;西安交通大学 核科学与技术学院,陕西 西安710049
摘    要:现象识别排序表(PIRT)是反应堆热工水力分析的重要依据,传统PIRT的建立依赖于专家经验,因此缺乏专家经验时难以开展参数的识别工作。本文开展在缺乏专家经验时确定各输入参数重要度排序的研究,选定的工况为典型三回路压水堆(PWR)小破口失水事故(SBLOCA)。参考已有的SBLOCA PIRT,并基于基准计算结果,筛选和补充了可能对目标输出(FOM)具有影响的54个不确定性输入参数。使用一种优化矩独立全局敏感性分析方法计算得到了各输入参数对FOM的敏感性度量和重要度排序。将参数的重要度排序转换为Savage分数,按照Savage分数定性地将所有输入参数进行重要度分组,从而得到了SBLOCA的参数重要度排序表,为压水堆SBLOCA工况的参数排序提供了参考。

关 键 词:敏感性分析    参数重要度    小破口失水事故    现象识别排序表

Development of Parameter Importance Ranking Table for Typical PWR Small Break LOCA
XIONG Qingwen,HUANG Tao,GOU Junli,DU Peng,DENG Jian,YUAN Peng,ZHOU Jiayue,HU Wenzhen.Development of Parameter Importance Ranking Table for Typical PWR Small Break LOCA[J].Atomic Energy Science and Technology,2022,56(6):1188-1195.
Authors:XIONG Qingwen  HUANG Tao  GOU Junli  DU Peng  DENG Jian  YUAN Peng  ZHOU Jiayue  HU Wenzhen
Affiliation:Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610213, China;School of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
Abstract:The phenomenon identification and ranking table (PIRT) is an important basis for nuclear reactor thermal-hydraulic analysis, and it is mainly used in the construction of the code assessment matrix as well as the identification of important input parameters in the best estimate plus uncertainty (BEPU) analysis. It would be difficult to perform the parameter identification process when lacking of expert experience since the development of the PIRT relies heavily on relevant expert experience. One way to decrease to reliance on expert experience in the phenomenon identification and ranking process is to use the quantitative sensitivity analysis technique, such as the Sobol or the moment-independent method. In this paper, the research on determining the parameter importance rankings in short of expert experience was carried out by using an efficient moment-independent global sensitivity analysis method. Since the small break loss of coolant accident (SBLOCA) scenario is an important case in the safety assessment of the nuclear power plant, it was adopted as the scenario of interest in the research. Therefore, the target scenario was determined to be the SBLOCA in a typical three-loop pressurized water reactor (PWR), and five different break sizes were analyzed. Firstly, the nominal cases were simulated to analyze the accident phases as well as potential thermal-hydraulic phenomena. Then, the figure of merit (FOM) was determined to be the minimum collapsed level (MCL) in the active core section. A total of 54 uncertain input parameters with potential influence on the FOM were then screened and added by referring to some PIRTs and by analyzing the base case calculation. And then, the efficient moment-independent global sensitivity analysis method was utilized to calculate the sensitivity measure of each input on the FOM. The importance rankings of the inputs were then transferred into the Savage scores and the inputs can be grouped qualitatively based on the Savage scores. The results show that there are two phases where the collapsed level deceases significantly, namely the blowdown phase and the loop seal and clearing phase. The parameters that have significant influences on the MCL during the blowdown phase are mainly the initial power, the initial primary pressure, the critical flow model, and the flow resistance in the primary loop. In the loop seal and clearing phase, the core level drop is also related to the core boiling, so the interfacial friction model, various heat transfer models and the auxiliary feedwater system delay also have large influences on the MCL. Finally, a parameter importance ranking table of the SBLOCA scenario was obtained, which can provide guidance for similar cases.
Keywords:sensitivity analysis                                                                                                                        parameter importance                                                                                                                        small break loss of coolant accident                                                                                                                        phenomenon identification and ranking table
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