Volume 13: Risk Assessments and Management最新文献_第4页

The Research on the Risk Monitor With Specific Plant Configuration at Shutdown Mode for VVER Nuclear Reactor VVER核反应堆停堆模式下特殊机组配置风险监测研究

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-91663

Fangyu Dong, Jinyan Du, Chao Ma, W. Deng, Qingqing Xu, Rui Zhang

引用次数: 0

Probabilistic Safety Assessment of Newly Added Auxiliary Transformers In Fangjiashan Nuclear Power Plant 方家山核电站新增辅助变压器的概率安全评价

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-89071

Shengjia Zou, Jian Wu, Yong Cao, Zilong Wang, Yang Luo, Mingsha Zhao, Deyi Liu, Honghao Chen

{"title":"Probabilistic Safety Assessment of Newly Added Auxiliary Transformers In Fangjiashan Nuclear Power Plant","authors":"Shengjia Zou, Jian Wu, Yong Cao, Zilong Wang, Yang Luo, Mingsha Zhao, Deyi Liu, Honghao Chen","doi":"10.1115/icone29-89071","DOIUrl":"https://doi.org/10.1115/icone29-89071","url":null,"abstract":"\u0000 In order to further improve the safety of the nuclear power plant, China nuclear power Fangjiashan nuclear power plant plans to add an auxiliary standby transformer, which is used for the redundancy of the original auxiliary transformer. This permanent change will improve the reliability of external power supply of nuclear power plant and reduce the frequency of loss of external power supply, so as to improve the safety level of Fangjiashan nuclear power plant. In this paper, the probabilistic safety assessment method is applied to analyze Fangjiashan unit, and the level-1 PSA model of internal events under power operation conditions, level-1 PSA model of internal events under low power and shutdown conditions and spent fuel pool model are modeled respectively. After the permanent change of auxiliary standby transformer is added during Fangjiashan power operation, low power and shutdown, The quantitative safety analysis results are given for the improvement of safety and reliability of Fangjiashan nuclear power plant. This evaluation provides an idea for the application of PSA in the permanent change of nuclear power plant. Before the permanent change of power plant plan, through the analysis of probabilistic safety evaluation, we can get how much benefit this change brings to the nuclear safety of power plant.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"7 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130332937","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants 核电站重负荷下降风险评估研究

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-89056

Chao Ma, Yiming Wang, C. Feng, Jian Yang

{"title":"Research on Risk Assessment of Heavy Load Drops in Nuclear Power Plants","authors":"Chao Ma, Yiming Wang, C. Feng, Jian Yang","doi":"10.1115/icone29-89056","DOIUrl":"https://doi.org/10.1115/icone29-89056","url":null,"abstract":"\u0000 After years of development, probabilistic safety assessment has become a tool for the evaluation and optimization of the design and operation of nuclear power plants, and the analysis scope has also developed from internal events to internal hazards and external hazards. In the assessment of internal and external hazards, the probabilistic safety assessment of internal fire, internal flooding and seismic has been fully studied, and a systematic analysis method has been formed, which is used to support the design and operation of nuclear power plants. The drop of heavy load is one of the internal hazards of nuclear power plants. At present, there is no systematic method how to quantitatively evaluate the risks to nuclear power plants. This paper refers to the analysis requirements of IAEA, NEI and other institutions on the analysis of heavy load drop, and combines the design characteristics and operating experience of the power plant to carry out a study on the risk assessment of heavy load drop, including: analysis of the possibility of heavy load drop, analysis of the impact of heavy load drop, CDF levels caused by heavy load drop, etc. Through the research in this paper, it is expected to provide insights into the risk of heavy load drop and provide support for subsequent risk assessment and optimization of nuclear power plants.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"84 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130444697","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Study on Social Stability Risk Assessment of Nuclear Facilities 核设施社会稳定风险评估研究

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-91907

Rongxu Zhu, Feng Zhao, Xiaofeng Zhang, Meng Zhang

引用次数: 0

Study on Methodology and Application of Seismic Level 2 Probabilistic Safety Assessment for Nuclear Power Plants 核电站地震二级概率安全评价方法及应用研究

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-93057

Hongjia Zheng

{"title":"Study on Methodology and Application of Seismic Level 2 Probabilistic Safety Assessment for Nuclear Power Plants","authors":"Hongjia Zheng","doi":"10.1115/icone29-93057","DOIUrl":"https://doi.org/10.1115/icone29-93057","url":null,"abstract":"\u0000 Many countries have paid more attention to seismic risk in nuclear power plants after the Fukushima nuclear accident. It indicates that evaluating the risk for seismic event is vitally important. Seismic Level 1 probabilistic safety assessment (PSA) has a mature methodology, but how to perform the study on seismic Level 2 PSA has become a crucial problem needed to be considered deeply by both regulators and operators. In this paper, the methodology of seismic Level 2 probabilistic safety assessment (PSA) is developed for nuclear power plants. Seismic Level 2 PSA is focused on the severe accident phenomenon, progression and source terms release to evaluate the containment response after core damage caused by seismic event. To demonstrate the effectiveness of the proposed approach, this study took a nuclear power plant under construction in China as an example. Seismic Level 2 PSA focuses on crucial elements including Level 1/ Level 2 PSA interface analysis, severe accident design features, severe accident phenomenon, containment event tree analysis, seismic fragility analysis, etc. A risk-informed seismic Level 2 PSA model is developed to evaluate large release frequency (LRF) caused by seismic event. The proposed methodology can be expected to provide an effective framework for performing the seismic Level 2 PSA and decision support to improve the nuclear power plant safety.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"22 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126786028","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant 压水堆核电站运行阶段启动事件分析

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-93295

Feng Chu-ran, Ma Yuan, Yan Lin, Yang Guansan, Liu Bin

{"title":"Initiating Events Analysis in Operating Phase for Pressurized Water Reactor Nuclear Power Plant","authors":"Feng Chu-ran, Ma Yuan, Yan Lin, Yang Guansan, Liu Bin","doi":"10.1115/icone29-93295","DOIUrl":"https://doi.org/10.1115/icone29-93295","url":null,"abstract":"\u0000 Probabilistic Safety Assessment (PSA) is an important tool for risk-informed integrated decision making application. Initiating events are caused by equipment failure or/and personnel error which causes disturbance to the nuclear power plant (NPP) and may lead to core damage. As the start of PSA, the quality of initiating events analysis has an important influence on safety assessment and PSA application for NPPs, and the application of operating experience of domestic and aboard are of great importance in initiating events analysis. Based on analysis experience of PSA model in design phase and operation phase for different NPPs, this paper developed a set of method for initiating events analysis of operation phase PSA model development. Combined with the referenced initiating events list, engineering evaluation, operating experience analysis and main logic diagram, a relatively complete initiating events list have been determined. According to the characteristics of the initiating events and analysis requirements for PSA applications, this paper adopted statistical analysis method or specific analysis method to determine the frequency of initiating events which could reflect the design of specific NPPs and operation level of domestic NPPs. The development and application of these initiating events analysis method, which could reflect design and operating characteristics more realistically, improved the development level of PSA model in operation phase effectively, and laid a solid foundation for PSA applications.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"169 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123191402","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Fire Probability Safety Analysis for a Compact Small Modular Reactor 小型模块化反应堆的火灾概率安全分析

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-91381

Yanzhu Chen

引用次数: 0

Level 1 Probabilistic Safety Analysis (PSA) of TNPP Units 3 and 4 3、4号机组的一级概率安全分析(PSA)

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-92359

Wenge Yu, Youyi Li, Xiye Lang, Yang Sun, Pengfei Zhao

{"title":"Level 1 Probabilistic Safety Analysis (PSA) of TNPP Units 3 and 4","authors":"Wenge Yu, Youyi Li, Xiye Lang, Yang Sun, Pengfei Zhao","doi":"10.1115/icone29-92359","DOIUrl":"https://doi.org/10.1115/icone29-92359","url":null,"abstract":"\u0000 Tianwan Nuclear Power Plant (TNPP) Units 3&4 (the second phase) are a landmark project for Chinese and Russian governments to jointly promote China-Russia nuclear energy cooperation.All the reactor units adopt the Russian VVER-1000 improved nuclear power units which are now operated by project owner, Jiangsu Nuclear Power Corporation (JNPC).\u0000 The depth and quality of PSA development, at the stage of Units 3&4 commercial operation,should be sufficient to obtain the risk-informed insights, enough to support the Risk-Informed application of PSA, and also reflect the actual design and its operation experience of TNPP.\u0000 This paper presents the brief introduction of PSA of Unit 3&4 of TNPP (power operation mode). The important parts of this presentation are as follows:probabilistic safety indices, study scope, technical elements and the analysis of Core Damage Frequency (CDF) quantitative results.\u0000 Through quantitative calculation, the point estimation value of the total CDF of TNPP under the power condition is obtained. And the frequency of occurrence of each event sequence and the CDF contribution of each initiating event (IE) etc., are analyzed.\u0000 Based on the developed PSA models, four PSA application tools have been developed and applied in the risk monitoring activities of nuclear power plant. This PSA model is used to take the lead in carrying out the Online maintenance in China.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"378 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121763391","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0

Research on PSA Analysis for Equipment Degradation in Nuclear Power Plant 核电站设备退化的PSA分析研究

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-93228

Zhi Yang, Si-Qi Zhang

引用次数: 0

Pilot Application of RISMC Methodology on Specific SBLOCA Sequences of Passive NPP RISMC方法在被动核电厂特定SBLOCA序列上的试点应用

Volume 13: Risk Assessments and Management Pub Date : 2022-08-08 DOI: 10.1115/icone29-92128

Yujia Du, Qinfang Zhang

{"title":"Pilot Application of RISMC Methodology on Specific SBLOCA Sequences of Passive NPP","authors":"Yujia Du, Qinfang Zhang","doi":"10.1115/icone29-92128","DOIUrl":"https://doi.org/10.1115/icone29-92128","url":null,"abstract":"\u0000 In this paper, a typical passive nuclear power plant small break LOCA is taken as the research object. Based on the theory of Risk Informed Safety Margin Characterization methodology, the development process of the accident is studied. The specific sequence is selected to be studied. The important systems are discretely branched (such as Automatic Depressurization System), and the important uncertainty parameters are sampled (such as ADS valve and IRWST valve resistance coefficient). The event tree is re-established, and the success criterion of the head is modified. The fault tree is reestablished. After that the uncertainty parameters are sampled for specific sequences and the accident simulation of the whole plant is carried out for each condition. Thus, the frequency of each sequence and the conditional failure probability under the specific condition are obtained, and the core damage frequency (CDF) value based on RISMC method is finally calculated.\u0000 This analysis is mainly aimed at the configuration and sensitivity of ADS. The selected sequence 45,53,64 are generated from the risk significant core damage sequence S in the original model. Through the analysis and calculation of RISMC method, it is concluded that sequence 45 is ok sequence, and the assumption in the original model is too conservative. OK cases with epidemic proportions existed in sequence 53; sequence 64 is consistent with the original hypothesis, which is a CD sequence. Therefore, the calculated value of CDF is reduced to a certain extent.\u0000 This paper verifies the feasibility of RISMC method in application on passive NPPs and also proves that the method can remove unnecessary conservatism. more realistic assessment of the risk helps us quantify the safety margin of nuclear power plants better.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"2 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2022-08-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"133310431","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}

引用次数: 0