{"title":"Research on Risk Management of Nuclear Engineering - Taking T Project Reverse Power Supply As an Example","authors":"Baoquan Wang","doi":"10.1115/icone29-90277","DOIUrl":"https://doi.org/10.1115/icone29-90277","url":null,"abstract":"\u0000 Under the vision of sustainable development and a community with a shared future for mankind, the era of “zero carbon” is coming to us. Nuclear energy has long been seen as one of the powerful means to achieve a “carbon neutral” future. Nuclear power projects are characterized by high technical requirements, long construction period, complex system composition, numerous stakeholders and heavy social responsibilities. Any link is crucial. Therefore, effective risk management of nuclear power projects is of great significance.\u0000 Based on the actual situation of nuclear POWER T project, the following studies are carried out:\u0000 (1) Through the research of domestic and foreign literature, Delphi method anonymous voting and expert consultation meeting were adopted to merge, filter and supplement the risk factors, and 24 risk factors in seven categories, including design, installation and commissioning, construction, contract, external, procurement and administrative licensing, were identified in the process of power transmission of NUCLEAR POWER T project.\u0000 (2) AHP fuzzy comprehensive evaluation method is used to select the hierarchical structure model of power supply risk factors, construct a judgment matrix, establish a risk evaluation table, calculate the risk weight of each level and rank it, compare the value interval of risk evaluation set, and get the power supply risk level of NUCLEAR power T project.\u0000 (3) In the outlook, the author considers the use of bow-tie model to prevent and control risk events in advance in the future, so as to formulate measures. Finally, the integrated risk control platform of reporting, early-warning, disposal and monitoring is proposed to form a closed-loop management of risk identification, reporting, disposal and rectification.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"1 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":"114922705","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}
{"title":"PSA Application in UK HPR1000 Numerical Targets Evaluation","authors":"Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang","doi":"10.1115/icone29-92462","DOIUrl":"https://doi.org/10.1115/icone29-92462","url":null,"abstract":"\u0000 As an important safety assessment tool, PSA plays a very important role in identifying the weak points in Nuclear Power Plants (NPP) design and optimizing plant design. Traditional PSA risk identification is mainly carried out from two dimensions: Core Damage Frequency (CDF) and Large Release Frequency (LRF). In the Generic Design Assessment (GDA) demonstration of UK HPR1000, As Low As Reasonably Practicable (ALARP) concept and Numerical Targets (NTs) are introduced, so the application scope of PSA is expanded. Risk contribution is identified not only from CDF and LRF dimensions, but also from on-site and off-site personnel radiation risk dimensions. Based on the expanded PSA application dimension, the safety level of nuclear power plants can be further improved. This study will give the methodology of PSA application in NTs 5∼9 evaluation, and the identified NPP weak points and related design improvement suggestions of UK HPR1000.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"734 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":"115129615","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}
{"title":"Study on Maintenance Strategy Optimization of Nuclear Power Plants After the Implementation of Maintenance Rule","authors":"Ma Xiliang, Xie Yongkui","doi":"10.1115/icone29-93167","DOIUrl":"https://doi.org/10.1115/icone29-93167","url":null,"abstract":"\u0000 After NNSA issued “Technical Policy for Improving Maintenance Effectiveness of Nuclear Power Plants (Trial)” in 2017, relevant units in China actively carried out pilot maintenance rule and gradually carried out optimization research on related maintenance activities. Suzhou Nuclear Power Research Institute Co., Ltd. has participated in most maintenance rule related projects in China. This paper introduces the development of maintenance rule in China and the current implementation of maintenance rule for nuclear power plants in China. Combined with the current situation of technical specification and the construction of configuration risk management in China’s nuclear power plants, the optimization of maintenance strategy based on maintenance rule is studied, which lays a foundation for more risk-informed applications, in order to strengthen the safety of nuclear power plants more effectively and reduce the unnecessary operation burden without affecting safety.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"1 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":"128862676","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}
{"title":"Research on Risk-Informed Regulation Approaches of MSPI and SDP","authors":"Guoxu Zhang, L. Chen","doi":"10.1115/icone29-90820","DOIUrl":"https://doi.org/10.1115/icone29-90820","url":null,"abstract":"\u0000 By integrating operating experience, accident analysis, risk assessment and defense-in-depth philosophy into decision-making consideration, risk-informed regulation better focuses regulatory attention to an issue consistent with its risk significance, which facilitates the establishment of appropriate regulation without damaging nuclear safety at the same time. By referring to the inspection findings from nuclear power plant, this paper utilizes Mitigating System Performance Indicator (MSPI) and Significance Determination Process (SDP) for research. From perspectives of basic theory, risk analysis and regulatory application consideration, this paper analyzes the correlation and differences between MSPI and SDP. The work could provide reference for the application and promotion of Risk-informed Regulation Approaches.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"27 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":"122246381","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}
{"title":"Nuclear Power Plant Design Optimization Based on Risk-Informed Method","authors":"Wenjing Li, Y. Liu, Gaopeng Wang, Xinli Yu","doi":"10.1115/icone29-89268","DOIUrl":"https://doi.org/10.1115/icone29-89268","url":null,"abstract":"\u0000 The probabilistic safety analysis method is an effective tool to demonstrate the balance of design and identify the vulnerabilities. It can provide technical support for the design optimization of nuclear power plant. A nuclear power plant in China specially designed the reactor cavity injection system (RCI) with both active and passive trains to mitigate the severe accident with core damaged. When the core damage accident occurs, the melt debris in the lower head can be cooled by RCI with water injection to the outside surface of the reactor vessel, thereby maintaining the integrity of the vessel and realizing the core melt in-vessel retention (IVR). This paper will introduce the design of the cavity injection system, and use the PSA method to establish a model of the system. Then the reliability of the system and its contribution to the large release frequency will be discussed, the vulnerability of the system will be identified. System design optimization recommendations will be proposed based on PSA results, and the results comparison between the optimization scheme and the original design is discussed. It can be concluded that in the design process of NPP, risk-informed methods should be considered as an important technical support tool.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"48 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":"128202809","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}
{"title":"Practice of Risk-Informed Nuclear Safety Management in CGN","authors":"Chen Shijun, Luo Wenbo, Wang Zichun, C. Lihui","doi":"10.1115/icone29-93663","DOIUrl":"https://doi.org/10.1115/icone29-93663","url":null,"abstract":"\u0000 The development experience of nuclear power industry shows that risk-guided nuclear safety management is an effective means to deal with multi-unit nuclear safety management and improve the flexible operation of nuclear power plants. In order to comprehensively and effectively manage the nuclear safety status of group plant units, based on advanced nuclear safety management methods, CGN has gradually established and improved an independent supervision system for nuclear safety since 2017. After several years of exploration, the evaluation of group plant performance indexes and the importance of abnormal events, the determination of the operation safety state supervision and management action matrix and the corresponding action requirements have been carried out gradually, so as to realize the closed-loop management of the operation state of units. This paper summarizes the implementation of advanced nuclear safety management methods at the group level and proposes the direction for further development.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"1 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":"130139064","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}
{"title":"Study on Probability Safety Assessment Method of Small Aircraft Crash Event in a Nuclear Power Plant","authors":"Handing Wang, X. Liang","doi":"10.1115/icone29-90733","DOIUrl":"https://doi.org/10.1115/icone29-90733","url":null,"abstract":"\u0000 In nuclear power plants, one of the external human-caused events is aircraft crash. The method used to evaluate the risk of aircraft crash must comply with the requirements of national nuclear safety guidelines. When estimating the distance of aircraft from facility, the events for which the aircraft distance satisfying the screening guidelines may be left out of account firstly. While for those unmet, it is necessary to apply probability safety assessment to further study whether the risk of aircraft crash into nuclear power plants is within the probabilistic screening level. If the aircraft impact can not be eliminated through distance or probability screening, the next step is to identify the corresponding aircraft type, and determine the design basis of aircraft crash event as an input. For the purpose, this paper analyzes the impacts of small military airports near nuclear power plants, and researches into the probability safety assessment method for military aircraft impacting nuclear power plants, i.e., airport and non-airport operation risks. According to the study, the risk of airport operation can be ignored as the conditional probability f (x, y) representing the military aircraft falling to the site shows very low. Conservatively considering the military aircraft impact “four-factor formula parameters”, the aircraft crash impact frequency of non-airport operation is 6.23E−08/year, also the total impact frequency of military aircraft crash event, which is less than the screening level in terms of probability and meets the requirements of nuclear safety guidelines. This study aims at providing certain reference value for the establishment of design basis to protect nuclear power plants from aircraft crash.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"64 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":"132953019","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}
{"title":"Research on Optimization Method of Risk-Informed In-Service Inspection Strategy of RCP-RRA Connection Inlet Valve in Nuclear Power Plant","authors":"Chen Li-hui, Yong Zhang, Chen Shi-jun","doi":"10.1115/icone29-93142","DOIUrl":"https://doi.org/10.1115/icone29-93142","url":null,"abstract":"\u0000 This paper discusses the problems and risks exiting in the in-service inspection of RCP-RRA and connection inlet valve of nuclear power plant, and puts forward the method of optimizing the in-service inspection strategy according to the essence of risk-informed technology. Taking a domestic PWR nuclear power plant as an example, the application process of the optimization method is demonstrated through the combination of determinism and probability theory. The results show that it is acceptable to extend the disassembly inspection cycle of RCP-RRA connection inlet valve,verify the feasibility of the optimization method, and point out the impact of valve monitoring measures on the optimization method, so as to support the comprehensive decision-making and safety review of nuclear power plants.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"112 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":"127964067","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}
{"title":"Application of Nuclear Insurance Risk Survey Results in Nuclear Power Plant Safety Improvement Program","authors":"Jiang Ping, An Jiangtao, Liu Changliang","doi":"10.1115/icone29-90396","DOIUrl":"https://doi.org/10.1115/icone29-90396","url":null,"abstract":"\u0000 From the prospective of loss prevention, economic risk reduction and catastrophe risk reduction, nuclear insurance risk survey provides professional and foresighted safety improvement recommendations based on the international nuclear and insurance experience. As a common international risk management practice, nuclear insurers provide loss prevention evaluation services, which is considered as peer review by nuclear operators. With the development of Chinese insurance industry and increasing loss prevention demand from Chinese nuclear power plant, Chinese insurance industry gradually integrates international practice, and establishes a systematic, Chinese characterized nuclear insurance survey methodology. This thesis introduces insurance survey background and importance, analyses the areas in which insurance survey could support nuclear power risk management. This paper focuses on risk survey methodology and implementation plan based on insurance service practices, and analyses survey result trends. The methodology has been implemented in nuclear power risk management regime. Recent cases have verified the insurance survey could support nuclear power plant safety improvement. Besides, based on the current practice, this paper suggest the potential ways to improve the interface between insurance risk survey and nuclear power risk management, improve common risk and enhance survey effectiveness.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"10 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":"131038841","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}