Volume 13: Risk Assessments and Management最新文献

{"title":"Nuclear Power Plant Fire Safety Risk Management Method and Application","authors":"Yaoyao Zhu","doi":"10.1115/icone29-93533","DOIUrl":"https://doi.org/10.1115/icone29-93533","url":null,"abstract":"\u0000 The history of nuclear power development shows that fire is one of the important risks faced by nuclear power plants, and the harm to nuclear power plants cannot be ignored. As scientific and technological innovation is playing an increasingly important role in changing social production and life, it is necessary to explore the application of information technology to comprehensively improve the technological, informational and intelligent level of fire fighting work, and improve the efficiency of fire fighting management through the deep integration of fire safety and intelligence in nuclear power field. This paper analyzes the current status of fire safety management in domestic nuclear power plants. It takes the fire load refinement and intelligent management as an example to discuss and propose optimization suggestions for nuclear power plant fire safety management. Based on Performance-based and Risk-informed nuclear power fire safety management, Establish corresponding risk assessment guidelines to provide risk-informed decision-making advice for fire safety work. Develop nuclear power plant fire safety risk management application tools according to risk management methods. It can monitor the important fire hazard areas in real time, effectively supervise the new fire risk areas of nuclear power plants, quantitatively assess the fire risk and formulate coping strategies, and upgrade and optimize existing fire management methods. The fire safety risk management method covers risk-informed fire risk management to all fire protection fields of nuclear power plants, and develops fire safety management of nuclear power plants in a refined, informational and intelligent direction, greatly improving the fire safety management of nuclear power plants Level.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"47 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":"132672096","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 Risk-Informed Approach in Emergency Compressor Emergency Backup Function Test","authors":"Deyi Liu, Sixing Zha, Jian Wu, Yong Cao, Zilong Wang","doi":"10.1115/icone29-91480","DOIUrl":"https://doi.org/10.1115/icone29-91480","url":null,"abstract":"\u0000 The emergency compressed air production system is a part of the compressed air production system of the nuclear power plant. Its function is to provide the necessary compressed air to the nuclear island when the main air compressor fails and cannot provide compressed air. Each unit of the nuclear power plant has two emergency air compressors to provide backup air source for the compressed air distribution system for instrumentation. Under normal working conditions, one emergency air compressor is in the basic load state and the other is in the standby state. The two emergency air compressors will automatically start according to the degree of pressure drop of the compressed air production system. The purpose of the emergency backup function of the emergency air compressor is to verify that the two air compressors will start up as the system pressure drops in different states, and to verify the operating parameters of the two emergency air compressors. The test period is one week. Periodic testing is an important activity for nuclear power plants to ensure the availability of equipment that performs important functions. However, periodic testing exceeding a certain frequency may reduce the safety of the power plant and increase the unnecessary burden of the power plant. At present, PSA has been widely used in nuclear power plant operation guidance, maintenance rules and many other fields, PSA has developed into an important tool for safety assessment and decision-making. With the development of PSA technology, the risk-oriented model combining probability theory and determinism has also been applied in the optimization of the periodic test cycle of nuclear power plants, so that the resource allocation of power plants can be optimized under the premise of ensuring sufficient safety of nuclear power plants. Improve regulatory and operational efficiency. This paper will take the emergency compressed air production system of Fangjiashan Nuclear Power Plant (FSJ NPP) as an example to introduce the application method of the risk-oriented periodic test optimization method.","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":"132363226","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":"Radioactive Substance Release Risk Assessment for Fuel Mechanical Damage in Fuel Route","authors":"Ming Wang, D. Guo, Fei Wang, Zhixin Xu, Bing Zhang, Jinkai Wang, L. Tong, Xuewu Cao","doi":"10.1115/icone29-92301","DOIUrl":"https://doi.org/10.1115/icone29-92301","url":null,"abstract":"\u0000 Irradiated fuel assemblies may be damaged by dropped load or other external force during their operation and storage, resulting in a potential release of radioactive substance. In order to assess the risk of radioactive substance release risk caused by fuel mechanical damage, the methodology of probabilistic safety assessment is used in this study. It takes the initiating events analysis as the starting point, studies the various technical elements involved, and provides the corresponding quantitative assessment results and risk insights. The results of case analysis show that the dominant contribution to the fuel mechanical damage frequency comes from the drop of fuel assembly due to spent fuel pool crane failure. The risk of fuel mechanical damage can be effectively reduced by the purification of spent fuel pool water and ventilation system in the buildings. Optimizing the lifting path of spent fuel cask in hoisting pit to avoid the maximum lifting height exceeding the cask test height, which can greatly reduce the risk of spent fuel cask cask dropping.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"12 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":"115402035","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":"Relay Chatter Analysis With Practical Application in Seismic PSA in Nuclear Power Station","authors":"Jianfeng Yang, Xiaohui Gu, Bingchen Feng, Hangding Wang","doi":"10.1115/icone29-89375","DOIUrl":"https://doi.org/10.1115/icone29-89375","url":null,"abstract":"\u0000 In the seismic PSA analysis of a nuclear power plant, the relay chatter analysis is a unique and important research content. An earthquake may cause inadvertent vibration of the relay contacts with an undesired output due to the low seismic ruggedness, and if the chatter time sustained more than 2 milliseconds, it will give an error signal. The error signal may lead to a refusing action or a mis-operation of relevant equipment, which will cause trouble to the mitigation of the earthquake accident of the nuclear power plant. Relay chatter could also actuate the lockout devices or seal-in devices associated with the supply breaker for essential buses, thus operator manual recovery is needed to re-close these breakers. Considering the accessibility of these equipment locations after an earthquake, it is difficult for operators to manually restore them if the number of these equipment is large. So relay chatter may cause an adverse impact on the accident mitigation functions by rendering selected accident mitigation equipment unavailable. This paper briefly introduces the method and procedure of Relay Chatter Analysis for the nuclear power plant PSA or SMA, then, illustrate it with an example of 380 VAC contactor control circuit. Finally, the modeling and quantification process for relay chatter analysis results in seismic PSA is briefly introduced, and a reference for solving similar problems is given.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"211 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":"124153340","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 and Practice of Living PSA Maintenance Methods","authors":"Zhi Yang, Chunhui Wang, Gang Li, Shihui Wang, Liang Pei","doi":"10.1115/icone29-93229","DOIUrl":"https://doi.org/10.1115/icone29-93229","url":null,"abstract":"\u0000 In the technical policy for configuration risk management of nuclear power plants (Trial), it is clearly required to use the active probabilistic safety analysis model to carry out configuration risk management. Living PSA is not a new concept independent of PSA, but a higher requirement for PSA, to ensure that PSA truly reflects the design and operation characteristics of nuclear power plant, and truly reflects the risk of nuclear power plant. The development and maintenance of living PSA involves all aspects of nuclear power plant and requires close cooperation of multiple departments. Therefore, the construction of living PSA system requires not only reasonable maintenance methods, but also appropriate organization and quality assurance support.\u0000 Based on this point, this paper introduces the basic concept, content and development status at home and abroad of living PSA, studies the maintenance methods of living PSA, and puts forward the common problems and development direction in the maintenance process of living PSA in combination with the actual process and mode in the application process of CGN group, which has reference significance for the development of PSA model maintenance strategy, configuration risk management and maintenance rules.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"140 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":"123342160","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":"Probabilistic Safety Assessment on Water Intake Blockage of Nuclear Power Plant","authors":"Yan Wu, Bingchen Feng, Gan Meng, Xiaoming Zhang","doi":"10.1115/icone29-93528","DOIUrl":"https://doi.org/10.1115/icone29-93528","url":null,"abstract":"\u0000 The marine organism outbreak can lead to water intake blockage, system degradation, equipment failure, and even worse, trip or lose of heat-sink event. According to a survey conducted by the American Electric Power Research Institute (EPRI) in 2009, among the 77 plants surveyed, more than 55% of plants suffered unplanned shutdown or unplanned power reduction events caused by water intake blockage. In recent years, several water intakes blockage events caused by marine organism were reported by domestic nuclear power plants. which leaded to power reduction or shutdown event and heat sink SSCs (systems, structures, and components) degrade or failure. These events greatly threaten operation management, equipment maintenance and emergency response of nuclear power plants. Hence, it is necessary to carry out detailed risk assessment on the water intake blockage event caused by marine organism outbreak.\u0000 Aiming at a large-sized pressurized water reactor (PWR) nuclear power plant, this paper builds a realistic model to analyze the risk caused by marine organism using PSA (probabilistic safety assessment) method, and obtains quantitative results of the unit. This paper also identifies the problems and deficiencies in plant’s response to the water intake blockage events, and provides us with risk insight to improve the safety level of nuclear power plants combining the analysis results.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"6 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":"134547867","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 Probabilistic Safety Analysis Method of Spent Fuel Reprocessing Facilities","authors":"Jinghan Zhang, Jun Zhao, Jie Hou","doi":"10.1115/icone29-90767","DOIUrl":"https://doi.org/10.1115/icone29-90767","url":null,"abstract":"\u0000 Probabilistic safety analysis (PSA) method is a systematic analysis method based on probability theory. Based on the PSA method, the relationship and interaction between various factors in a large and complex system can be recognized clearly, and the accident scenarios can be modeled correctly. After years of development, PSA has gradually become an important tool for evaluating the safety of nuclear power plants, and has been widely used. For the safety analysis of spent fuel reprocessing facilities, deterministic safety analysis methods are still mostly used. It is beneficial to introduce quantitative probabilistic safety analysis methods into spent fuel reprocessing facilities. For spent fuel reprocessing plants, there are many features which are totally different from nuclear power plants. Therefore, we are supposed to establish a new framework for PSA of spent fuel reprocessing plants. In this study, the spent fuel reprocessing facilities safety evaluation methods and the PSA method were investigated, based on the risk characteristics of spent fuel reprocessing facilities, every technical element of PSA method was adjusted. We studied the possible problems existing in the application of PSA method and proposed corresponding solutions, and then established a PSA method system suitable for spent fuel reprocessing facilities. Finally, we used PSA method to evaluate the safety of the selected typical processes of spent fuel reprocessing facilities and got the analysis result which is useful for practical application.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"29 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":"129471482","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 of Probabilistic Safety Assessment of CPR1000 Considering Aging Effects","authors":"Xiaoming Zhang, Lijuan Wang","doi":"10.1115/icone29-92459","DOIUrl":"https://doi.org/10.1115/icone29-92459","url":null,"abstract":"\u0000 In order to quantify aging impact to core damage risk of CPR1000 units which are widely distributed in China, it is necessary to develop a technical framework of probabilistic safety assessment (PSA) considering aging effects. Several basic technical elements affected were identified. At first, general rules were established to identify and screen structures, systems and components (SSCs) based on their risk contributions and aging sensitivities. No further work was required for SSCs screened out. Some SSCs which are not included in current PSA model should be added if aging effects are considered, e.g. pipes and cables. Secondly, a formula to calculate the aging failure rate was developed, considering aging effects and aging management actions. Thirdly, a method of integrating aging effects into current PSA model was developed, including the development of aging basic events and handling of different failure rates with different operating time. The accident of large break loss of coolant was selected for case analysis. A brief PSA model was developed and a quantitative result was generated for the selected accident. The result of the case analysis showed that aging effect could have a significant influence to the core damage frequency and relevant risk insights of PSA for a CPR1000 nuclear power unit.","PeriodicalId":407628,"journal":{"name":"Volume 13: Risk Assessments and Management","volume":"9 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":"115152388","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":"The Application of Risk-Informed Management Index in NPPs Risk Management","authors":"Chen Shijun, Zhang Yong, Luo Wenbo, Y. Shuixiang","doi":"10.1115/icone29-93639","DOIUrl":"https://doi.org/10.1115/icone29-93639","url":null,"abstract":"\u0000 With domestic NPP units increased, it is urgent to establish a more reasonable regulation way with full emphasis on plant significant items. This paper, based on the deterministic methodology and engineering judge, researches the risk-informed management index by applying SDP into events risk evaluation at all sites, which can help forecast the risk trend next month and pre-determine the current NPP risk status of each month with established risk judge criteria. Furthermore, some information and suggestions about risk significant events and risk prediction values are also mentioned in this paper, as well as some examples, in order to offer some references for management level to accomplish the decision-making.","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":"133352114","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":"Fuel Route Risk Assessment Framework and Pilot Plant Application","authors":"Ming Wang, Chun-Hao Yang, Linmei Xiao, Wenyu Hou, Zhixin Xu, Bing Zhang, Jinkai Wang, Lei Cui","doi":"10.1115/icone29-90824","DOIUrl":"https://doi.org/10.1115/icone29-90824","url":null,"abstract":"\u0000 Damage to fuel assemblies and the release of radioactive substance may occur during fuel lifting and storage in nuclear power plant. For the purpose of quantitatively evaluate internal events, internal and external hazards induced risk of spent fuel pool and related fuel lifting facilities, to identify weaknesses of the fuel route design and provide corresponding risk insights, the methodology of fuel route probabilistic safety assessment (PSA) is systematically summarized in this study, and based on the design characteristics of a specific pressurized water reactor nuclear power plant, fuel damage frequencies and radioactive substance release frequencies in the fuel route are assessed, some possible further safety improvements for the fuel route are identified. The results of analysis case show that the fuel building ventilation system failure has the largest contribution to the overall fuel thermal damage frequency, while the spent fuel crane failure has the largest contribution to the overall fuel mechanical damage frequency. The drop of the spent fuel cask full of spent fuels in loading pit has a prominent contribution to the risk of radioactive substances release due to the mechanical damage. The safety risk in the fuel route can be effectively reduced by the diversified design of local cooling unit fans in fuel building ventilation system and type modification of the spent fuel pool crane.","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":"130555784","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}