Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle最新文献_第3页

Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs 高温高压堆和压水堆燃料元件损伤监测技术研究

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-88883

Rui Nie, Yu Wang, F. Xie, Shan Qing, Jian-zhu Cao

{"title":"Investigation of the Fuel Element Damage Monitoring Technology in HTGRs and PWRs","authors":"Rui Nie, Yu Wang, F. Xie, Shan Qing, Jian-zhu Cao","doi":"10.1115/icone29-88883","DOIUrl":"https://doi.org/10.1115/icone29-88883","url":null,"abstract":"\u0000 Understanding the performance of fuel elements, particularly defective ones, in the reactor core quickly and accurately is essential as most radioactive nuclides are produced in the fuel elements and released into the primary circuit. Radioactivity in the primary circuit may result in potential radiation hazards to the maintenance workers and the environment near the nuclear power plant. Therefore, fuel element damage monitoring technology has received wide attention in the field of nuclear fission reactors. Few reviews focus on fuel element damage monitoring technology to facilitate the development of high-temperature gas-cooled reactors (HTGRs). In this study, we investigated the state of fuel element damage monitoring technology in HTGRs and pressurized water reactors (PWRs), summarized their characteristics and parameters, and compared their advantages and disadvantages. The radioactive source terms in HTGRs and PWRs were listed, and the typical nuclides in the primary circuit adopted for the fuel element damage monitoring were illustrated. This study can provide a good reference for developing fuel element damage monitoring technology in HTGRs in the future.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"109 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":"131867853","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

Review of Operating License Extension of Nuclear Power Plants 核电站运营许可证延期审查

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-93427

Zhilin Chen, Xiaowei Li, Ping Huang, C. Wang, Jun Wang, Zhiyuan Chi, Kuiyuan Fang, Y. An, Yanwei Zhang

{"title":"Review of Operating License Extension of Nuclear Power Plants","authors":"Zhilin Chen, Xiaowei Li, Ping Huang, C. Wang, Jun Wang, Zhiyuan Chi, Kuiyuan Fang, Y. An, Yanwei Zhang","doi":"10.1115/icone29-93427","DOIUrl":"https://doi.org/10.1115/icone29-93427","url":null,"abstract":"\u0000 Operating license extension (OLE) is an important trend in the development of Nuclear Power Plants (NPPs). About 30.2% of the units in operation in the world have reached or exceeded 40 years of operation. “License Renewal, LR” and “Periodic Safety Review, PSR” are two commonly strategies used for operating license extension demonstration. In December 2015 the technical policy of OLE in China was issued by National Nuclear Safety Administration (NNSA), with the main works of the demonstration include: (1) Current License Basis Review, (2) Scoping and Screening of Structures, Systems and Components (SSCs), (3) Aging Management Review (AMR), (4) Time Limited Aging Analysis (TLAA), (5) Updated of Finally Safety Analysis Report (FSAR), (6) Environment Evaluation. The demonstration of OLE of NPPs were carried out in two NPPs since 2013. In this paper, the demonstration strategies for OLE were introduced, the processes of the demonstration by LR in USA and PSR in France were provided. The interpretation of technical policy and Domestic status of OLE in China were illustrated. The technical issues for the OLE safety assessment were also reviewed. Furthermore, the trends for OLE in the future, such as multiple plants demonstration at one time, the secondly license renewal were discussed as well.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"42 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":"134141399","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

Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump 反应堆冷却剂泵停机分析与设计方法研究

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-93302

Yun Zhong

{"title":"Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump","authors":"Yun Zhong","doi":"10.1115/icone29-93302","DOIUrl":"https://doi.org/10.1115/icone29-93302","url":null,"abstract":"\u0000 Methodology of coastdown analysis for RCPs was investigated with consideration of combined effect of loop fluid inertia and pump inertia. A simplified methodology based on momentum equations of the loop and the pump respectively was developed to describe the combined effect, leading to a different guess of flow coastdown rather than speed coastdown. Both the traditional axial-sealed RCP and a canned motor sealless RCP experiment data on test rigs were used to verify the accuracy of the abovementioned methodology for coastdown flow calculation. It has been verified that the calculated coastdown flow fits with the measured data better when considering the influence of loop fluid inertia. Then a coastdown performance oriented design method considering the influence of loop fluid inertia was developed based on coastdown analysis methodology investigation, which can increase pump inertia flexibility without violation of nuclear safety and benefit for balance of safety, economy and technical feasibility. Using the slope of 1/q coastdown curve, which is approximately a straight line, makes RCP inertia determination much more definitely. And the methodology of coastdown analysis and design can be applied to sealless RCP when using overall efficiency without electric loss as input. Especially, deduction of electrical loss from the overall efficiency is important for canned motor RCP, because it has significantly large electrical loss due to stator can, while this loss is not applicable during coastdown without electric power supply.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"31 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":"122983773","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: 2

Study on the Water Intake of Heat Trap Blocked by Marine Life in Nuclear Power Plant 核电站海洋生物阻挡热阱取水的研究

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-90544

Zhenhua Zhang, Bo Zhang, Chaoying Zheng

{"title":"Study on the Water Intake of Heat Trap Blocked by Marine Life in Nuclear Power Plant","authors":"Zhenhua Zhang, Bo Zhang, Chaoying Zheng","doi":"10.1115/icone29-90544","DOIUrl":"https://doi.org/10.1115/icone29-90544","url":null,"abstract":"\u0000 In recent years, the operational events that the water intake of heat trap was blocked by marine life in nuclear power plants have occurred repeatedly. Since 2000, there have been more than 200 shutdown events of biological (foreign body) blockage resulting in failure of cooling water system in the United States, the United Kingdom, Sweden, Arabia, India, Israel, Japan, South Korea and China. It has caused major safety risks and brought huge economic losses and has attracted wide attention from various governments, related industries and research institutions. It can be seen that water intake blockage event is a safety problem for all kinds of power plants to face. This paper introduces the typical design of water intake and analyses the potential effects of a large number of marine life into the heat trap water intake from the perspective of circulating water system (CRF) jump pump and essential service water system (SEC) loss of function. Based on the characteristics of the high frequency of such operation events and they may cause major safety risks, the reactor shutdown response time in different conditions is simulated. When a large number of marine organisms flood into the water intake of heat trap, the response of the operator on the potential impact of the unit condition and the operational response plan are analyzed. The impact of the unplanned changes in operating status caused by the blockage of the water intake is explained. Ultimately, based on the analysis as described above, suggestions on the design improvement of the heat trap water intake and seawater filtration system in the nuclear power plant are presented. At the same time, suggestions are put forward on the supervision analysis, dynamic monitoring of the surrounding environment of the water intake, establishing a rapid decision-making mechanism, improving the cold source emergency response plan and increasing the operation control strategy.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","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":"129177091","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

Analysis of Contribution Degree of Vibration Transmission of Bolted Structure 螺栓结构振动传递贡献度分析

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-92499

Shuai Liu, Wanyou Li, Xuan Huang, Furui Xiong, Xiaozhou Jiang, Liwei Deng

{"title":"Analysis of Contribution Degree of Vibration Transmission of Bolted Structure","authors":"Shuai Liu, Wanyou Li, Xuan Huang, Furui Xiong, Xiaozhou Jiang, Liwei Deng","doi":"10.1115/icone29-92499","DOIUrl":"https://doi.org/10.1115/icone29-92499","url":null,"abstract":"\u0000 In practical engineering, the vibration transmission between bolted structures supported by cantilever beams involves many factors, including the friction between plates and the bolt connection relationship. The vibration transmission effect is the embodiment of the coupling of various factors, so it is impossible to accurately and quantitatively evaluate the influence degree of various factors. In this paper, the influence factors of vibration between bolted plates in the form of cantilever beam are studied by numerical calculation method. The effects of friction coefficient, bolt preload, temperature and internal and external pressure on vibration characteristics are studied. Finally, the contribution of different influencing factors to vibration transmission is given. The preliminary research shows that the bolt connects the two plates into a whole structure, and its stiffness changes little with the friction coefficient, bolt preload, temperature and internal and external pressure. The natural frequency of each order increases with the increase of friction coefficient, bolt preload and internal and external pressure, decreases with the increase of temperature, and the overall trend changes little. At the same time, the bolt preload is verified by test, the difference of natural frequency under the same preload is compared and analyzed, the numerical calculation is compared with the test value, and the vibration contribution of preload is verified.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","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":"114928788","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

An Insulation Structure With Noise Reduction Function 一种具有降噪功能的保温结构

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-93144

Zhang Yicheng, Bian Pengfei, Zhang Kai

{"title":"An Insulation Structure With Noise Reduction Function","authors":"Zhang Yicheng, Bian Pengfei, Zhang Kai","doi":"10.1115/icone29-93144","DOIUrl":"https://doi.org/10.1115/icone29-93144","url":null,"abstract":"\u0000 The sound insulation performance of nuclear power related equipment and pipelines is of great practical significance for the safe operation of nuclear power equipment. At the same time, the surface of the equipment is often covered with an insulating layer to maintain the temperature of the nuclear power equipment. If the thermal insulation material can play the role of vibration isolation and noise reduction, it will undoubtedly have a positive effect on the vibration and noise control of nuclear power equipment. Aiming at the insulation layer structure using glass wool as insulation material, this paper studies the acoustic performance of the pipeline after installing the insulation layer by means of experiments and theoretical calculations. This paper verifies that the thermal insulation layer structure can effectively improve the insertion loss and sound transmission loss of the structure while meeting the requirements of the thermal insulation layer. At the same time, this paper conducts a parametric analysis study to study the effect of different structural variables on the sound insulation performance of the thermal insulation layer. The results show that the increase in the bulk density of glass wool, the increase in the thickness of the metal coat, and the additional damping layer all increase the insertion loss of the structure.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"36 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":"125771865","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

The Test of Leakage Current of Terminal Stator Winding of the 4# Generator and Defects Treatment 4#发电机定子终端绕组漏电流测试及缺陷处理

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-93102

Kunpeng Tian, Ping Li, Yu Zhao, Xingwei Fei

引用次数: 0

Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance 开发核电站智能设备监控系统，提高核电站性能

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-91638

Jianming Yu, Yibiao Cai

{"title":"Developing Intelligent Equipment Monitoring System of Nuclear Power Plants to Improve Plant Performance","authors":"Jianming Yu, Yibiao Cai","doi":"10.1115/icone29-91638","DOIUrl":"https://doi.org/10.1115/icone29-91638","url":null,"abstract":"\u0000 The active development of nuclear power is an important strategic choice to achieve carbon peak and neutrality goals. It is an essential study to realize the economic operation of nuclear plants on the premise of ensuring the safety and reliability of nuclear power plants. Intelligent monitoring and maintenance technology is an important development tendency that can effectively improve the operation safety and maintenance economy of nuclear power plant. In this article, an intelligent monitoring and maintenance system of AP1000 significant equipment in Sanmen Nuclear Power Plant is developed based on the equipment operation mechanism and failure mode analysis by using advanced pattern recognition technologies including intelligent sensing, big data analysis, multidimensional spatio-temporal correlation condition monitoring and fault diagnosis technologies. It can realize online real-time equipment performance monitoring, automatic trend analysis, automatic health condition evaluation, early anomaly identification and automatic fault diagnosis of equipment in nuclear power plant and promote the transformation of maintenance mode from time-based maintenance to condition-based maintenance. The intelligent monitoring and maintenance system has been applied in various mechanical and electrical equipment of Sanmen Nuclear Power Plant such as reactor coolant pump, main steam turbine, main transformer, heat exchanger and achieved certain technical achievements and economic benefits. The construction of intelligent monitoring system has certain demonstration and popularization.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"103 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":"115716922","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

Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators 弹性亥姆霍兹谐振腔充液管道结构的紊乱

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-93421

Qingna Zeng, Donghui Wang, F. Zang, Yixion Zhang, Bihao Wang, Zhihao Yuan

{"title":"Disorders in Fluid Filled Pipeline Structure With Elastic Helmholtz Resonators","authors":"Qingna Zeng, Donghui Wang, F. Zang, Yixion Zhang, Bihao Wang, Zhihao Yuan","doi":"10.1115/icone29-93421","DOIUrl":"https://doi.org/10.1115/icone29-93421","url":null,"abstract":"\u0000 This paper studies the influence of hybrid disorders on acoustic transmission characteristic in pipeline with periodic elastic HRs. Band gap structures (BGs) for infinite period are investigated by transfer matrix method and finite element method respectively, and fit well with the corresponding transmission loss (TL) for finite regular periods. By introducing a certain degree of uncertainty level, Interval analysis method is used to convert uncertain parameter problems into two deterministic models. Frequency response function (FRF) for near-periodic structure with single disorder and BGs for quasi-periodic structure with multiple disorders considering cavity radius and periodic length are investigated. The existence of disorders in periodic structure would always reduce attenuation interval and intensity, some disturbance would even change the original acoustic transmission characteristic and excite completely new attenuation zones. The sensitivity of pipeline acoustic vibration transfer characteristic to disorder parameter depends on attenuation mechanism, as for periodic elastic HRs pipeline, acoustic propagation stability is more sensitive to characteristic of locally resonant unit. The work in this paper enriches the stability analysis of pipeline with elastic HRs, which would provide theoretical reference for noise and vibration reduction design in practical engineering applications.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"2014 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":"127573475","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

Analysis Method and Application of Maintenance Rules for Main Steam System in Qinshan no.1 Nuclear Power Plant 秦山一号主蒸汽系统维修规程分析方法及应用核电站

Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle Pub Date : 2022-08-08 DOI: 10.1115/icone29-92056

Yangjun Jin

{"title":"Analysis Method and Application of Maintenance Rules for Main Steam System in Qinshan no.1 Nuclear Power Plant","authors":"Yangjun Jin","doi":"10.1115/icone29-92056","DOIUrl":"https://doi.org/10.1115/icone29-92056","url":null,"abstract":"\u0000 Nuclear power plants have traditionally adopted regular preventive and corrective maintenance methods, but extensive international operation experience shows that inadequate maintenance, excessive maintenance and improper maintenance will adversely affect nuclear power plant structures, systems and equipment, and thus affect the safety level of nuclear power plant operation. According to China’s National Nuclear Safety Administration of the improved technology policy (try out) “the effectiveness of the nuclear power plant maintenance requirements, with the first nuclear power qinshan owner steam system as an example, the implementation based on the structures, systems and equipment effectiveness analysis method and risk management of the maintenance rules, can be more reasonable and effective to improve the reliability of maintenance.\u0000 The method mainly includes: determining the system boundary and the scope of structures, systems and equipment involved in the maintenance rules, screening the system maintenance rules function; List the equipment and failure modes that affect the function; The failure probability and function importance of each function group are calculated. The reliability index and availability index of the system are determined and verified by historical data. Supervise each function group of the system according to the key indicators, evaluate the actual operation of these structures, systems and equipment regularly, determine whether to meet the established performance indicators, optimize and adjust the maintenance rules according to the evaluation results, so as to avoid insufficient and excessive maintenance.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"55 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":"123474933","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