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

{"title":"Development and Application of Nuclear Power Plant Life Cycle Management Database Platform","authors":"Cao Guochang, Liu Zhao, Lv Fangming, Yang Zhenzhong, J. He, Cui Yixin","doi":"10.1115/icone29-93061","DOIUrl":"https://doi.org/10.1115/icone29-93061","url":null,"abstract":"\u0000 In the long life extension operation of nuclear power plant, life cycle management technology can provide reliable support for the economic operation of nuclear power plant, and is an important support technology for the evaluation of nuclear power plant’s continuous operation. In order to promote the development of life cycle management technology in nuclear power plants, information technology is used to transform specific problems into standardized databases, relying on the Operation License Renewal Project, the software platform of life cycle management database for important equipment in nuclear power plant is developed. In addition to the storage function of the equipment life cycle management information, the database has the functions of cost calculation and economic comparison of the long-term operation plan. It includes seven modules: Original Information, Program Management, Aging Mechanism, Out-of-date Evaluation, Failure Rate, Economic Analysis and External Feedback. The database built-in nuclear power plant life cycle management typical equipment such as steam turbines, generators, main transformers, and so on, while users can be independent in life-cycle equipment maintenance to add the need to expand the object. It is considered that the acquisition and reliability of cost data, equipment reliability data, and equipment life and failure rate data are the difficulties of life cycle management of nuclear power plants at present.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"96 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":"115436297","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 Treatment of Pressure Regulation Defects in Fuel Circuit of Emergency Diesel Engine of One Nuclear Power Plant","authors":"G. Feng","doi":"10.1115/icone29-92726","DOIUrl":"https://doi.org/10.1115/icone29-92726","url":null,"abstract":"\u0000 For one nuclear power plant, the pressure of the diesel engine fuel oil circuit happened to fail to fit the design because of low fuel oil inlet pressure and fall-off of the O-ring of the pressure regulating valve. A lot of data has been collected from tests performed in different conditions during the commissioning phase of this type of diesel, and after a lot of work the wrong diameter of the orifice plate and the improper inner structure of the pressure regulating valve in the fuel oil returning circuit were proved to be the main reasons. This project tried to solve the problems in a systematic way. Single-variable method was used to find out that the inner hole diameter of the orifice plate was too large to maintain the fuel oil pressure at a high level even if the pressure regulating valve was blocked and the right diameter was found and tested on site. The inner part (valve disc) of the pressure regulating valve was found fail to keep the O-ring under the alterable pressure, then fail to regulate the fuel oil pressure. The structure of the valve disc was optimized to fit the alterable pressure working situation. Finally, the defect in fuel circuit of emergency diesel engine was solved by adjusting the bore diameter of the orifice plate and changing the structure of the pressure regulating valve disc. The relevant tests were successfully done after the modification implementation.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","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":"121053488","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":"Reliability Analysis of Off-Plant Power for Multi-Units","authors":"Chen Honghao, Ren Cheng, Wu Jian, Liu Deyi, Luo Yang, Zou Shengjia, Wang Zilong","doi":"10.1115/icone29-91870","DOIUrl":"https://doi.org/10.1115/icone29-91870","url":null,"abstract":"\u0000 Globally, multi-units are located at the same nuclear power plant site. After several serious nuclear accidents, the overall risk assessment of a nuclear power plant with multiple reactors has attracted much attention. Combined with the concept of PSA (probabilistic safety analysis) for multi-units, this paper analyzes the off-plant power supply configuration of 9 units in Qinshan Nuclear Power Base. In view of the 6KV emergency busbar directly affected by the instability of the off-site power grid, the correlation among several units is fully considered, and the exploratory research and analysis of off-site power grid reliability is carried out in Qinshan Nuclear Power Base. Taking the reliability of external power grid of Qinshan Nuclear Power Base as an example, the reliability of emergency bus and the influence range and contribution of various analysis factors to the evaluation results are quantitatively analyzed through fault tree modeling. The results of model analysis are in line with the actual situation. The analysis concept based on the multi-unit PSA methodology should be used in a wider range. For example, thematic analysis should be carried out for other highly correlated originating events (common cold source, equipment common cause failure, etc.), and the development and progress of multi-unit PSA should be promoted through practice with a point-to-surface approach. In the follow-up research, we should improve the model system, take the actual situation into full consideration, and develop a set of overall risk assessment system that can reflect the real-time risk level of multiple unit site.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"23 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":"125955380","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 the Technology Accuracy of the On-Line Fracture Assessment of Cracked Pipe in NPPs","authors":"Mingya Chen, M. Yu, Hongbo Gao, Shuang Qi, Lei Lin, D. Xu, Weiqiang Wang, Jinhua Shi, Q. Peng, Guodong Zhang","doi":"10.1115/icone29-89057","DOIUrl":"https://doi.org/10.1115/icone29-89057","url":null,"abstract":"\u0000 The cracked pipes usually need to be replaced or conservatively evaluated in the Nuclear Power Plants (NPPs). There is still a lack of effective methods for a real-time crack propagation and safety evaluation based on massive monitoring transient data. From a technical standpoint, there is a need to establish inspection and monitoring technologies. This research has carried out a re-development in the general finite element analysis (FEA) software platform which is based on our research results and the requirements of the RSE-M Code. In this paper, the re-development is introduced firstly. Then, the information of the large pipe test information from France, Japan and China is summarized. Finally, the technology accuracy of the on-line fracture assessment of a cracked pipe in the NPPs is studied. The comparative research results show that the FEA analysis and modeling method of the pipe adopted by the authors in the re-development software is reliable and can meet the requirements for the on-line fracture assessment.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","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":"123428858","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 Method of Design Basis in Operating Nuclear Power Plants","authors":"Guangao Wu, W. Xiao","doi":"10.1115/icone29-91484","DOIUrl":"https://doi.org/10.1115/icone29-91484","url":null,"abstract":"\u0000 How to maintain the design basis to maintain or improve the safety level of nuclear power plants in their lifetime, the major nuclear power operation countries led by the United States and France have made a beneficial attempt. There is no systematic research and Application on the maintenance of design basis in China. With the accumulation of operation time of domestic nuclear power plants, we will soon face the challenge of design basis and the resulting pressure of safe operation. Design basis maintenance concept was raised from international Nuclear Power Plants (NPPs) operating experience, due to the safety and operating performance being challenged by the missing or violating of design bases. Investigation in the international experience of design basis maintenance is carried out and basis and key performance factors are identified base on the research in World Association of Nuclear Operators (WANO) and International Atomic Energy Agency (IAEA) suggestion and criteria. Methodology framework is proposed based on the basis. The framework clarifies the goal and tasks of design basis maintenance, raises a systematic method that carrying out margin management during NPP daily operation and maintenance, controlling the modification and carrying out periodic safety review to maintain the design bases. It can provide a useful reference for how to carry out design basis maintenance in operational nuclear power plants.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"69 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":"124595778","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 Signal Reconstruction Technology for Nuclear Power Plant Based on Self-Associative Kernel Regression","authors":"Zhuang Miao, Fangxiaozhi Yu, Zhao Xu","doi":"10.1115/icone29-89258","DOIUrl":"https://doi.org/10.1115/icone29-89258","url":null,"abstract":"\u0000 The instrument control system of the nuclear power plant is an important part of ensuring its safe and reliable operation. The sensor is the core component of the instrument control system to monitor the operation status of the nuclear power plant and trigger the operation of the instrument. Therefore, the availability of the sensor plays an important role of the safe operation of the nuclear power plant. The virtual sensor technology based on self-associative kernel regression can accurately determine the fault of the sensor signal, such as instrument drift, missing instrument values, etc. And it can replace the fault sensor with reliable and accurate values in a short period of time, ensuring normal operation of the system in a short period of time. In addition, the output value of the virtual sensor can also be used to calculate the measured value of the unmounted sensor part. This paper introduces a method to replace sensor values with right values when measured sensor values has something unusual. This paper only concerns about replacing sensor values and the paper assumes that it can find sensor fault correctly and timely. The paper selects the main steam system of the pressurized water reactor of the nuclear power plant as an example to verify the feasibility and reliability of the virtual sensor technology based on the self-associative kernel regression. The research results show that it is basically feasible to implement the virtual sensor technology by using the related technical solutions proposed in this paper.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"39 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":"123214512","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":"Simulation Analysis of Main and Auxiliary Switching and Motor Starting in Nuclear Power Plants","authors":"Zhang Xingzhen, Sun Hui","doi":"10.1115/icone29-92755","DOIUrl":"https://doi.org/10.1115/icone29-92755","url":null,"abstract":"\u0000 The main and auxiliary switching process involves the large-capacity asynchronous motor used in various systems (such as water pumps, fans, etc.) that are accompanied by strong electrical and mechanical shocks during the restarting or reinput process, especially the influence of the motor group restarting shock. The process includes the dynamic behavior of the electromagnetic and mechanical transient change process. In Order to quantitatively analyze the dynamic behavior of induction motor starting, the general steady-state analysis method can no longer be accurately solved, it is necessary to consider the dynamic load model of the transient process, and select ETAP software to realize the model establishment and transient process simulation calculation. For high-power motor load starting, the motor may fail to start due to low starting torque or other running motors connected to the power grid. Therefore, this paper selects typical high-power motors as the research object as the largest single load, and considers the harsh power supply conditions, and the transient conditions of the above-mentioned plant power switch motor group start, To verify whether the motor starting or restart will cause itself and other motors to stall, or whether it causes the EDG diesel generator to start. Whether the power system of nuclear power plant can resume stable operation after the above transient process has become an important index for evaluating the power system design of nuclear power plant. In this paper, the simulation study of the switching between the main power supply and the auxiliary power supply of the nuclear power plant, and the starting process of the high-power motor is established, the power system model of the power grid is analyzed at high voltage and low voltage, and the transformer is automatically loaded. The on-load voltage regulation, the plant power switching process and the high-power motor starting simulation calculation, effectively reduce the cost of the experiment, Has great economic benefits, it has positive significance for fault analysis.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"150 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":"121397546","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":"Proposal of Detailed Procedures of Determining Rational In-Service Inspection Requirements Based on System Based Code Concept","authors":"H. Yada, S. Takaya, K. Morohoshi, Shinobu Yokoi","doi":"10.1115/icone29-90542","DOIUrl":"https://doi.org/10.1115/icone29-90542","url":null,"abstract":"\u0000 In order to develop rationalized maintenance plans of nuclear power plants, it is necessary to consider characteristics of each plant. For sodium-cooled fast reactor (SFR) plants, there are constraints on inspections due to the specialty that sodium equipment needs to be handled, which is one of the important points when considering rationalization of maintenance. Therefore, we previously proposed a maintenance optimization scheme based on the System Based Code (SBC) concept. The concept of the SBC intends to give a theoretical procedure to optimize the reliability of the system by administrating every related engineering requirement throughout the life of the system from design to decommissioning. “ASME Boiler and Pressure Vessel Code, Code Case, N-875 Alternative Inservice Inspection Requirements for Liquid-Metal Reactor Passive Components” was already developed based on the SBC concept. The basic procedure of the code case has been also implemented in “ASME Boiler and Pressure Vessel Code, Section XI, Division 2” which provides requirements for Reliability and Integrity Management (RIM) programs for nuclear power plants including advanced reactors. One of proposed scheme goals is to develop detailed procedures of preparing a maintenance plan based on the process in the code case. In this study, the procedures to determine inspections for potential degradation and additional inspections in terms of defense-in-depth have been further clarified. The modified maintenance optimization scheme consists of the following processes. At first, potential active degradation mechanisms are identified. If there are any degradation mechanisms that are not addressed in the design codes, structural reliability evaluations are conducted to confirm whether the component of interest has sufficient reliability for the degradation mechanisms of concern. In the case the evaluated reliability does not meet a predetermined reliability target, inspections for the potential degradation are required. Next, the detectability of hypothetical defects before they grow to an unacceptable size in terms of plant safety is assessed. A method which has sufficient detectability, either in direct way such as volumetric examinations or in indirect way such as monitoring, is required as an additional inspection. If any methods are not applicable, reliability evaluation with a penalty is required. The penalty is determined conservative hypothesis relating safety function of the component of interest. If the evaluated reliability meets to the reliability target, additional inspections can be exempted. In this paper, the modified maintenance optimization scheme is also illustrated by a quantitative trial evaluation of the core support structure of the next SFR under development in Japan.","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":"129997716","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":"Safety Analysis About Combined Heat and Power Generation of Nuclear Power Plant","authors":"ShiYao Liu","doi":"10.1115/icone29-92883","DOIUrl":"https://doi.org/10.1115/icone29-92883","url":null,"abstract":"\u0000 Nuclear energy is one of the most efficient, clean and stable energy sources. The technology of combined heat and power generation, which is widely used in the conventional thermal power plants all over the world, is also applicable to the nuclear power plants to make full use of the nuclear energy. But at present, the mode of combined heat and power generation is rarely used in the nuclear power plants in China, concerning about the nuclear safety problem. This study aims at the optimum use of nuclear energy to raise the potential margin of nuclear power plants, under the premise of ensuring nuclear safety, and analyzes the influence of the combined heat and power generation (such as the external supply of steam generated by nuclear power plants) of a pressurized water reactor on nuclear safety, including the influence on the normal operation, design basis conditions, design extension conditions and transient analysis. It shows that combined heat and power generation of nuclear power plants has no negative impact on nuclear safety. In the meanwhile, the mode of combined heat and power generation can improve the economy of nuclear power plants and has positive significance for the efficient use of nuclear energy.","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":"131031711","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":"Maintenance Strategy Optimization Based on AP-913 in Relay Protection Field","authors":"Yu Zhao, Ping Li, Kunpeng Tian, Xingwei Fei","doi":"10.1115/icone29-93089","DOIUrl":"https://doi.org/10.1115/icone29-93089","url":null,"abstract":"\u0000 AP-913 (Equipment Reliability Process Description) describes an equipment reliability process offered to assist member utilities to maintain high levels of safe and reliable plant operation in an efficient manner. This document based on AP-913 process document, this paper generally describes its determination by logic and analysis method. Combining with the types of failure and consequences in the actual problems, it created a more simplified maintenance strategy optimization mind maps (including the system stability, the design necessity, the economic efficiency, the equipment reliability four factors, refining the equipment and benefit related factors, its relationship and influence between the four are clarified), that can raise efficiency of maintenance and enhance the stability of the system. Through its application in the maintenance cases, it takes some cases for example: Increase the PM project of replacing the power board card of the transformer group, shorten the PM project cycle of the transformer group power transmitter, and change the control operation mode of the main transformer cooler;cancel the design of outdated manual working frequency excitation equipment and its PM items, cancellation of electric disk cabinet timer, etc. It is proved that the reliability of the equipment is improved after the implement of the maintenance strategy optimization. Time costs and labor costs are saved, and the cost of equipment procurement is decreased too. Responding to control the company’s cost positively, some ideas at the same time also can provide reference for other similar plant maintenance work.","PeriodicalId":110070,"journal":{"name":"Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle","volume":"51 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":"133664514","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}