Xia Yan, Xuedong Ou, Min Lin, J. Mou, Shaolei Sun, Chunyun Chi, C. Zhao, Qin Zhou
Currently a two-step designing method of sequential neutronic physics and Stirling physical analysis was used for a Miniature Integrated nuclear Reactor design with gravity independent Autonomous Circulation (ACMIR). It was proposed in this article to optimize the intermediate/transitive variables of dead volume and heat exchange area/dead volume ratio as much as possible in the first step so that the system objectives in the second step can be better achieved. The ACMIR core was modified from using rod typed fuels to using plate typed fuels, making use of the plated core’s advantages of easy compression of coolant flow channel while maintaining large heat transfer area. As applied to a 40kWt cooperative dual Stirling power system design of ACMIR, the output power and efficiency index of the system had been significantly improved from 981W to 6395W (each Stirling), with efficiency from 7.4% to 26.6%.
{"title":"The Core Design Modifications for Stirling Thermal-Electric Integrated Micro Reactor","authors":"Xia Yan, Xuedong Ou, Min Lin, J. Mou, Shaolei Sun, Chunyun Chi, C. Zhao, Qin Zhou","doi":"10.1115/icone29-93465","DOIUrl":"https://doi.org/10.1115/icone29-93465","url":null,"abstract":"\u0000 Currently a two-step designing method of sequential neutronic physics and Stirling physical analysis was used for a Miniature Integrated nuclear Reactor design with gravity independent Autonomous Circulation (ACMIR). It was proposed in this article to optimize the intermediate/transitive variables of dead volume and heat exchange area/dead volume ratio as much as possible in the first step so that the system objectives in the second step can be better achieved. The ACMIR core was modified from using rod typed fuels to using plate typed fuels, making use of the plated core’s advantages of easy compression of coolant flow channel while maintaining large heat transfer area. As applied to a 40kWt cooperative dual Stirling power system design of ACMIR, the output power and efficiency index of the system had been significantly improved from 981W to 6395W (each Stirling), with efficiency from 7.4% to 26.6%.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"36 5 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":"116853057","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}
Qinghua Li, Jun Fang, Yafei Li, Bin Zhao, Guangfei Wang
Base on the result of full scope accident analysis for HPR1000,which is a third generation localized PWR with combination of initiative and passivity, the secondary side pressure of the damaged SG should be controlled by the steam generator blowdown system (TTB) during the retreat process of SGTR accident. In order to response the safety criteria of DBA function, the proposal of post accident discharge pipeline of TTB system should be improved. The part of secondary side fluid are discharged through the pipeline after SGTR, to realize the decrease of water level of damaged SG and preventing SG overfill. The paper suggests a proposal of post accident discharge pipeline for TTB as a mitigation measure of SGTR accident. The discharge flowrate with two phases flow condition in the discharge pipeline must be verified by theoretical calculation to evaluate the mitigation capability of the proposal. Now the performance test has been finished in the first unit of HPR1000, The achievement indicate the discharge capability of the proposal conform to the relative safety criteria for the SGTR accident.
{"title":"Design Improvement of the Discharge Proposal Preventing SG Overfill After SGTR in HPR1000 PWR","authors":"Qinghua Li, Jun Fang, Yafei Li, Bin Zhao, Guangfei Wang","doi":"10.1115/icone29-93093","DOIUrl":"https://doi.org/10.1115/icone29-93093","url":null,"abstract":"\u0000 Base on the result of full scope accident analysis for HPR1000,which is a third generation localized PWR with combination of initiative and passivity, the secondary side pressure of the damaged SG should be controlled by the steam generator blowdown system (TTB) during the retreat process of SGTR accident. In order to response the safety criteria of DBA function, the proposal of post accident discharge pipeline of TTB system should be improved. The part of secondary side fluid are discharged through the pipeline after SGTR, to realize the decrease of water level of damaged SG and preventing SG overfill. The paper suggests a proposal of post accident discharge pipeline for TTB as a mitigation measure of SGTR accident. The discharge flowrate with two phases flow condition in the discharge pipeline must be verified by theoretical calculation to evaluate the mitigation capability of the proposal. Now the performance test has been finished in the first unit of HPR1000, The achievement indicate the discharge capability of the proposal conform to the relative safety criteria for the SGTR accident.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"200 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":"121625579","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}
Nuclear power plant accidents are an important public safety issue, and most accidents occur mainly due to unexpected events of the operator. However, traditional nuclear plant interfaces do not provide operators with the ability to resolve unexpected events. As an interface design method, ecological interface design can improve the situational awareness of operators and is widely used in nuclear power plants and other fields. At the same time, in order to improve the adaptability of the interface structure change, this paper introduces a formative method — Cognitive Work Analysis (CWA). This approach aims to describe the given constraints acting on a complex system from different perspectives and structural levels in order to better show how the system operates, and traditionally consists of five stages: Work Domain Analysis (WDA, which create a set of models that describe how complex systems work and then use those models to guide system design), Control Task Analysis (ConTA, which Build models for known repetitive tasks), Strategy Analysis (StrA, which observe known repetitive activity in more detail), Social Organization & Cooperation Analysis (SOCA, which designed to address team communication and cooperation constraints and boundary conditions), and Worker Competencies Analysis (WCA, which describe the level of cognitive control required by the operator to accomplish different system functional goals and tasks). This article will discuss the framework for the use of these five stages at the ecological interface.
{"title":"Design of Ecological Interface for Nuclear Power Plant Based on Cognitive Work Analysis","authors":"Qike Yan, Feng Cheng, Hui Wu, Junzhou He","doi":"10.1115/icone29-93115","DOIUrl":"https://doi.org/10.1115/icone29-93115","url":null,"abstract":"\u0000 Nuclear power plant accidents are an important public safety issue, and most accidents occur mainly due to unexpected events of the operator. However, traditional nuclear plant interfaces do not provide operators with the ability to resolve unexpected events. As an interface design method, ecological interface design can improve the situational awareness of operators and is widely used in nuclear power plants and other fields. At the same time, in order to improve the adaptability of the interface structure change, this paper introduces a formative method — Cognitive Work Analysis (CWA). This approach aims to describe the given constraints acting on a complex system from different perspectives and structural levels in order to better show how the system operates, and traditionally consists of five stages: Work Domain Analysis (WDA, which create a set of models that describe how complex systems work and then use those models to guide system design), Control Task Analysis (ConTA, which Build models for known repetitive tasks), Strategy Analysis (StrA, which observe known repetitive activity in more detail), Social Organization & Cooperation Analysis (SOCA, which designed to address team communication and cooperation constraints and boundary conditions), and Worker Competencies Analysis (WCA, which describe the level of cognitive control required by the operator to accomplish different system functional goals and tasks). This article will discuss the framework for the use of these five stages at the ecological interface.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"53 3 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":"121998783","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}
Mechanical analysis of nuclear power pipeline is an important part of nuclear power design. At present, the widely used nuclear-grade pipeline mechanical analysis software in the world is PepS, which almost contains the commonly used standards and specifications in the nuclear power industry. PepS software is used to carry out the mechanical analysis of nuclear-grade pipeline. The key step is building a calculation input pipeline model that accounts for more than 70% of the entire pipe mechanical analysis workload. At the same time, in order to meet the strict process layout requirements of nuclear power, a pipeline usually needs to undergo multiple mechanical analysis and demonstration. There are thousands of pipelines in nuclear power projects, and its mechanical analysis needs to invest a lot of manpower cost. This research deeply analyzes the procedures and principles of PepS calculation input model, the topological structure and geometric characteristics of the 3D model of the pipeline based on the three-dimensional layout design results, and realizes the automatic modeling technology of mechanical calculation input model of nuclear power pipeline based on PepS software through digital and intelligent information technology. The implementation of this technology completely replaces the manual modeling, eliminates the human error of manual modeling, fundamentally liberates the productivity, obtains remarkable economic benefits, and helps the nuclear power design company go hand in hand with multiple projects to realize batch quantitative design and production.
{"title":"Research and Application of Automatic Modeling Technology for Mechanical Analysis of Nuclear Power Pipelines Based on PepS","authors":"Xiaoyang Gong, Xian Jing Jin, Yu Zhang","doi":"10.1115/icone29-91928","DOIUrl":"https://doi.org/10.1115/icone29-91928","url":null,"abstract":"\u0000 Mechanical analysis of nuclear power pipeline is an important part of nuclear power design. At present, the widely used nuclear-grade pipeline mechanical analysis software in the world is PepS, which almost contains the commonly used standards and specifications in the nuclear power industry. PepS software is used to carry out the mechanical analysis of nuclear-grade pipeline. The key step is building a calculation input pipeline model that accounts for more than 70% of the entire pipe mechanical analysis workload. At the same time, in order to meet the strict process layout requirements of nuclear power, a pipeline usually needs to undergo multiple mechanical analysis and demonstration. There are thousands of pipelines in nuclear power projects, and its mechanical analysis needs to invest a lot of manpower cost. This research deeply analyzes the procedures and principles of PepS calculation input model, the topological structure and geometric characteristics of the 3D model of the pipeline based on the three-dimensional layout design results, and realizes the automatic modeling technology of mechanical calculation input model of nuclear power pipeline based on PepS software through digital and intelligent information technology. The implementation of this technology completely replaces the manual modeling, eliminates the human error of manual modeling, fundamentally liberates the productivity, obtains remarkable economic benefits, and helps the nuclear power design company go hand in hand with multiple projects to realize batch quantitative design and production.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"61 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":"129612492","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}
Heat pipe cooled traveling wave reactor (HPTWR) is a newly proposed heat pipe reactor. The HPTWR can achieve the low enrichment of loaded fuel, high power density, and long-term continuous operation for the power supply of decentralized electricity markets. Due to the excellent breeding capability of the HPTWR, the Th fuel is also added into the breeding fuel region of the reactor to achieve the Th-U fuel cycle in this work. The Monte Carlo code RMC is used to obtain the reactivity swing, propagation of axial power peak, burnup and the productions of bred fissile nuclides for the HPTWR with Th and U fuels. The study shows that the HPTWR with 14.3% 235U enrichment of ignition fuel and 20% 235U enrichment of breeding fuel can continuously operate for 41 years without refueling when the mass fraction of 232Th in heavy metals of breeding fuel region is 50% at the initial time. The propagation velocity of axial power peak and total burnup for the HPTWR with the Th and U fuels is about 0.3659 cm/years and 89.32 GWd/THM during the 41 years operation respectively. The productions of the bred 239Pu, 241Pu and 233U in the HPTWR with Th and U fuels are about 356.40 kg of 239Pu, 1.57 kg of 241Pu and 199.94 kg of 233U at the end of life respectively. The obtained results in this study demonstrate that the HPTWR can achieve the Th fuel breeding in the case of the low 235U enrichment loading (≤ 20%) and long-term continuous operation (> 40 years).
热管冷却行波堆(HPTWR)是一种新型热管堆。HPTWR可实现负荷燃料富集度低、功率密度高、长期连续运行，为分散电力市场供电。由于HPTWR具有优良的增殖能力，本工作还在反应堆的增殖燃料区加入了Th燃料，实现了Th- u燃料循环。利用蒙特卡罗代码RMC计算了以Th和U为燃料的HPTWR的反应性摆动、轴向功率峰值的传播、燃耗和可增殖核素的产生。研究表明，当初始增殖燃料区重金属中232Th的质量分数为50%时，点火燃料235U浓度为14.3%、增殖燃料235U浓度为20%的HPTWR无需换料即可连续运行41年。在41年的运行过程中，使用钍和铀燃料的HPTWR轴向功率峰值的传播速度约为0.3659 cm/年，总燃耗约为89.32 GWd/THM。在使用Th和U燃料的HPTWR中，产生的239Pu、241Pu和233U在寿命结束时分别为356.40 kg、1.57 kg和199.94 kg 233U。本研究结果表明，HPTWR在低235U富集负荷(≤20%)和长时间连续运行(> 40年)的情况下可以实现Th燃料增殖。
{"title":"Study of Breeding Performance in a Heat Pipe Cooled Traveling Wave Reactor With Th and U Fuels","authors":"Kunfeng Ma, P. Hu","doi":"10.1115/icone29-93399","DOIUrl":"https://doi.org/10.1115/icone29-93399","url":null,"abstract":"\u0000 Heat pipe cooled traveling wave reactor (HPTWR) is a newly proposed heat pipe reactor. The HPTWR can achieve the low enrichment of loaded fuel, high power density, and long-term continuous operation for the power supply of decentralized electricity markets. Due to the excellent breeding capability of the HPTWR, the Th fuel is also added into the breeding fuel region of the reactor to achieve the Th-U fuel cycle in this work. The Monte Carlo code RMC is used to obtain the reactivity swing, propagation of axial power peak, burnup and the productions of bred fissile nuclides for the HPTWR with Th and U fuels. The study shows that the HPTWR with 14.3% 235U enrichment of ignition fuel and 20% 235U enrichment of breeding fuel can continuously operate for 41 years without refueling when the mass fraction of 232Th in heavy metals of breeding fuel region is 50% at the initial time. The propagation velocity of axial power peak and total burnup for the HPTWR with the Th and U fuels is about 0.3659 cm/years and 89.32 GWd/THM during the 41 years operation respectively. The productions of the bred 239Pu, 241Pu and 233U in the HPTWR with Th and U fuels are about 356.40 kg of 239Pu, 1.57 kg of 241Pu and 199.94 kg of 233U at the end of life respectively. The obtained results in this study demonstrate that the HPTWR can achieve the Th fuel breeding in the case of the low 235U enrichment loading (≤ 20%) and long-term continuous operation (> 40 years).","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"15 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":"121935331","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}
Modular construction technology is one of the effective ways to shorten the construction period and reduce the cost of nuclear power plants. It is one of the important features of the development of nuclear power engineering construction technology. The application of the module in China has a history of more than 20 years, and it was first used in the construction technology of nuclear island workshop dome steel lining. As modularization is the technology of integrated design,procurement and construction,and is based on the three-dimensional design platform, the close cooperation among design, procurement and construction also needs the support of the corresponding information platform. It is more urgent and necessary for the unified, shared and rapid interface response processing of upstream, downstream and management information. Based on the actual needs of nuclear power project construction and relying on the modular three-dimensional model, this paper develops and constructs a three-dimensional visual modular comprehensive information management system integrating the business data of design, procurement, construction, commissioning and management, realizes the efficient coordination and fine management of modular advanced construction technology of nuclear power project, and provides an information management platform for modular construction of nuclear power project.
{"title":"Development and Application of Modular Information Management System for Nuclear Power Engineering","authors":"Xiaocheng Gong, Xinwei Xu, Wei Zhou","doi":"10.1115/icone29-92073","DOIUrl":"https://doi.org/10.1115/icone29-92073","url":null,"abstract":"\u0000 Modular construction technology is one of the effective ways to shorten the construction period and reduce the cost of nuclear power plants. It is one of the important features of the development of nuclear power engineering construction technology. The application of the module in China has a history of more than 20 years, and it was first used in the construction technology of nuclear island workshop dome steel lining. As modularization is the technology of integrated design,procurement and construction,and is based on the three-dimensional design platform, the close cooperation among design, procurement and construction also needs the support of the corresponding information platform. It is more urgent and necessary for the unified, shared and rapid interface response processing of upstream, downstream and management information. Based on the actual needs of nuclear power project construction and relying on the modular three-dimensional model, this paper develops and constructs a three-dimensional visual modular comprehensive information management system integrating the business data of design, procurement, construction, commissioning and management, realizes the efficient coordination and fine management of modular advanced construction technology of nuclear power project, and provides an information management platform for modular construction of nuclear power project.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"20 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":"121989696","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}
The nuclear power large comprehensive reports need a lot of editing work and participants, the process is opaque, the format is not standardized and there are no effective collaborative tools. Because of overall process improving requirements, report review needs of format verification, optimization process, centralized storage of documents, and specification of document content, our company is in urgent need of new technical means. Collaborative editing is a new technology that is fundamental and critical in multidimensional collaboration of organizations, tasks, resources, processes, and format specifications. This thesis is based on the promotion of collaborative editing of large comprehensive reports, in-depth study of related technologies including the timeliness of collaborative editing, unified document format standards, unified and effective process control, unified document storage and version management from tools, processes and platforms, and proposes a construction plan to solve these existing problems, and finally provides a collaborative editing platform for each major. Construction and application of collaborative editing system for the nuclear power large comprehensive report realizes workflow and standardization, greatly improves editing efficiency and quality of large comprehensive reports, reduces manpower input, human errors, saves management costs of various professions and lately helps HPR1000 successfully pass qualification verification.
{"title":"Construction and Application of Collaborative Editing System for the Nuclear Power Large Comprehensive Report","authors":"Cheng Luo, Lin Jia, Wang Hao, Xiangyong Wu","doi":"10.1115/icone29-92900","DOIUrl":"https://doi.org/10.1115/icone29-92900","url":null,"abstract":"\u0000 The nuclear power large comprehensive reports need a lot of editing work and participants, the process is opaque, the format is not standardized and there are no effective collaborative tools. Because of overall process improving requirements, report review needs of format verification, optimization process, centralized storage of documents, and specification of document content, our company is in urgent need of new technical means. Collaborative editing is a new technology that is fundamental and critical in multidimensional collaboration of organizations, tasks, resources, processes, and format specifications. This thesis is based on the promotion of collaborative editing of large comprehensive reports, in-depth study of related technologies including the timeliness of collaborative editing, unified document format standards, unified and effective process control, unified document storage and version management from tools, processes and platforms, and proposes a construction plan to solve these existing problems, and finally provides a collaborative editing platform for each major. Construction and application of collaborative editing system for the nuclear power large comprehensive report realizes workflow and standardization, greatly improves editing efficiency and quality of large comprehensive reports, reduces manpower input, human errors, saves management costs of various professions and lately helps HPR1000 successfully pass qualification verification.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","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":"126671586","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}
Component Cooling Water System (CCWS) heat exchanger in nuclear power plant plays an important role in normal operation and accident condition. Because of the different requirements of heat conduction performance under normal operation and accident conditions, it is necessary to monitor the heat conduction performance under normal conditions to valuation the performance under accident condition. At present, the heat transfer coefficient is calculated by collecting the temperature and flow parameters of the cold and hot sides of CCWS heat exchanger. This way of valuation does not consider the influence of the change of plant operating conditions on the heat transfer coefficient of the heat exchanger, and it is also impossible to predict the failure time.The intelligent monitoring and diagnosis system using big data intelligent algorithm and failure mechanism model can automatically calculate the evaluation parameters that can characterize the trend changes of thermal and hydraulic performance of heat exchanger in real time, and realize the purpose of predicting the faults of heat exchanger in advance, thus guiding on-site maintenance personnel to accurately arrange maintenance activities.Based on the research of intelligent monitoring and diagnosis system of CCWS heat exchanger, this paper introduces the development direction and suggested realization method of CCWS heat exchanger in the intelligent process of nuclear power plant, and puts forward the conception of developing intelligent monitoring and diagnosis system of CCWS heat exchanger.
{"title":"Intelligent Monitoring and Diagnosis of CCWS Heat Exchanger For Nuclear Power Plant","authors":"Qian Ming, Jian Hu, Wu Wang","doi":"10.1115/icone29-92260","DOIUrl":"https://doi.org/10.1115/icone29-92260","url":null,"abstract":"\u0000 Component Cooling Water System (CCWS) heat exchanger in nuclear power plant plays an important role in normal operation and accident condition. Because of the different requirements of heat conduction performance under normal operation and accident conditions, it is necessary to monitor the heat conduction performance under normal conditions to valuation the performance under accident condition. At present, the heat transfer coefficient is calculated by collecting the temperature and flow parameters of the cold and hot sides of CCWS heat exchanger. This way of valuation does not consider the influence of the change of plant operating conditions on the heat transfer coefficient of the heat exchanger, and it is also impossible to predict the failure time.The intelligent monitoring and diagnosis system using big data intelligent algorithm and failure mechanism model can automatically calculate the evaluation parameters that can characterize the trend changes of thermal and hydraulic performance of heat exchanger in real time, and realize the purpose of predicting the faults of heat exchanger in advance, thus guiding on-site maintenance personnel to accurately arrange maintenance activities.Based on the research of intelligent monitoring and diagnosis system of CCWS heat exchanger, this paper introduces the development direction and suggested realization method of CCWS heat exchanger in the intelligent process of nuclear power plant, and puts forward the conception of developing intelligent monitoring and diagnosis system of CCWS heat exchanger.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"53 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":"114466976","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}
According to the process and content of process piping layout design, based on the A-star algorithm, this paper introduces the concept of automatic arrangement, and proposes an automatic arrangement design method for nuclear power plant process piping. The method takes into account several factors, such as the nuclear power plant plant scheme, the connection relationship and location of process equipment, the constraints involved in the design of process piping layout, and the performance of the process piping layout scheme. Based on this method, the programming simulation of the automatic arrangement of the nuclear power plant process piping is carried out, the automatic arrangement design of the nuclear power plant process piping is realized, and the applicability of the method in the automatic arrangement of the process piping of the nuclear power plant workshop is verified.
{"title":"Research on Automatic Arrangement Method of Process Piping in Nuclear Power Plant","authors":"Jincheng Su, Jing Xue, Xiaopan Jia, Zhenjie Gu","doi":"10.1115/icone29-92866","DOIUrl":"https://doi.org/10.1115/icone29-92866","url":null,"abstract":"\u0000 According to the process and content of process piping layout design, based on the A-star algorithm, this paper introduces the concept of automatic arrangement, and proposes an automatic arrangement design method for nuclear power plant process piping. The method takes into account several factors, such as the nuclear power plant plant scheme, the connection relationship and location of process equipment, the constraints involved in the design of process piping layout, and the performance of the process piping layout scheme. Based on this method, the programming simulation of the automatic arrangement of the nuclear power plant process piping is carried out, the automatic arrangement design of the nuclear power plant process piping is realized, and the applicability of the method in the automatic arrangement of the process piping of the nuclear power plant workshop is verified.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","volume":"77 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":"127225151","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}
Nuclear power equipment is an important part of nuclear power plant. It has the characteristics of complex system structure, long manufacturing cycle, long-term operation under irradiation conditions and poor working environment. It has high requirements for product quality grade. High reliability nuclear power equipment is an important premise and guarantee for the smooth construction and safe operation of nuclear power plant. Through digital twin technology, optimizing the design, manufacturing, operation and maintenance process of nuclear power equipment and improving the operation and maintenance efficiency of systems and equipment will be an important direction for the digital transformation and intelligent upgrading of nuclear power plants. This paper studies the digital twin core technologies such as multi-scale modeling, multidisciplinary joint simulation, virtual reality presentation and data mining, draws lessons from the concept of data life cycle management, develops the digital design platform of nuclear power equipment, realizes the integration of three-dimensional design, analysis, verification and Simulation of nuclear power equipment, and integrates the key data and models of nuclear power equipment operation, Provide support for the monitoring and maintenance of in-service equipment, and promote the digital transformation and upgrading of R & D and operation of key equipment in nuclear power plants.
{"title":"Research and Application Innovation of Digital Twin Technologies for Key Equipment of Nuclear Power Plants","authors":"Dong Zhao, F. Guan","doi":"10.1115/icone29-93416","DOIUrl":"https://doi.org/10.1115/icone29-93416","url":null,"abstract":"\u0000 Nuclear power equipment is an important part of nuclear power plant. It has the characteristics of complex system structure, long manufacturing cycle, long-term operation under irradiation conditions and poor working environment. It has high requirements for product quality grade. High reliability nuclear power equipment is an important premise and guarantee for the smooth construction and safe operation of nuclear power plant. Through digital twin technology, optimizing the design, manufacturing, operation and maintenance process of nuclear power equipment and improving the operation and maintenance efficiency of systems and equipment will be an important direction for the digital transformation and intelligent upgrading of nuclear power plants. This paper studies the digital twin core technologies such as multi-scale modeling, multidisciplinary joint simulation, virtual reality presentation and data mining, draws lessons from the concept of data life cycle management, develops the digital design platform of nuclear power equipment, realizes the integration of three-dimensional design, analysis, verification and Simulation of nuclear power equipment, and integrates the key data and models of nuclear power equipment operation, Provide support for the monitoring and maintenance of in-service equipment, and promote the digital transformation and upgrading of R & D and operation of key equipment in nuclear power plants.","PeriodicalId":422334,"journal":{"name":"Volume 12: Innovative and Smart Nuclear Power Plant Design","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":"127630668","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}
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