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Optimization of SCO2 Brayton Cycle Coupled Seawater Desalination System SCO2 Brayton循环耦合海水淡化系统的优化
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.112014
一非 滕
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引用次数: 0
Discussion of Emergency Equipment Management on Nuclear Power Plant from the “Operation Feedback of the Post-Fukushima Improvement Action” 从“后福岛改善行动的运行反馈”谈核电站应急设备管理
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.111008
文元 刘
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引用次数: 0
Research on Simplified Method for Calculating Thermal Deformation of the Pump Support in the Sodium-Cooled Fast Reactor 钠冷快堆泵支架热变形简化计算方法研究
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.112016
海波 许
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引用次数: 0
Application Research on Intelligent Optimization Algorithm in the Automatic Finetune of Nuclear Power Plant Digital-Twin System 智能优化算法在核电厂数字孪生系统自动调谐中的应用研究
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.111007
云龙 肖
{"title":"Application Research on Intelligent Optimization Algorithm in the Automatic Finetune of Nuclear Power Plant Digital-Twin System","authors":"云龙 肖","doi":"10.12677/nst.2023.111007","DOIUrl":"https://doi.org/10.12677/nst.2023.111007","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90565680","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
Development of the IAEA Severe Accident Simulator Based on Autonomous Severe Accident Analysis Program NUSSAP 基于自主严重事故分析程序NUSSAP的IAEA严重事故模拟器研制
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.113026
巍 魏
{"title":"Development of the IAEA Severe Accident Simulator Based on Autonomous Severe Accident Analysis Program NUSSAP","authors":"巍 魏","doi":"10.12677/nst.2023.113026","DOIUrl":"https://doi.org/10.12677/nst.2023.113026","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2023-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"90613179","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
Application Research of Neutron Activation Code ABURN in Shutdown Dose Rate Calculation of Nuclear Installation 中子激活码ABURN在核设施停堆剂量率计算中的应用研究
Nuclear Science and Technology Pub Date : 2023-01-01 DOI: 10.12677/nst.2023.111003
晓泽 赵
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引用次数: 0
Neutronic design of a PWR fuel assembly with accident tolerant-composite for the long-life core 长寿命堆芯耐事故复合材料压水堆燃料组件的中子设计
Nuclear Science and Technology Pub Date : 2022-05-11 DOI: 10.53747/nst.v11i2.358
Van-Khanh Hoang, Viet-Phu Tran, Thi Dung Nguyen
{"title":"Neutronic design of a PWR fuel assembly with accident tolerant-composite for the long-life core","authors":"Van-Khanh Hoang, Viet-Phu Tran, Thi Dung Nguyen","doi":"10.53747/nst.v11i2.358","DOIUrl":"https://doi.org/10.53747/nst.v11i2.358","url":null,"abstract":"For the future of nuclear power, the design and development of an economical, accident tolerant fuel (ATF) for use in the current pressurized water reactors (PWRs) are highly desirable and essential. It is reported that the composite fuels are advantageous over the conventional UO2 fuel due to their higher thermal conductivities and higher uranium densities. Due to higher uranium densities of the composite fuels, the use of composite fuels would lead to the significant increase of discharged burnup, thereby enhancing fuel cycle economy compared to that of the UO2 fuel. The higher thermal conductivities of composite fuels will increase the fuel safety margins. For implementation of the accident tolerant fuel concept, this study also investigates on the replacement of the conventional Zircaloy-4 cladding with SiC to minimize the hydrogen production due to interaction of water with cladding at high temperatures. In the present work, neutronic investigation of the composite fuels for a PWR has been conducted in comparison with that of the conventional UO2 fuel. Numerical calculations have been performed based on a lattice model using the SRAC2006 system code and JENDL-4.0 data library. Various parameters have been surveyed for designing a fuel with the UO2 and composite fuels such as U-235 enrichment, fuel pin pitch. In order to reduce the excess reactivity, Erbium was selected as a burnable poison due to its good depletion performance. The temperature coefficients including fuel, coolant temperature reactivity coefficients, and both the small and large void reactivity coefficients are also investigated. It was found that it is possible to achieve sufficient criticality up to 100 GWd/t burnups without compromising the safety parameters including that four reactivity coefficients are considered those associated with the fuel temperature, coolant temperature, small (5%) void and large (90%) void. Further analysis of the performance of the UO2 and composite fuels in a full core model of a PWR is being conducted.","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-05-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"79324553","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
Application and Research on Low Temperature Performance of Silicon Photomultiplier 硅光电倍增管低温性能的应用与研究
Nuclear Science and Technology Pub Date : 2022-01-01 DOI: 10.12677/nst.2022.101004
小雪 范
{"title":"Application and Research on Low Temperature Performance of Silicon Photomultiplier","authors":"小雪 范","doi":"10.12677/nst.2022.101004","DOIUrl":"https://doi.org/10.12677/nst.2022.101004","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"74583854","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
Application and Optimization of RSE-M 2010 in In-Service Inspection Program of Fuqing 5 & 6 Units RSE-M 2010在福清5、6号机组在役检验方案中的应用与优化
Nuclear Science and Technology Pub Date : 2022-01-01 DOI: 10.12677/nst.2022.101005
嘉维 刘
{"title":"Application and Optimization of RSE-M 2010 in In-Service Inspection Program of Fuqing 5 & 6 Units","authors":"嘉维 刘","doi":"10.12677/nst.2022.101005","DOIUrl":"https://doi.org/10.12677/nst.2022.101005","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"82342726","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
Design and Implementation of Configuration Management System Based on Nuclear Power Simulation Platform 基于核电仿真平台的组态管理系统设计与实现
Nuclear Science and Technology Pub Date : 2022-01-01 DOI: 10.12677/nst.2022.102006
华建 方
{"title":"Design and Implementation of Configuration Management System Based on Nuclear Power Simulation Platform","authors":"华建 方","doi":"10.12677/nst.2022.102006","DOIUrl":"https://doi.org/10.12677/nst.2022.102006","url":null,"abstract":"","PeriodicalId":19445,"journal":{"name":"Nuclear Science and Technology","volume":null,"pages":null},"PeriodicalIF":0.0,"publicationDate":"2022-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"80404923","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
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