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Development of Obligation Tracking System for Internationally Controlled Items in Accordance with Bilateral Nuclear Cooperation Agreements 根据双边核合作协定开发国际管制物品义务跟踪系统
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-11 DOI: 10.1080/00295450.2024.2325742
Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi
{"title":"Development of Obligation Tracking System for Internationally Controlled Items in Accordance with Bilateral Nuclear Cooperation Agreements","authors":"Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi","doi":"10.1080/00295450.2024.2325742","DOIUrl":"https://doi.org/10.1080/00295450.2024.2325742","url":null,"abstract":"A Bilateral Nuclear Cooperation Agreement serves as a means to promote effective and universal cooperation while simultaneously guaranteeing overall nuclear nonproliferation. This agreement is lega...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"206 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570312","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety 核安全被动安全壳冷却系统中 ATHLET 系统代码的修正蒸发模型
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-08 DOI: 10.1080/00295450.2024.2319933
Michel Haag, Iurii Dolganov, Stephan Leyer
{"title":"Modified Evaporation Model for ATHLET System Code in a Passive Containment Cooling System for Nuclear Safety","authors":"Michel Haag, Iurii Dolganov, Stephan Leyer","doi":"10.1080/00295450.2024.2319933","DOIUrl":"https://doi.org/10.1080/00295450.2024.2319933","url":null,"abstract":"The presented work deals with the improvement of the evaporation model of the ATHLET (Analysis of Thermal and Hydraulics of Leaks and Transients) system code to be applied to a passive containment ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"92 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570287","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool 使用 MCNP-ORIGEN 激活自动化工具进行延迟加热计算
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-08 DOI: 10.1080/00295450.2024.2319922
Roberto E. Fairhurst-Agosta, Tomasz Kozlowski
{"title":"Delayed Heating Calculations Using the MCNP-ORIGEN Activation Automation Tool","authors":"Roberto E. Fairhurst-Agosta, Tomasz Kozlowski","doi":"10.1080/00295450.2024.2319922","DOIUrl":"https://doi.org/10.1080/00295450.2024.2319922","url":null,"abstract":"An accurate assessment of the deposited energy across a reactor geometry allows for a better determination of the heat removal requirements and ensures effective cooling after shutdown. This work d...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"50 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570305","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
A Blowdown Critical Heat Flux Experimental Vehicle 吹扫临界热通量实验飞行器
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-08 DOI: 10.1080/00295450.2024.2309601
Musa Moussaoui, Wade Marcum
{"title":"A Blowdown Critical Heat Flux Experimental Vehicle","authors":"Musa Moussaoui, Wade Marcum","doi":"10.1080/00295450.2024.2309601","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309601","url":null,"abstract":"In the most challenging nuclear power plant accidents, transient critical heat flux (CHF) is a primary phenomenon that drives peak cladding temperature, and ultimately, fuel failure. It has not yet...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"50 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-08","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570471","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations 稳态运行期间 Es-Salam 反应堆燃料棒的 PCMI 不确定性和敏感性分析
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-05 DOI: 10.1080/00295450.2024.2323226
Djillali Saad, Mohamed Elhadi Boulheouchat, Mohamed Bouaouina, Tahar Zidi
{"title":"PCMI Uncertainty and Sensitivity Analysis of Es-Salam Reactor Fuel Rods During Steady-State Operations","authors":"Djillali Saad, Mohamed Elhadi Boulheouchat, Mohamed Bouaouina, Tahar Zidi","doi":"10.1080/00295450.2024.2323226","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323226","url":null,"abstract":"Nuclear safety relies heavily on the quality of the results of numerical simulation codes. Among the various components of the simulation of the installation are the pellet-cladding mechanical inte...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"120 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570288","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Evaluation of Reaction Rate Distribution for Shielding Region in the Prototype Fast Reactor Monju 原型快堆 "孟州 "屏蔽区反应速率分布评估
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-05 DOI: 10.1080/00295450.2024.2323228
Tetsuya Mouri, Taira Hazama, Hiroki Katagiri, Kazuya Ohgama
{"title":"Evaluation of Reaction Rate Distribution for Shielding Region in the Prototype Fast Reactor Monju","authors":"Tetsuya Mouri, Taira Hazama, Hiroki Katagiri, Kazuya Ohgama","doi":"10.1080/00295450.2024.2323228","DOIUrl":"https://doi.org/10.1080/00295450.2024.2323228","url":null,"abstract":"The reliability and usefulness of the reaction rate distribution data measured in the prototype fast breeder reactor Monju were examined through a comparison with a calculation using JENDL-4.0, mai...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"37 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570294","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Effect of Cooling Pump Transient Power Supply on ETRR-2 Safety Parameters 冷却泵瞬态电源对 ETRR-2 安全参数的影响
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-04 DOI: 10.1080/00295450.2024.2325739
Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly
{"title":"Effect of Cooling Pump Transient Power Supply on ETRR-2 Safety Parameters","authors":"Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly","doi":"10.1080/00295450.2024.2325739","DOIUrl":"https://doi.org/10.1080/00295450.2024.2325739","url":null,"abstract":"The primary goals of the engineering design for nuclear reactors involve safeguarding the integrity of the reactor core. Preserving the integrity of the cladding material is especially crucial, as ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"28 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570470","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Reconstruction of γ Dose Rate Field and Algorithm Validation Based on Inverse Distance Weight Interpolation 基于反距离加权插值的 γ 剂量率场重建与算法验证
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-03 DOI: 10.1080/00295450.2024.2312026
Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song
{"title":"Reconstruction of γ Dose Rate Field and Algorithm Validation Based on Inverse Distance Weight Interpolation","authors":"Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song","doi":"10.1080/00295450.2024.2312026","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312026","url":null,"abstract":"The inverse distance weighting (IDW) interpolation algorithm is used to reconstruct the γ radiation field. The traditional IDW interpolation algorithm is improved. The power exponent of distance P ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"52 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-03","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570826","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Optimization of Elliptical U-tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method 基于田口方法和 CFD 方法优化用于喷雾冷却的椭圆 U 型管换热器 (EUTHE)
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-02 DOI: 10.1080/00295450.2024.2311978
Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang
{"title":"Optimization of Elliptical U-tube Heat Exchanger (EUTHE) for Spray Cooling Based on the Taguchi and CFD Method","authors":"Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang","doi":"10.1080/00295450.2024.2311978","DOIUrl":"https://doi.org/10.1080/00295450.2024.2311978","url":null,"abstract":"The elliptical U-tube heat exchanger (EUTHE) is widely used in various cooling systems of nuclear engineering for its simple geometrical structure and small space cost. In this paper, a two-phase f...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"24 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570303","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
引用次数: 0
Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3 添加 Sm2O3 增强 TeO2-Li2O-ZnO-Nb2O5 玻璃体系的伽马射线和中子屏蔽性能
IF 1.5 4区 工程技术
Nuclear Technology Pub Date : 2024-04-02 DOI: 10.1080/00295450.2023.2294603
Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao
{"title":"Enhancement of Gamma-Ray and Neutron Shielding Properties of TeO2-Li2O-ZnO-Nb2O5 Glass System with the Addition of Sm2O3","authors":"Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao","doi":"10.1080/00295450.2023.2294603","DOIUrl":"https://doi.org/10.1080/00295450.2023.2294603","url":null,"abstract":"Radiation shielding glass is widely used, as it protects people from ionizing radiation while allowing for the observation of irradiated areas. However, the performance of even the best-performing ...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"43 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570291","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":4,"RegionCategory":"工程技术","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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