Pub Date : 2024-04-11DOI: 10.1080/00295450.2024.2325742
Mun-Young Ryu, Hyun-Jo Kim, Jin-Ha Choi
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...
双边核合作协定是促进有效和普遍合作的一种手段，同时又能保证全面的核不扩散。该协定的法律...
{"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}
Pub Date : 2024-04-08DOI: 10.1080/00295450.2024.2319933
Michel Haag, Iurii Dolganov, Stephan Leyer
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 ...
{"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}
Pub Date : 2024-04-08DOI: 10.1080/00295450.2024.2319922
Roberto E. Fairhurst-Agosta, Tomasz Kozlowski
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...
{"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}
Pub Date : 2024-04-08DOI: 10.1080/00295450.2024.2309601
Musa Moussaoui, Wade Marcum
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...
{"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}
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...
{"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}
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...
{"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}
Pub Date : 2024-04-04DOI: 10.1080/00295450.2024.2325739
Abdelfatah Abdelmaksoud, Asmaa Gamal, Ahmed R. Adly
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 ...
核反应堆工程设计的首要目标是保护反应堆堆芯的完整性。保护包壳材料的完整性尤为重要，因为...
{"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}
Pub Date : 2024-04-03DOI: 10.1080/00295450.2024.2312026
Biao Zhang, Jinjia Cao, Shuang Lin, Yingming Song
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 ...
采用反距离加权（IDW）插值算法重建 γ 辐射场。对传统的 IDW 插值算法进行了改进。距离的幂指数 P ...
{"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}
Pub Date : 2024-04-02DOI: 10.1080/00295450.2024.2311978
Binqi Hao, He Zhou, Xiaofeng Li, Zu’An Wang, Shunyang Li, Pengfei Wang
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...
椭圆 U 型管换热器（EUTHE）因其几何结构简单、空间成本小而广泛应用于核工程的各种冷却系统中。在本文中，椭圆形 U 型管热交换器是一种两相热交换器。
{"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}
Pub Date : 2024-04-02DOI: 10.1080/00295450.2023.2294603
Zhigang Li, Junfeng Zhao, Yuanjie Sun, Yi Wang, Hongtao Zhao
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 ...
{"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}
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