Pub Date : 2024-04-02DOI: 10.1080/00295450.2024.2312023
Gongbo Chen, Naibin Jiang
The heat exchange tubes in the steam generator are susceptible to vibration caused by fluid flow, which can lead to damage to both the tubes and their support structures due to collisions. To enhan...
{"title":"A Semi-Analytical Prediction Model for Fluid-Elastic Instability of a Normal Triangular Tube Array Under Transverse Flow Excitation","authors":"Gongbo Chen, Naibin Jiang","doi":"10.1080/00295450.2024.2312023","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312023","url":null,"abstract":"The heat exchange tubes in the steam generator are susceptible to vibration caused by fluid flow, which can lead to damage to both the tubes and their support structures due to collisions. To enhan...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"26 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570724","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 : 2024-04-01DOI: 10.1080/00295450.2024.2312022
Ryan J. Hoover, Kenji Shimada
Transient mitigation for nuclear power plants is essential for safe operation. The fourth industrial revolution brings with it the potential for data-based predictive maintenance and identifying re...
{"title":"Determination of Gain Scheduling Parameters for Loss of a Feedwater Pump Transient Mitigation Using Neural Networks","authors":"Ryan J. Hoover, Kenji Shimada","doi":"10.1080/00295450.2024.2312022","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312022","url":null,"abstract":"Transient mitigation for nuclear power plants is essential for safe operation. The fourth industrial revolution brings with it the potential for data-based predictive maintenance and identifying re...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"28 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570304","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}
Simulation of a station blackout (SBO) scenario was carried out for an open pool–type nuclear research reactor. The SBO transient was analyzed using the best estimate (BE) thermal-hydraulic code RE...
{"title":"Best Estimate Plus Uncertainty Analysis of Station Blackout Transient in Pool-Type Research Reactor","authors":"Amitanshu Mishra, Paban Kumar Guchhait, Samiran Sengupta","doi":"10.1080/00295450.2024.2304915","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304915","url":null,"abstract":"Simulation of a station blackout (SBO) scenario was carried out for an open pool–type nuclear research reactor. The SBO transient was analyzed using the best estimate (BE) thermal-hydraulic code RE...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"206 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570825","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 : 2024-04-01DOI: 10.1080/00295450.2024.2312019
Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight
In aluminum-clad spent nuclear fuels, an (oxy)hydroxide layer on the surface of the cladding hosts chemisorbed water formed during reactor and post-discharge exposure to water. Any residual water i...
{"title":"Drying and Analysis of Aluminum (Oxy)hydroxide Films for Dry Storage of Aluminum-Clad Spent Nuclear Fuels","authors":"Robert J. Demuth, Anna L. D’Entremont, Rebecca Smith, Robert L. Sindelar, Travis W. Knight","doi":"10.1080/00295450.2024.2312019","DOIUrl":"https://doi.org/10.1080/00295450.2024.2312019","url":null,"abstract":"In aluminum-clad spent nuclear fuels, an (oxy)hydroxide layer on the surface of the cladding hosts chemisorbed water formed during reactor and post-discharge exposure to water. Any residual water i...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"57 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-04-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140570297","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 : 2024-03-27DOI: 10.1080/00295450.2024.2309070
Shekhar Kumar
The density of aqueous solutions containing actinide nitrates is an important parameter for process design, equipment design, and remote operation/control. It is also significantly important for th...
含有锕系元素硝酸盐的水溶液的密度是工艺设计、设备设计和远程操作/控制的重要参数。它对于...
{"title":"Estimation of Densities of Aqueous Actinide Solutions Ranging from Pure Water to Hydrated Crystals","authors":"Shekhar Kumar","doi":"10.1080/00295450.2024.2309070","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309070","url":null,"abstract":"The density of aqueous solutions containing actinide nitrates is an important parameter for process design, equipment design, and remote operation/control. It is also significantly important for th...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"109 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-27","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316231","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 : 2024-03-26DOI: 10.1080/00295450.2024.2304931
Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva
According to a recently proposed nuclear safeguards technique, monitoring the power-normalized, ex-core neutron detection rate over time could be used to detect undeclared changes to the fissile co...
{"title":"Simulation of Neutron Leakage Variations at Fuel Substitution in a Small Modular Reactor and Implications for Unattended Safeguards Monitoring","authors":"Markus Preston, Erik Branger, Sophie Grape, Olena Khotiaintseva","doi":"10.1080/00295450.2024.2304931","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304931","url":null,"abstract":"According to a recently proposed nuclear safeguards technique, monitoring the power-normalized, ex-core neutron detection rate over time could be used to detect undeclared changes to the fissile co...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"210 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316061","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 : 2024-03-26DOI: 10.1080/00295450.2024.2304910
Teklu Hadgu, Edward Matteo, Thomas Dewers
Disposal of commercial spent nuclear fuel in a geologic repository is studied. In situ heater experiments in underground research laboratories provide a realistic representation of subsurface behav...
{"title":"Model Development for Thermal-Hydrology Simulations of a Full-Scale Heater Experiment in Opalinus Clay","authors":"Teklu Hadgu, Edward Matteo, Thomas Dewers","doi":"10.1080/00295450.2024.2304910","DOIUrl":"https://doi.org/10.1080/00295450.2024.2304910","url":null,"abstract":"Disposal of commercial spent nuclear fuel in a geologic repository is studied. In situ heater experiments in underground research laboratories provide a realistic representation of subsurface behav...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"38 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316227","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 : 2024-03-25DOI: 10.1080/00295450.2024.2309599
Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung
There are numerous computational programs available for fire influence analysis; however, currently, there is no computational program in Korea specifically designed to aid Authority Having Jurisdi...
用于火灾影响分析的计算程序不胜枚举，但目前韩国还没有专门用于协助管理局进行火灾影响分析的计算程序。
{"title":"Mobile Application Development Plan for Fire Influence Analysis Using Algebraic Models","authors":"Yongjae Kim, Seokhyeon Han, Seungjun Oh, Samwon Chung","doi":"10.1080/00295450.2024.2309599","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309599","url":null,"abstract":"There are numerous computational programs available for fire influence analysis; however, currently, there is no computational program in Korea specifically designed to aid Authority Having Jurisdi...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"34 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316135","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 : 2024-03-25DOI: 10.1080/00295450.2024.2309080
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
The utilization of a grid spacer with vane is a significant component within reactor fuel channels. The presence of the vane has a notable impact on the mixing of flow and the enhancement of heat t...
带叶片的栅格隔板是反应堆燃料通道的重要组成部分。叶片的存在对流动的混合和热量的提高有显著的影响。
{"title":"Numerical Analysis of Effects of Vane Deflection Angle on Flow-Thermal Characteristics in a Fuel Rod Assembly","authors":"Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma","doi":"10.1080/00295450.2024.2309080","DOIUrl":"https://doi.org/10.1080/00295450.2024.2309080","url":null,"abstract":"The utilization of a grid spacer with vane is a significant component within reactor fuel channels. The presence of the vane has a notable impact on the mixing of flow and the enhancement of heat t...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"14 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140316057","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 : 2024-03-25DOI: 10.1080/00295450.2024.2311977
Nora Nassiri-Mofakham, Mojtaba Kakaei
Waste from resource extraction industries contains uranium and thorium decay chain radionuclides. One important radiological impact of these wastes is the release of radon into the atmosphere. Ther...
{"title":"Experimental Model to Study Characteristics of Radon Cover in Waste Landfills","authors":"Nora Nassiri-Mofakham, Mojtaba Kakaei","doi":"10.1080/00295450.2024.2311977","DOIUrl":"https://doi.org/10.1080/00295450.2024.2311977","url":null,"abstract":"Waste from resource extraction industries contains uranium and thorium decay chain radionuclides. One important radiological impact of these wastes is the release of radon into the atmosphere. Ther...","PeriodicalId":19402,"journal":{"name":"Nuclear Technology","volume":"252 1","pages":""},"PeriodicalIF":1.5,"publicationDate":"2024-03-25","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"140302541","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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