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Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method 用混合非连续伽勒金方法求解中子输运方程的广义积分法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-18 DOI: 10.1080/00295639.2024.2394732
Wei Xiao, Xiaojing Liu, Jianhua Zu, Xiang Chai, Hui He, Tengfei Zhang
{"title":"Generalized Integral Method for Solving the Neutron Transport Equation with the Hybridized Discontinuous Galerkin Method","authors":"Wei Xiao, Xiaojing Liu, Jianhua Zu, Xiang Chai, Hui He, Tengfei Zhang","doi":"10.1080/00295639.2024.2394732","DOIUrl":"https://doi.org/10.1080/00295639.2024.2394732","url":null,"abstract":"Accurate modeling of the neutron transport equation (NTE) with anisotropic scattering is crucial to the understanding of neutron interactions within various mediums. The primary challenges in this ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-18","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267393","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 235U 外镉中子诱发 235U 裂变的中子后质量产率分布
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-17 DOI: 10.1080/00295639.2024.2372514
H. Naik, S. P. Dange, R. J. Singh, W. Jang
{"title":"Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron-Induced Fission of 235U","authors":"H. Naik, S. P. Dange, R. J. Singh, W. Jang","doi":"10.1080/00295639.2024.2372514","DOIUrl":"https://doi.org/10.1080/00295639.2024.2372514","url":null,"abstract":"Cumulative and independent yields of various fission products within the mass ranges of 78 to 117 and 123 to 155 have been measured in the epi-cadmium reactor neutron-induced fission of 235U by usi...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-17","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267392","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
An Open-Source Coupling for Depletion During Fuel Cycle Modeling 用于燃料循环建模期间损耗的开源耦合器
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-12 DOI: 10.1080/00295639.2024.2393940
Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk
{"title":"An Open-Source Coupling for Depletion During Fuel Cycle Modeling","authors":"Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk","doi":"10.1080/00295639.2024.2393940","DOIUrl":"https://doi.org/10.1080/00295639.2024.2393940","url":null,"abstract":"Fuel depletion is an important aspect of fuel cycle modeling, allowing a user to account for how loaded fuel compositions affect in-core and spent fuel compositions and their related fuel cycle met...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188933","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Development of Target Holder for the First Experiment on an Alternative Route for 64Cu Radioisotope Production by Secondary Neutron Irradiation of a 64ZnO Target 为通过二次中子辐照 64ZnO 靶件生产 64Cu 放射性同位素的替代途径的首次实验开发靶架
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-12 DOI: 10.1080/00295639.2024.2392070
Imam Kambali, Angga Dwi Saputra, Marlina Marlina, Isdandy Rezki Febrianto, Ihwanul Aziz, Wira Y Rahman, Kristedjo Kurnianto, Rasito Tursinah, Rien Ritawidya, Ratna Dini Haryuni, Parwanto Parwanto, Rajiman Rajiman, Nur Huda, Kartika Fajarwati
{"title":"Development of Target Holder for the First Experiment on an Alternative Route for 64Cu Radioisotope Production by Secondary Neutron Irradiation of a 64ZnO Target","authors":"Imam Kambali, Angga Dwi Saputra, Marlina Marlina, Isdandy Rezki Febrianto, Ihwanul Aziz, Wira Y Rahman, Kristedjo Kurnianto, Rasito Tursinah, Rien Ritawidya, Ratna Dini Haryuni, Parwanto Parwanto, Rajiman Rajiman, Nur Huda, Kartika Fajarwati","doi":"10.1080/00295639.2024.2392070","DOIUrl":"https://doi.org/10.1080/00295639.2024.2392070","url":null,"abstract":"The target holder, as part of the target system for cyclotron-based radioisotope production, plays a crucial role in successful radioisotope production. The target holder has to be designed and dev...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267394","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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 “Consistent” Quasidiffusion Method for Solving Particle Transport Problems 解决粒子传输问题的 "一致 "准扩散方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-12 DOI: 10.1080/00295639.2024.2392942
Edward W. Larsen, Tomás M. Paganin, Richard Vasques
{"title":"A “Consistent” Quasidiffusion Method for Solving Particle Transport Problems","authors":"Edward W. Larsen, Tomás M. Paganin, Richard Vasques","doi":"10.1080/00295639.2024.2392942","DOIUrl":"https://doi.org/10.1080/00295639.2024.2392942","url":null,"abstract":"The quasidiffusion (QD) method is an established and efficient iterative technique for solving particle transport problems. Each QD iteration consists of a high-order SN sweep, followed by a low-or...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188932","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Conceptual Design of a Thermal–to-14-MeV Neutron Conversion Device for Use in the Advanced Test Reactor 用于先进试验反应堆的热-14-兆电子伏中子转换装置的概念设计
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-05 DOI: 10.1080/00295639.2024.2387967
Nicolas P. Martin, Andrew J. Bascom, Jason V. Brookman, Nicolas E. Woolstenhulme
{"title":"Conceptual Design of a Thermal–to-14-MeV Neutron Conversion Device for Use in the Advanced Test Reactor","authors":"Nicolas P. Martin, Andrew J. Bascom, Jason V. Brookman, Nicolas E. Woolstenhulme","doi":"10.1080/00295639.2024.2387967","DOIUrl":"https://doi.org/10.1080/00295639.2024.2387967","url":null,"abstract":"This paper details the conceptual design of a thermal–to–14-MeV neutron converter consisting of a mixture of lithium and deuterium in a blanket material. Such a device operates a two-step reaction,...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-05","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267395","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations 水平和倾斜向上方向气泡流的一维漂移通量分析
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-09-04 DOI: 10.1080/00295639.2024.2385777
Drew Ryan, Seungjin Kim
{"title":"One-Dimensional Drift Flux Analysis of Bubbly Flows in Horizontal and Inclined-Upward Orientations","authors":"Drew Ryan, Seungjin Kim","doi":"10.1080/00295639.2024.2385777","DOIUrl":"https://doi.org/10.1080/00295639.2024.2385777","url":null,"abstract":"Void fraction and relative velocity between phases are parameters of key importance when analyzing two-phase flow systems. The drift flux model is a simple, yet robust, method of predicting these p...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-09-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142267397","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel 使用小于 10%浓缩二氧化铀燃料的先进高温钠冷热堆
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-30 DOI: 10.1080/00295639.2024.2381387
Gilles Youinou
{"title":"Advanced High-Temperature Sodium-Cooled Thermal Reactors Using Less Than 10% Enriched UO2 Fuel","authors":"Gilles Youinou","doi":"10.1080/00295639.2024.2381387","DOIUrl":"https://doi.org/10.1080/00295639.2024.2381387","url":null,"abstract":"This paper presents a 1200-MW(thermal) advanced sodium-cooled thermal reactor concept that uses online refueling of 3.5% to 9.95% enriched UO2 fuel pin bundles; uses either graphite or beryllium ox...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188934","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Preliminary Verification of Key Physical Models in Oxide Fuel Performance Analysis Code FEATURE Based on COMSOL 基于 COMSOL 的氧化物燃料性能分析代码 FEATURE 中关键物理模型的初步验证
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-30 DOI: 10.1080/00295639.2024.2384225
Rui Yu, Guan Wang, Wei Jiang, Yanlei Zhu, Changping Qin, Long Gu
{"title":"Preliminary Verification of Key Physical Models in Oxide Fuel Performance Analysis Code FEATURE Based on COMSOL","authors":"Rui Yu, Guan Wang, Wei Jiang, Yanlei Zhu, Changping Qin, Long Gu","doi":"10.1080/00295639.2024.2384225","DOIUrl":"https://doi.org/10.1080/00295639.2024.2384225","url":null,"abstract":"Nuclear performance analysis is of great significance for fuel design optimization and the safe operation of a reactor. Considering the design requirements of the China initiative Accelerator Drive...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-30","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188937","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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
Development, Construction, and Operation of the Agile Non-nuclear Microreactor Experimental Test Bed (MAGNET) and Helium Component Test Facility (He-CTF) 敏捷非核微反应器实验台（MAGNET）和氦组件测试设施（He-CTF）的开发、建设和运行
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-28 DOI: 10.1080/00295639.2024.2384218
Terry J. Morton, Michael McKellar, Piyush Sabharwall, Shaleena Jaison
{"title":"Development, Construction, and Operation of the Agile Non-nuclear Microreactor Experimental Test Bed (MAGNET) and Helium Component Test Facility (He-CTF)","authors":"Terry J. Morton, Michael McKellar, Piyush Sabharwall, Shaleena Jaison","doi":"10.1080/00295639.2024.2384218","DOIUrl":"https://doi.org/10.1080/00295639.2024.2384218","url":null,"abstract":"Idaho National Laboratory and the National Reactor Innovation Center (NRIC) constructed the Microreactor Agile Non-nuclear Experimental Test bed (MAGNET) to reduce uncertainty and risk for microrea...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188935","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":3,"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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