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 ...
{"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}
Pub Date : 2024-09-17DOI: 10.1080/00295639.2024.2372514
H. Naik, S. P. Dange, R. J. Singh, W. Jang
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...
{"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}
Pub Date : 2024-09-12DOI: 10.1080/00295639.2024.2393940
Amanda M. Bachmann, Oleksandr Yardas, Madicken Munk
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...
{"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}
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...
{"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}
Pub Date : 2024-09-12DOI: 10.1080/00295639.2024.2392942
Edward W. Larsen, Tomás M. Paganin, Richard Vasques
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...
准扩散（QD）方法是一种成熟、高效的迭代技术，用于解决粒子传输问题。每次 QD 迭代包括一次高阶 SN 扫描，然后是一次低阶或高阶 SN 扫描。
{"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}
Pub Date : 2024-09-05DOI: 10.1080/00295639.2024.2387967
Nicolas P. Martin, Andrew J. Bascom, Jason V. Brookman, Nicolas E. Woolstenhulme
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,...
{"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}
Pub Date : 2024-09-04DOI: 10.1080/00295639.2024.2385777
Drew Ryan, Seungjin Kim
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...
{"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}
Pub Date : 2024-08-30DOI: 10.1080/00295639.2024.2381387
Gilles Youinou
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...
{"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}
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...
{"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}
Pub Date : 2024-08-28DOI: 10.1080/00295639.2024.2384218
Terry J. Morton, Michael McKellar, Piyush Sabharwall, Shaleena Jaison
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...
{"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}
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