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Nuclear Science and Engineering最新文献

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Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation 蒙特卡洛计算中统计几何法对 TRISO 燃料涂层的简化处理
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-28 DOI: 10.1080/00295639.2024.2384236
Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Kazuya Yamaji, Hiroki Koike, Koji Asano
{"title":"Simplified Treatment of Coating Layers in TRISO Fuel in Statistical Geometry Method in Monte Carlo Calculation","authors":"Akio Yamamoto, Tomohiro Endo, Satoshi Takeda, Kazuya Yamaji, Hiroki Koike, Koji Asano","doi":"10.1080/00295639.2024.2384236","DOIUrl":"https://doi.org/10.1080/00295639.2024.2384236","url":null,"abstract":"An improved sampling method for flight distance is proposed for Monte Carlo analysis of TRISO fuel particles using the statistical geometry (STG) method. The statistically uniform distribution of f...","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":"142267396","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 Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor 利用区域偶极性不连续因子开发多组蒙特卡洛中子输运方法
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-26 DOI: 10.1080/00295639.2024.2383102
Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto
{"title":"Development of Multigroup Monte Carlo Neutron Transport Method with Regionwise Even-Parity Discontinuity Factor","authors":"Yoshiki Oshima, Tomohiro Endo, Akio Yamamoto","doi":"10.1080/00295639.2024.2383102","DOIUrl":"https://doi.org/10.1080/00295639.2024.2383102","url":null,"abstract":"The multigroup Monte Carlo (MC) neutron transport method with a regionwise even-parity discontinuity factor (REPDF), i.e. the discontinuity factor (DF)–MC method, is developed with the aim to provi...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-26","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188936","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
Optimizing Hydride Stability in U-ZrHx Nuclear Fuel: The “Goldilocks Radius” 优化 U-ZrHx 核燃料中的氢化物稳定性："黄金半径
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-22 DOI: 10.1080/00295639.2024.2383111
Jordan A. Evans, Carlo Parisi
{"title":"Optimizing Hydride Stability in U-ZrHx Nuclear Fuel: The “Goldilocks Radius”","authors":"Jordan A. Evans, Carlo Parisi","doi":"10.1080/00295639.2024.2383111","DOIUrl":"https://doi.org/10.1080/00295639.2024.2383111","url":null,"abstract":"Nuclear-powered microreactors show great promise for opening new nuclear energy markets due to the flexibility offered by their rapid/streamlined in-factory fabrication, transportability, and self-...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188939","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
Vaporization in Liquid-Core Nuclear Thermal Rockets 液芯核热火箭中的汽化现象
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-22 DOI: 10.1080/00295639.2024.2380633
Dakota Santana, D. Keith Hollingsworth
{"title":"Vaporization in Liquid-Core Nuclear Thermal Rockets","authors":"Dakota Santana, D. Keith Hollingsworth","doi":"10.1080/00295639.2024.2380633","DOIUrl":"https://doi.org/10.1080/00295639.2024.2380633","url":null,"abstract":"This work provides an overview of vaporization phenomena in liquid-core nuclear thermal rockets to aid in unifying modeling assumptions by characterizing the impact of vaporization. Historical vari...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-22","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188938","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
ARIANT Assessments for CANDU Analysis Using RD-14M Experiments 利用 RD-14M 试验对 CANDU 分析进行 ARIANT 评估
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-19 DOI: 10.1080/00295639.2024.2380628
John Cui, Geoffrey Waddington, Shujun Wang, Songyu Liu
{"title":"ARIANT Assessments for CANDU Analysis Using RD-14M Experiments","authors":"John Cui, Geoffrey Waddington, Shujun Wang, Songyu Liu","doi":"10.1080/00295639.2024.2380628","DOIUrl":"https://doi.org/10.1080/00295639.2024.2380628","url":null,"abstract":"ARIANT (AlgoRIthm for Analysis of Network Thermalhydraulics) is a Canadian Nuclear Laboratories system thermal-hydraulic code for the modeling and analysis of two-phase flow and heat transfer for p...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-19","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142188940","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
Effect of Angular Momentum–Dependent Transparency on the Neutron-Nucleus Cross Section 角动量相关透明度对中子-核截面的影响
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-15 DOI: 10.1080/00295639.2024.2381397
A. M. Alshamy, M. M. Musthafa
{"title":"Effect of Angular Momentum–Dependent Transparency on the Neutron-Nucleus Cross Section","authors":"A. M. Alshamy, M. M. Musthafa","doi":"10.1080/00295639.2024.2381397","DOIUrl":"https://doi.org/10.1080/00295639.2024.2381397","url":null,"abstract":"We study the effect of the angular momentum dependence of the optical potential transparency on the neutron-nucleus cross section. In this work, we derive a functional form of the neutron-nucleus c...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142189069","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
Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident 基于堵塞事故下钠冷快堆燃料组件的仿真分析
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-15 DOI: 10.1080/00295639.2024.2381391
Zenghao Dong, Jianquan Liu, Xinyi Niu, Lihan Hai, Wenlong Zhou
{"title":"Simulation Analysis Based on Sodium-Cooled Fast Reactor Fuel Assembly Under Blockage Accident","authors":"Zenghao Dong, Jianquan Liu, Xinyi Niu, Lihan Hai, Wenlong Zhou","doi":"10.1080/00295639.2024.2381391","DOIUrl":"https://doi.org/10.1080/00295639.2024.2381391","url":null,"abstract":"This paper employs computational fluid dynamics to investigate the fuel assemblies within a sodium-cooled fast neutron reactor. To begin with, we developed computational models for seven wire space...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142189070","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
Effect of Bi2O3/WO3 on Improving the Ability of Polyepoxide-Based Composites to Attenuate Gamma Rays Bi2O3/WO3 对提高聚氧化物基复合材料衰减伽马射线能力的影响
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-15 DOI: 10.1080/00295639.2024.2383105
Mohamed Y. Hanfi, Mohammad W. Marashdeh, Sitah Alanazi, Mamduh J. Aljaafreh, Karem A. Mahmoud
{"title":"Effect of Bi2O3/WO3 on Improving the Ability of Polyepoxide-Based Composites to Attenuate Gamma Rays","authors":"Mohamed Y. Hanfi, Mohammad W. Marashdeh, Sitah Alanazi, Mamduh J. Aljaafreh, Karem A. Mahmoud","doi":"10.1080/00295639.2024.2383105","DOIUrl":"https://doi.org/10.1080/00295639.2024.2383105","url":null,"abstract":"This work aims to prepare a new series of polyepoxide resins reinforced with a mixture of WO3 and Bi2O3 compounds. The effect of replacing WO3 with by Bi2O3 on the radiation shielding parameters wa...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142189068","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
Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + 7Li Reaction 背衬对低能量准单能 p + 7Li 反应中子谱的影响
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-15 DOI: 10.1080/00295639.2024.2380636
H. Kumawat
{"title":"Effect of Backing on Neutron Spectra for Low-Energy Quasi-Monoenergetic p + 7Li Reaction","authors":"H. Kumawat","doi":"10.1080/00295639.2024.2380636","DOIUrl":"https://doi.org/10.1080/00295639.2024.2380636","url":null,"abstract":"The Monte Carlo Nucleon Transport (MONC) code for nucleon transport is extended for below 20-MeV proton transport using the ENDF and EXFOR databases. It is used to simulate the p + 7Li reaction up ...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142189066","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 General Formulation of the Resonance Spectrum Expansion Self-Shielding Method 共振谱扩展自屏蔽法的一般公式
IF 1.2 3区 工程技术
Nuclear Science and Engineering Pub Date : 2024-08-12 DOI: 10.1080/00295639.2024.2375908
Alain Hébert
{"title":"A General Formulation of the Resonance Spectrum Expansion Self-Shielding Method","authors":"Alain Hébert","doi":"10.1080/00295639.2024.2375908","DOIUrl":"https://doi.org/10.1080/00295639.2024.2375908","url":null,"abstract":"The resonance spectrum expansion (RSE) self-shielding method was recently proposed by Nagoya and Osaka universities as a powerful alternative to existing approaches. First investigations of the RSE...","PeriodicalId":19436,"journal":{"name":"Nuclear Science and Engineering","volume":null,"pages":null},"PeriodicalIF":1.2,"publicationDate":"2024-08-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"142189067","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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