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期刊


ISSN2332-8983
刊名Journal of nuclear engineering and radiation science
参考译名核工程和辐射科学杂志
收藏年代2016～2024



全部

2016 2017 2018 2019 2020 2021
2022 2023 2024

2024, vol.10, no.1 2024, vol.10, no.2 2024, vol.10, no.3 2024, vol.10, no.4

题名作者出版年年卷期
Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data LibrariesVu, Thanh Mai; Tran, Le Quang Linh; Bui, Thi Hong; Pham, Nhu Viet Ha20242024, vol.10, no.3
Public-Private Partnering in Nuclear Reactor Development-Historical Review and Implications for TodayKrahn, Steven; Sowder, Andrew20242024, vol.10, no.3
Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3Yankey, Jacob; Monreal, Marisa; Jackson, Matt; Simpson, Michael20242024, vol.10, no.3
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity DevelopmentSchulthess, Jason L.; Baird, Katelyn; Petersen, Philip; Salvato, Daniele; Ozaltun, Hakan; Hanson, William A.; Ullum, Nicholas; Giglio, Jeffrey; Cole, James I.20242024, vol.10, no.3
Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed VolumeDwijayanto, R. Andika Putra; Ardiansyah, Harun; Harto, Andang Widi20242024, vol.10, no.3
Design and Analysis of a Free-Piston Stirling Engine for Microreactor ApplicationsDoan, Phat; Chen, Minghui20242024, vol.10, no.3
Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication ConditionsLiu, Yuqi; Chen, Minghui; Che, Shuai; Burak, Adam20242024, vol.10, no.3
Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel RodsWojtaszek, Daniel T.; Bromley, Blair P.20242024, vol.10, no.3
Interactions Between Molten Sodium and Standard Pipe InsulationLabrier, Daniel; Harley, Jordan; Robbins, Morgan20242024, vol.10, no.3
An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling ConditionHe, Mingfu; Chen, Minghui20242024, vol.10, no.3
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