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期刊
ISSN
2332-8983
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 Libraries
Vu, Thanh Mai; Tran, Le Quang Linh; Bui, Thi Hong; Pham, Nhu Viet Ha
2024
2024, vol.10, no.3
Public-Private Partnering in Nuclear Reactor Development-Historical Review and Implications for Today
Krahn, Steven; Sowder, Andrew
2024
2024, vol.10, no.3
Electrochemical Activity Measurements of UCl 3 in Molten NaCl-MgCl 2 -UCl 3
Yankey, Jacob; Monreal, Marisa; Jackson, Matt; Simpson, Michael
2024
2024, vol.10, no.3
Mechanical Properties of Irradiated U-10 wt. %Mo Alloy Degraded by Porosity Development
Schulthess, Jason L.; Baird, Katelyn; Petersen, Philip; Salvato, Daniele; Ozaltun, Hakan; Hanson, William A.; Ullum, Nicholas; Giglio, Jeffrey; Cole, James I.
2024
2024, vol.10, no.3
Verification and Geometry Optimization of a One Fluid Molten Salt Reactor With Fixed Volume
Dwijayanto, R. Andika Putra; Ardiansyah, Harun; Harto, Andang Widi
2024
2024, vol.10, no.3
Design and Analysis of a Free-Piston Stirling Engine for Microreactor Applications
Doan, Phat; Chen, Minghui
2024
2024, vol.10, no.3
Molten Salt Pump Journal-Bearings Dynamic Characteristics Under Hydrodynamic Lubrication Conditions
Liu, Yuqi; Chen, Minghui; Che, Shuai; Burak, Adam
2024
2024, vol.10, no.3
Evaluating Hydrogen-Based Moderators in High-Temperature Gas-Cooled Reactors With 5 wt.% Enriched Uranium Annular Fuel Rods
Wojtaszek, Daniel T.; Bromley, Blair P.
2024
2024, vol.10, no.3
Interactions Between Molten Sodium and Standard Pipe Insulation
Labrier, Daniel; Harley, Jordan; Robbins, Morgan
2024
2024, vol.10, no.3
An Improved Heat Flux Partitioning Model of Nucleate Boiling Under Saturated Pool Boiling Condition
He, Mingfu; Chen, Minghui
2024
2024, vol.10, no.3
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