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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
2016~2025
全部
2016
2017
2018
2019
2020
2021
2022
2023
2024
2025
2020, vol.6, no.1
2020, vol.6, no.2
2020, vol.6, no.3
2020, vol.6, no.4
题名
作者
出版年
年卷期
Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle
Kiss, Attila; Mervay, Bence
2020
2020, vol.6, no.3
Evaluation of Friction-Factor Correlations at Supercritical Water Conditions in Support of the Canadian SCWR
Nava-Dominguez, A.
2020
2020, vol.6, no.3
Special Section: Selected Papers From the Ninth International Symposium on Supercritical Water-Cooled Reactors
Leung, Laurence; Guzonas, David; Schulenberg, Thomas
2020
2020, vol.6, no.3
Study on Calculation Difference of the SCWR Core Steady-State Analysis Code
Wang, Lianjie; Yao, Lei; Yang, Ping; Lu, Di; Zhao, Wenbo
2020
2020, vol.6, no.3
General Corrosion of Chromium-Coated Zirconium- and Titanium-Based Alloys in Supercritical Water at 500 degrees C
Khumsa-Ang, K.; Edwards, M.; Rousseau, S.
2020
2020, vol.6, no.3
Research on Improved Simplified SCWR Assembly and Core Design
Lei, Yao; Bangyang, Xia; Di, Lu; Lianjie, Wang
2020
2020, vol.6, no.3
Analysis of Heat Transfer Characteristics of Canadian SCWR Fuel Assembly Concept
Nava Dominguez, A.; Rao, Y. F.; Beuthe, T.
2020
2020, vol.6, no.3
A Numerical Study of Turbulent Upward Flow of Super Critical Water in a 2 x 2 Rod Bundle With Nonuniform Heating
Liu, Bo; He, Shuisheng; Moulinec, Charles; Uribe, Juan
2020
2020, vol.6, no.3
Simulation of IAEA Reactivity Initiated Transient Benchmarks Using Reactor Dynamics Code "REDAC"
Kale, Vivek A.; Obaidurrahman, K.
2020
2020, vol.6, no.3
Investigating the Effect of Prior Distributions on Posterior Estimates of Common Cause Failure Parameters Using Bayesian Method
Shitsi, Edward; Boafo, Emmanuel K.; Ameyaw, Felix; Odoi, H. C.
2020
2020, vol.6, no.3
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