知识中心主页
文献服务
文献资源
外文期刊
外文会议
专业机构
智能制造
高级检索
版权声明
使用帮助
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
2016~2023
全部
2016
2017
2018
2019
2020
2021
2022
2023
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
1
2
3
制造业外文文献服务平台