中国机械工程学会生产工程分会知识服务平台

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2016~2023



全部

2016 2017 2018 2019 2020 2021
2022 2023

2016, vol.2, no.1 2016, vol.2, no.2 2016, vol.2, no.3 2016, vol.2, no.4

题名作者出版年年卷期
Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant ChannelEric C. Forrest; Sarah M. Don; Lin-Wen Hu; Jacopo Buongiorno; Thomas J. McKrell20162016, vol.2, no.2
The Development of Candling Module Code in Module In-vessel Degraded Analysis Code MIDAC and the Relevant Calculation for CPR1000 During Large-Break LOCAJun Wang; Yuqiao Fan; Yapei Zhang; Xinghe Ni; Wenxi Tian; Michael L. Corradini; Guanghui Su; Suizheng Qiu20162016, vol.2, no.2
Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle GeometryIkuo Kinoshita; Toshihide Torige; Minoru Yamada20162016, vol.2, no.2
Mitigating the Stress Corrosion Cracking of Zircaloy-4 Fuel Sheathing: Siloxane Coatings RevisitedGraham A. Ferrier; Mohsen Farahani; Joseph Metzler; Paul K. Chan; Emily C. Corcoran20162016, vol.2, no.2
Supercritical Oxidation of Boiler Tube MaterialsSatu Tuurna; Sanni Yli-Olli; Sami Penttila; Pertti Auerkari; Xiao Huang20162016, vol.2, no.2
Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In-Core Components of a Gen-IV SCWRRobert J. Klassen; Heygaan Rajakumar20162016, vol.2, no.2
Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr-, Ni-Cr-, and Fe-Cr-Based AlloysO. S. Bakai; V. M. Boriskin; A. M. Dovbnya; S. V. Dyuldya; D. A. Guzonas20162016, vol.2, no.2
Oxidation Behavior of Austenitic Stainless Steel 316L and 310S in Air and Supercritical WaterMajid Nezakat; Hamed Akhiani; Sami Penttila; Jerzy Szpunar20162016, vol.2, no.2
Microstructural Effects on the Oxidation Behavior of Alloy 800HT in Supercritical WaterHamed Akhiani; Majid Nezakat; Sami Penttila; Jerzy Szpunar20162016, vol.2, no.2
Fission Product Release Under Supercritical Water-Cooled Reactor ConditionsD. Guzonas; L. Qiu; S. Livingstone; S. Rousseau20162016, vol.2, no.2
123