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2016～2025



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
Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo CodeLee, Yi-Kang20202020, vol.6, no.4
Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear AccidentYadav, Mahesh Kumar; Punetha, Maneesh; Bhanawat, Abhinav; Khandekar, Sameer; Sharma, Pavan K.20202020, vol.6, no.4
Effect of Pulsation and Acceleration of Liquid Metal Turbulent Flow Through a Horizontal Channel by Large Eddy SimulationSatish, N.; Venkatasubbaiah, K.20202020, vol.6, no.4
Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ FrameworkGalushin, Sergey; Grishchenko, Dmitry; Kudinov, Pavel20202020, vol.6, no.4
ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature ReactorsKeating, Robert B.; McKillop, Suzanne P.; Allen, Todd; Anderson, Mark20202020, vol.6, no.4
Special Section: Selected Papers from ICONE-27Riznic, Jovica; Okawa, Tomio; Arastu, Asif; Cizelj, Leon; Revankar, Shripad; Schultz, Richard20202020, vol.6, no.4
A Novel Assessment of Delayed Neutron Detector Data in CANDU ReactorsAylward, Will; Wallace, Christopher; West, Graeme; McEwan, Curtis20202020, vol.6, no.4
Validation of the Moody and Henry-Fauske Critical Flow Models in apros Against Marviken Critical Flow ExperimentsTesinsky, Milan20202020, vol.6, no.4
Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core DataSong, Jason J.; Chan, Paul K.; Bonin, Hugues W.; Pandey, Mahesh20202020, vol.6, no.4
Xenon Behavior in Molten Salt Reactor GraphitePrice, Terry J.; Chvala, Ondrej; Taylor, Zack20202020, vol.6, no.4
123



制造业外文文献服务平台