학술논문
Evaluating the JEFF 3.1, ENDF/B-VII.0, JENDL 3.3, and JENDL 4.0 nuclear data libraries for a small 100 MWe molten salt reactor with plutonium fuel
Document Type
Article
Author
Source
In: Nuclear Science and Techniques . (Nuclear Science and Techniques, December 2022, 33(12))
Subject
Language
English
ISSN
22103147
10018042
10018042