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
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Title
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
Authors
Keywords
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Journal
Nuclear Science and Techniques
Volume 33, Issue 12, Pages -
Publisher
Springer Science and Business Media LLC
Online
2022-12-16
DOI
10.1007/s41365-022-01141-8
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