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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

Crossref DOI link: https://doi.org/10.1007/s41365-022-01141-8

Published Online: 2022-12-16

Published Print: 2022-12

Update policy: https://doi.org/10.1007/springer_crossmark_policy

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