Multi-group neutron cross section generation capability for FRENDY nuclear data processing code

Title
Multi-group neutron cross section generation capability for FRENDY nuclear data processing code
Authors
Keywords
-
Journal
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY
Volume -, Issue -, Pages 1-19
Publisher
Informa UK Limited
Online
2021-06-15
DOI
10.1080/00223131.2021.1921631

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