SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes

Published 2020 View Full Article

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Title
SCIANTIX: A new open source multi-scale code for fission gas behaviour modelling designed for nuclear fuel performance codes
Authors
Keywords
Multi-scale material modelling, Fission gas behaviour, Fuel performance code, Nuclear fuel
Journal
JOURNAL OF NUCLEAR MATERIALS
Volume 532, Issue -, Pages 152042
Publisher
Elsevier BV
Online
2020-02-07
DOI
10.1016/j.jnucmat.2020.152042

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