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United States Nuclear Regulatory Commission fuel-damage criteria
(Issue 170)
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Engineering
Materials science
Materials science bibliography
2026-10-20
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www.nrc.gov/sr0933/section-3-new-generic-issues/issue-170-fuel-damage-criteria-high-burnup-fuel
NRC discussion of high-
burnup
fuel damage and the established peak-cladding-
temperature
and
oxidation
criteria.
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Materials science bibliography
Materials science
Engineering
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Past exam of the MPhil in nuclear energy course of the University of Cambridge
/
2021
/
Module NE3
/
1
/
b
/
Solution
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