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International Analysis of LWR Rod Ejection Accident Agreement Report

OXIDATION OF Zr ALLOYS IN HIGH PRESSURE ... AND SOME RESULTS UNDER ATMOSPHERIC ... G. Hache

g ESBWR Design Control Document Tier 2

Development, Implementation, and Assessment of Specific Inverted-Annular Film-Boiling

International Agreement Report Kalinin VVER-1000 Nuclear Power Station Unit 1 PRA (Beta Project)

Pre-Application Safety Assessment Report related to the Advanced CANDU Reactor 700 MWe

Table of Contents Safety Evaluation Related to Extended Power Uprate at

Assessment of RELAP5/MOD2 KNU #1 Interational

TRAC-M Validation Test Matrix

MELCOR Best Practices as Applied in the State-of-the-Art Reactor Consequence Analyses
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