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OXIDATION OF Zr ALLOYS IN HIGH PRESSURE ... AND SOME RESULTS UNDER ATMOSPHERIC ... G. Hache
Information Digest 2 0 1 0 – 2 0 1 1 In fo
Official Transcript of Proceedings NUCLEAR REGULATORY COMMISSION
4. Reactor AP1000 Design Control Document
Document 1656096
4.3 Nuclear Design 4.3.1 Design Bases
12946 Federal Register
RIDGE -Concrete-Component Aging and -Its Significance Relative to
Safety Evaluation Report Related to the License Renewal of Hope Creek Generating
Development of Emergency Action Levels for Non-Passive Reactors NEI 99-01 [Revision 6]
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