An expert system framework for creep-fatigue analysis of high temperature nuclear components
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Date
1987-08-17
Authors
Advisors
Journal Title
Series/Report No.
E - Fast Reactor Core Coolant Circuit Structures
E-E03 - Creep-fatigue analysis
00 - SMiRT 9 - Lausanne, Switzerland. August 17-21, 1987
E-E03 - Creep-fatigue analysis
00 - SMiRT 9 - Lausanne, Switzerland. August 17-21, 1987
Journal ISSN
Volume Title
Publisher
IASMiRT
