Development of Irradiation-Induced Stress Analysis Code-System for Graphite Components in Gas-Cooled Reactor

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Title: Development of Irradiation-Induced Stress Analysis Code-System for Graphite Components in Gas-Cooled Reactor
Author: Ishihara, M.; Iyoku, T.; Shiozawa, S.; Shirai, H.; Takikawa, N.
Publisher: IASMiRT
Date: 1993-08-15
Series/Report No.: C - Fuel and Core Structures and Fuel Element Storage
C08 - Specific Fuel Element Design Problems
SMiRT 12 - Stuttgart, Germany. August 15-20, 1993
URI: http://www.lib.ncsu.edu/resolver/1840.20/23972


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