Analysis of Thermal and Irradiation Behaviour of Fuelled Graphite Bricks for a High Temperature Gas Cooled Reactor

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Title: Analysis of Thermal and Irradiation Behaviour of Fuelled Graphite Bricks for a High Temperature Gas Cooled Reactor
Author: V.S. Beckett
Publisher: IASMiRT
Date: 1971-09-20
Series/Report No.: D - Fuel Elements
D2 - Stress Analysis of Graphite Fuel/Moderator Elements-I
SMiRT 1 - Berlin, Germany. September 20-24, 1971
URI: http://www.lib.ncsu.edu/resolver/1840.20/28904


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