Theoretical Analysis of Stress, Strain and Fracture of Fast Reactor Fuel Cladding under Constant Power and Power-Cycling Conditions: Visco-elastic Model of Nuclear Fuel-pin Behavior

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Title: Theoretical Analysis of Stress, Strain and Fracture of Fast Reactor Fuel Cladding under Constant Power and Power-Cycling Conditions: Visco-elastic Model of Nuclear Fuel-pin Behavior
Author: J.H. Gittus
Publisher: IASMiRT
Date: 1973-09-10
Series/Report No.: C - Structural Analysis of Reactor Fuel and Cladding
C2 - Structural Analysis of Fuel Element Cladding--I
SMiRT 2 - Berlin, Germany. September 10-14, 1973
URI: http://www.lib.ncsu.edu/resolver/1840.20/28530


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