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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Date
1973-09-10T00:00:00+00:00
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Advisors
Journal Title
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
C2 - Structural Analysis of Fuel Element Cladding--I
SMiRT 2 - Berlin, Germany. September 10-14, 1973
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Volume Title
Publisher
IASMiRT
