Statistics for 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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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 6

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C2-1.pdf 31