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
| 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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| Files | Size | Format | View |
|---|---|---|---|
| C2-1.pdf | 222.4Kb |
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