Biaxial Stress-Rupture Properties of Austenitic Stainless Steels in Static Sodium
Research and development rept.
ROCKWELL INTERNATIONAL CANOGA PARK CA ATOMICS INTERNATIONAL DIV
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The mechanical properties of candidate cladding materials for fast breeder reactor fuel elements are being investigated as part of the Atomic Energy Commission Liquid Metal Cooled Past Breeder Reactor Program. This report deals with the stress-rupture characteristics of austenitic stainless steels in a liquid sodium environment, in both cold-worked and annealed conditions.
- Properties of Metals and Alloys
- Nuclear Fission Reactors (Power)