Mechanical properties of austenitic stainless steels irradiated at 323 K in the Japan Materials Testing reactor
- 1 October 1996
- journal article
- Published by Elsevier in Journal of Nuclear Materials
- Vol. 233-237, 188-191
- https://doi.org/10.1016/s0022-3115(96)00212-7
Abstract
No abstract availableKeywords
This publication has 8 references indexed in Scilit:
- Tensile, low cycle fatigue and fracture toughness behaviour of type 316L steel irradiated to 0.3 dpaJournal of Nuclear Materials, 1994
- Tensile properties of type 316L(N) stainless steel irradiated to 10 displacements per atomJournal of Nuclear Materials, 1994
- Fracture toughness of candidate materials for ITER first wall, blanket, and shield structuresJournal of Nuclear Materials, 1994
- Stress-strain relations of irradiated stainless steels below 673 KJournal of Nuclear Materials, 1992
- Tensile properties of austenitic stainless steels and their weld joints after irradiation by the ORR-spectrally-tailoring experimentJournal of Nuclear Materials, 1992
- The effects of intermediate temperature irradiation on the mechanical behavior of 300-series austenitic stainless steelsJournal of Nuclear Materials, 1991
- Empirical relations for tensile properties of austenitic stainless steels irradiated in mixed-spectrum reactorsJournal of Nuclear Materials, 1991
- Stress-strain relations of HFIR-irradiated austenitic stainless steelsJournal of Nuclear Materials, 1991