Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels
- Oak Ridge National Laboratory, TN (United States)
An austenitic stainless steel, designated 316LN-IG, has been chosen for the first wall/shield (FW/S) structure for the International Thermonuclear Experimental Reactor (ITER). The proposed operational temperature range for the structure (100 to 250{degree}C) is below the temperature regimes for void swelling (400-600{degree}C) and for helium embrittlement (500-700{degree}C). However, the proposed neutron dose is such that large changes in yield strength, deformation mode, and strain hardening capacity could be encountered which could significantly affect fracture properties. Definition of the irradiation regimes in which this phenomenon occurs is essential to the establishment of design rules to protect against various modes of failure.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OSTI ID:
- 270448
- Report Number(s):
- DOE/ER-0313/19; ORNL/M-5023; ON: DE96010874; TRN: 96:016895
- Resource Relation:
- Other Information: PBD: Apr 1996; Related Information: Is Part Of Fusion materials semiannual progress report for the period ending December 31, 1995; PB: 336 p.
- Country of Publication:
- United States
- Language:
- English
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