Summary of recommended correlations for ITER-grade type 316L(N) for the ITER materials properties handbook
The focus of this effort is the effects of irradiation on the ultimate tensile strengths (UTS), the yield strength (YS), the uniform elongation (UE), the total elongation (TE) and the reduction in area (RA) in the ITER-relevant temperature range of 100-400{degrees}C. For the purpose of this summary, data for European heats of 316 with 0.02<0.03 wt.% and 0.060.08 wt.% are referred to as E316L(N) data and grouped together. Other heats of 316 and Ti-modified 316 are also included in the data base. For irradiation and postirradiation-test temperatures in the range of 200-400{degrees}C, the common behavior of these heats of stainless steel is a yield strength approaching the ultimate tensile strength approaching 800 MPa, a uniform elongation approaching 0.3%, a total elongation approaching 3-9%, and a high (about 60%) reduction in area as the neutron damage approaches 10 dpa.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OSTI ID:
- 270465
- Report Number(s):
- DOE/ER-0313/19; ORNL/M-5023; ON: DE96010874; TRN: 96:016912
- 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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