Impact of structural design criteria on first wall surface heat flux limit
- Argonne National Lab., IL (United States)
The irradiation environment experienced by the in-vessel components of fusion reactors presents structural design challenges not envisioned in the development of existing structural design criteria such as the ASME Code or RCC-MR. From the standpoint of design criteria, the most significant issues stem from the irradiation-induced changes in material properties, specifically the reduction of ductility, strain hardening capability, and fracture toughness with neutron irradiation. Recently, Draft 7 of the ITER structural design criteria (ISDC), which provide new rules for guarding against such problems, was released for trial use by the ITER designers. The new rules, which were derived from a simple model based on the concept of elastic follow up factor, provide primary and secondary stress limits as functions of uniform elongation and ductility. The implication of these rules on the allowable surface heat flux on typical first walls made of type 316 stainless steel and vanadium alloys are discussed.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- OSTI ID:
- 330634
- Report Number(s):
- DOE/ER-0313/24; ON: DE98007433; TRN: 99:005089
- Resource Relation:
- Other Information: PBD: Sep 1998; Related Information: Is Part Of Fusion materials semiannual progress report for the period ending June 30, 1998; Burn, G. [ed.] [comp.]; PB: 314 p.
- Country of Publication:
- United States
- Language:
- English
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