Some implications of radiation-induced property changes in austenitic stainless steels on ITER (International Thermonuclear Experimental Reactor) first-wall design and performance

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6473232

Maziasz, P J; Rowcliffe, A F; Grossbeck, M L; Bell, G E.C.; Bloom, E E; Lousteau, D C ^[1]; Hishinuma, A; Kondo, T ^[2]; Mattas, R F; Smith, D L ^[3]

---

1. Oak Ridge National Lab., TN (USA)
2. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)
3. Argonne National Lab., IL (USA)

New data on radiation-induced hardening, low-temperature creep and potential susceptibility (sensitization) to aqueous corrosion have been obtained on various heats of austenitic stainless steel (including type 316) irradiated at 60--400{degree}C to 7--13 dpa. The data were obtained from spectral-tailoring reactor experiments, whose radiation-damage parameters are similar to those in the proposed International Thermonuclear Experimental Reactor (ITER) first-wall (FW) and blanket design. Austenitic stainless steels were found to increase significantly in strength at 60--330{degree}C, to have higher irradiation-creep rates at 60{degree}C than at 200--400{degree}C, and to show radiation-induced changes in electrochemical properties at 200--400{degree}C. These data on several radiation-induced property changes suggest that type 316 steel may be an adequate material for the FW of ITER. However, there is definitely a need for new data on fracture-toughness and on fatigue behavior below 400{degree}C, as well as more data on irradiation-creep and effects of irradiation on corrosion properties to better define temperature and dose dependencies for more detailed design analyses. Cold-working should remain an optional as-fabricated condition for the FW of ITER. Many properties of SA and CW 316 become similar after irradiation at 60--400{degree}C. The higher initial yield-strength of CW 316 will allow higher design stress and elastic strain limits. 31 refs., 10 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6473232
• Report Number(s): CONF-901007-29; ON: DE91004766; TRN: 91-000140
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
AUSTENITIC STEELS
RADIATION HARDENING
FIRST WALL
DESIGN
BREEDING BLANKETS
CORROSION
CREEP
ITER TOKAMAK
PERFORMANCE
PHYSICAL RADIATION EFFECTS
SWELLING
YIELD STRENGTH
ALLOYS
CHEMICAL REACTIONS
CLOSED PLASMA DEVICES
HARDENING
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
RADIATION EFFECTS
REACTOR COMPONENTS
STEELS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
TOKAMAK DEVICES
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700201 - Fusion Power Plant Technology- Blanket Engineering