Irradiation creep in austenitic stainless steel at 60 to 400 degrees C with a fusion reactor helium to dpa ratio
Creators
- 1. Oak Ridge National Lab., TN (USA)
- 2. Japan Atomic Energy Research Inst., Tokyo (Japan)
Description
Irradiation creep was investigated in the alloys-prime candidate alloy (PCA), Japanese Fusion Energy Program (JPCA), and American Iron and Steel Institute (AISI) 316 (UNS S31600) stainless steel. Tubes pressurized to stress levels of 50 to 400 MPa were irradiated in the Oak Ridge Research Reactor (ORR) with the neutron spectrum tailored to achieve the fusion reactor helium:dpa value of 12 appm/dpa in AISI 316 stainless steel. Irradiation temperatures of 60, 330, and 400 degrees C were investigated, and the irradiation produced 8 dpa and a maximum of about 100 appm helium. Irradiation creep rates of 2.2 to 14 x 10-4 MPa-1 dpa-1 were observed, similar to those found previously in similar experiments in the ORR. The low temperature irradiation creep was interpreted in terms of a new model for irradiation creep based on transient climb-enabled glide. The results are important in the design of experimental fusion reactors where temperatures below 100 degrees C are being considered for the operation of high flux components
Additional details
Publishing Information
- Publisher
- ASTM.
- Imprint Place
- Philadelphia, PA (USA)
- Imprint Title
- Effects of radiation on materials
- Imprint Pagination
- 820 p.
- Journal Page Range
- p. 537-550.
Conference
- Title
- 14. international symposium on effects of radiation on materials.
- Dates
- 27-29 Jun 1988.
- Place
- Andover, MA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22022302
- Subject category
- S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE; S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DAMAGING NEUTRON FLUENCE; IRRADIATION; PHYSICAL RADIATION EFFECTS; REACTOR MATERIALS; STEEL-CR17NI12MO3; THERMONUCLEAR REACTORS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STE; CORROSION RESISTANT ALLOYS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NEUTRON FLUENCE; NICKEL ALLOYS; RADIATION EFFECTS; STAINLESS STEELS; STEELS
Optional Information
- Secondary number(s)
- CONF-880613--.