Effects of annealing on the tensile properties of irradiated austenitic stainless steel
- 1. Japan Atomic Energy Res. Inst., Ibaraki (Japan). Dept. of Nucl. Energy Syst.
- 2. Oak Ridge National Lab., TN (United States). Metals and Ceramics Div.
Description
The austenitic stainless steel (Fe-0.06C-0.5Si-1.8Mn-14Cr-16Ni-2Mo-0.24Ti) was irradiated in a triple ion facility and the high flux isotope reactor. The materials used were in the solution annealed (SA) and 15% cold-worked (CW) condition. TEM and tensile specimens were irradiated to a dose level of 30 and 10 dpa at 200 C. Some of the specimens were annealed after the irradiation at 500 C for 8 h in a vacuum. Microhardness tests were carried out on the surface of the TEM disks at room temperature. Tensile tests were carried out at 200 C in a vacuum with strain rate of about 1 x 10-3 s-1. The microhardness of both SA and CW increased by ion irradiation and then decreased by annealing. The yield strengths of the neutron irradiated SA and CW decreased to 610 and 650 MPa by annealing, respectively. The strain to necking of the irradiated CW recovered from 0.7% to 7.6%. The fracture mode remained ductile in each case. (orig.)
Additional details
Publishing Information
- Journal Title
- Journal of Nuclear Materials
- Journal Volume
- 258-263
- Journal Issue
- pt.B
- Journal Page Range
- p. 1664-1668
- ISSN
- 0022-3115
- CODEN
- JNUMAM
Conference
- Title
- 8. international conference on fusion reactor materials (ICFRM-8)
- Dates
- 26-31 Oct 1997
- Place
- Sendai (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 30007627
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY; S36: MATERIALS SCIENCE; S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ANNEALING; COLD WORKING; DUCTILITY; FISSION NEUTRONS; HFIR REACTOR; MEV RANGE 10-100; MICROHARDNESS; NEUTRON FLUENCE; NICKEL IONS; RADIATION DOSES; RADIATION EFFECTS; TEMPERATURE RANGE 0400-1000 K; THERMONUCLEAR REACTOR MATERIALS; TRANSMISSION ELECTRON MICROSCOPY; YIELD STRENGTH
- Descriptors DEC
- BARYONS; CHARGED PARTICLES; ELECTRON MICROSCOPY; ELEMENTARY PARTICLES; ENERGY RANGE; ENRICHED URANIUM REACTORS; FABRICATION; FERMIONS; HADRONS; HARDNESS; HEAT TREATMENTS; IONS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS WORKING; MECHANICAL PROPERTIES; MEV RANGE; MICROSCOPY; NEUTRONS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TANK TYPE REACTORS; TEMPERATURE RANGE; TENSILE PROPERTIES; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 19 refs.