Mechanical properties of irradiated type 304 and 316 stainless steels
- 1. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)
Description
Mechanical properties were investigated for irradiated type 304 and 316 Stainless Steels (SS) which are used as core structural materials in LWRs and LMRs. An irradiation test was performed with a 24MW output power at the IR2 hole of HNARO for 11 days. The specimens accumulated neutron fluences of about 8.0∼10 x 1019 n/cm2 (E>1.0 MeV) at 320 .deg C. The tension test was conducted in the range from room temperature to 700 .deg. C in the IMEF hot cell of KAERI, while employing a strain rate of 2x10-3 /sec. The tensile test results of the irradiated type 304 and 316SS showed the typical irradiation hardening and low ductility behaviors, and especially the yield strength was increased considerably. But, at a high temperature above 500 .deg. C, the irradiated tensile strength approached the un-irradiated one. The reason for it is that the irradiation defects are recovered by thermal activation. Also, the irradiated ones showed higher values in the strain hardening exponents than the unirradiated ones, and their values were nearly saturated to the un-irradiated ones when reaching 600 .deg. C
Additional details
Publishing Information
- Publisher
- KAERI
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of international symposium on research reactor and neutron science
- Imprint Pagination
- 922 p.
- Journal Page Range
- p. 284-288
Conference
- Title
- International symposium on research reactor and neutron science
- Dates
- 11-13 Apr 2005
- Place
- Taejon (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 37008085
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- HANARO REACTOR; IRRADIATION; MECHANICAL PROPERTIES; STAINLESS STEEL-304; STAINLESS STEEL-316; WATER COOLED REACTORS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POOL TYPE REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEEL-CR19NI10; STEELS; TEST FACILITIES; TEST REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs, 9 figs, 1 tab