Published August 1999
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In-pile and post-irradiation creep of SUS304 with JMTR thermal neutron spectrum
Creators
- 1. Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment
Description
In-pile creep tests were performed using newly developed technology with in-situ measurement of elongation under different neutron spectra in addition to post-irradiation creep tests. Irradiation creep behavior of SUS304 at 550degC depends on a neutron spectrum. Irradiation creep deformation under a high thermal neutron flux condition is enhanced more than that under a thermal neutron shield condition and creep deformation of post-irradiation creep. (author)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the sixth Asian symposium on research reactors
- Imprint Pagination
- 445 p.
- Journal Page Range
- p. 201-206
- Report number
- JAERI-Conf--99-006
Conference
- Title
- 6. Asian symposium on research reactors
- Acronym
- ASRR-VI
- Dates
- 29-31 Mar 1999
- Place
- Mito, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 31009626
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CREEP; DAMAGING NEUTRON FLUENCE; ELONGATION; IRRADIATION; JMTR REACTOR; NEUTRON SPECTRA; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; STAINLESS STEEL-304; TEMPERATURE RANGE 0400-1000 K; THERMAL NEUTRONS
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; DEFORMATION; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; NEUTRON FLUENCE; NEUTRONS; NICKEL ALLOYS; NUCLEONS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SPECTRA; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TANK TYPE REACTORS; TEMPERATURE RANGE; TEST FACILITIES; TEST REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS