Technology development on production of test specimens from irradiated capsule outer-tube and mechanical evaluation test of stainless steel with high dose carried out by the technology
Creators
- 1. Japan Atomic Energy Agency, Oarai Research and Development Center, Oarai, Ibaraki (Japan)
Description
The irradiation capsule 74M-52J was irradiated during total 136 cycles at reactor core of JMTR and the maximum neutron dose reached on 3.9x1026 n/m2 at the capsule outer-tube made of a type 304 stainless steel. In order to produce mechanical test specimens from the outer-tube, a punching technique was developed as a simple remote-handling method in a hot-cell. From comparison between the punching and the mechanical cutting methods, it was clarified that the punching technique was applicable to practical use. Moreover, an evaluation test of mechanical properties using specimens sampled from the 74M-52 was performed with in-water high temperature condition, less than 288degC. The result shows that the residual elongation is 18% at 150degC and 13% at 288degC. It was confirmed that the type 304 stainless steel irradiated up to such high dose shows enough ductility. (author)
Availability note (English)
Available from JAEA; DOI: https://doi.org/10.11484/jaea-technology-2008-016
Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 60 p.
- Report number
- JAEA-Technology--2008-016
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 40024374
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- DUCTILITY; ELONGATION; HOT LABS; IRRADIATION CAPSULES; JAEA; JMTR REACTOR; MECHANICAL TESTS; NEUTRONS; PHYSICAL RADIATION EFFECTS; STAINLESS STEEL-304; STRESS CORROSION; TUBES
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BARYONS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; CORROSION; 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; JAPANESE ORGANIZATIONS; LABORATORIES; MATERIALS; MATERIALS TESTING; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; NUCLEAR FACILITIES; NUCLEONS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEEL-CR19NI10; STEELS; TANK TYPE REACTORS; TENSILE PROPERTIES; TEST FACILITIES; TEST REACTORS; TESTING; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 4 refs., 22 figs., 8 tabs.