Surveillance test of OWL-2 inpile tube
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki. Oarai Research Establishment
Description
A series of irradiation surveillance tests performed in integrity evaluation of an inpile tube for the test loop OWL-2 are described. Specimens were exposed to the neutron fluences from 1 x 1020 to 3.4 x 1021 n/cm2 (>1 MeV), and subjected to post-irradiation tensile test at room temperature and service temperature 285 0C. The strength increased and the ductility decreased with increasing neutron fluence. The reduction in fracture ductility due to neutron irradiation in the fluence range was insignificant, and the elongation of 33% was retained even for the maximum neutron fluence at 2850C. Little decrease of the ductility with fluence indicates that the tube would be in service for long time, ie to the integral fluence of 3.4 x 1021 n/cm2. (auth.)
Availability note (English)
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8315888.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 33 p.
- Report number
- JAERI-M--6667
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 8315888
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAST NEUTRONS; HIGH TEMPERATURE; IN PILE LOOPS; INSPECTION; IRRADIATION; IRRADIATION DEVICES; JMTR REACTOR; LIFETIME; NEUTRON FLUENCE; PHYSICAL RADIATION EFFECTS; PIPES; SAFETY; STAINLESS STEEL-316; TENSILE PROPERTIES
- Descriptors DEC
- ALLOYS; BARYONS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-NICKEL STEELS; CORROSION RESISTANT ALLOYS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HEAT RESISTING ALLOYS; IRON ALLOYS; IRON BASE ALLOYS; IRRADIATION REACTORS; MATERIALS TESTING REACTORS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NEUTRONS; NICKEL ALLOYS; NUCLEONS; RADIATION EFFECTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; STAINLESS STEELS; STEELS; TANK TYPE REACTORS; TEST REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS