Development of post-irradiation examination techniques for HTTR structural material
- 1. Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment
Description
Post-irradiation examinations (PIEs) on heat resistant alloys used for the High Temperature Engineering Test Reactor (HTTR) which is now under construction, are one of major PIE works in the JMTR Hot Laboratory facility (JMTR HL). The structural materials tested are Alloy 800H for the control rod cladding, 2 1/4Cr-1Mo steel for the reactor pressure vessel and 1Cr-1Mo-0.25V steel for the bolts, etc.. PIE techniques developed mainly for the HTTR are creep tests to obtain high temperature creep property and low cycle fatigue tests to obtain high temperature fatigue property. Newly developed PIE techniques for the study of irradiation effects on reactor pressure vessel materials are carried out to clarify dynamic fracture toughness of reactor structural materials using an instrumented Charpy impact testing machine. This report describes the present status of material tests with emphasis on PIE techniques newly developed for the HTTR. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the JAERI-KAERI joint seminar on post irradiation examination
- Imprint Pagination
- 298 p.
- Journal Page Range
- p. 218-228.
- Report number
- JAERI-M--93-016
Conference
- Title
- JAERI-KAERI joint seminar on post irradiation examination.
- Dates
- 9-10 Nov 1992.
- Place
- Oarai, Ibaraki (Japan).
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 25027592
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONSTRUCTION; CREEP; EQUIPMENT; FATIGUE; HEAT RESISTING ALLOYS; HOT LABS; HTTR REACTOR; MATERIALS TESTING; POST-IRRADIATION EXAMINATION; REACTOR MATERIALS
- Descriptors DEC
- ALLOYS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; LABORATORIES; MATERIALS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; TESTING