Published December 1994
| Version v1
Journal article
Evaluation of irradiation temperature of the fast reactor fuel pin by the cladding hardness measurement
- 1. Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center
Description
In order to evaluate the cladding temperature of the FBR fuel pin during irradiation, micro-hardness measurement was conducted on the fuel cladding irradiated in 'Joyo' MK-II core. In this report, the results of micro-hardness measurement and micro-structure observation on irradiated fuel cladding were described, and the applicability of these results to temperature estimation was analyzed. The analysis showed that the irradiation temperature of the FBR fuel cladding can be estimated by the micro-hardness measurement as an useful and practical method. (author)
Additional details
Publishing Information
- Journal Title
- Donen Giho
- Journal Issue
- no.92
- Journal Page Range
- p. 54-58.
- ISSN
- 0289-6605
- CODEN
- DOGIEL
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 26060333
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FUEL CANS; JOYO REACTOR; MICROHARDNESS; MICROSTRUCTURE; PHYSICAL RADIATION EFFECTS; POST-IRRADIATION EXAMINATION; SCREW DISLOCATIONS; STAINLESS STEEL-316; TEMPERATURE DEPENDENCE
- Descriptors DEC
- ALLOYS; AUSTENITIC STEELS; BREEDER REACTORS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CHROMIUM-MOLYBDENUM STEELS; CHROMIUM-NICKEL STEELS; CHROMIUM-NICKEL-MOLYBDENUM STEELS; CORROSION RESISTANT ALLOYS; CRYSTAL DEFECTS; CRYSTAL STRUCTURE; DISLOCATIONS; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; HARDNESS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; LINE DEFECTS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MATERIALS; MECHANICAL PROPERTIES; MOLYBDENUM ALLOYS; NICKEL ALLOYS; POWER REACTORS; RADIATION EFFECTS; REACTORS; RESEARCH AND TEST REACTORS; STAINLESS STEELS; STEEL-CR17NI12MO3; STEELS; TRANSITION ELEMENT ALLOYS