Fabrication of HTTR first loading fuel
Creators
- 1. Nuclear Fuel Industries, Ltd, Tokai-mura, Ibaraki-ken (Japan)
- 2. Japan Atomic Energy Research Institute, Oarai-machi, Ibaraki-ken (Japan)
Description
This paper summarizes the fabrication of the first loading fuel for HTTR, High Temperature engineering Test Reactor constructed by JAERI, Japan Atomic Energy Research Institute. The fuel fabrication started at the HTR fuel facility of NFI, Nuclear Fuel Industries, Ltd., June 1995. 4,770 fuel rods were fabricated through the fuel kernel, coated fuel particle and fuel compaction process, then 150 fuel elements were assembled in the reactor building December 1997. Fabrication technology for the fuel was established through a lot of R and D activities and fabrication experience of irradiation examination samples spread over about 30 years. Most of all, very high quality and production efficiency of fuel were achieved by the development of the fuel kernel process using the vibration dropping technology, the continuous 4-layer coating process and the automatic compaction process. As for the inspection technology, the development of the automatic measurement equipment for coated layer thickness of a coated fuel particle and uranium content of a fuel compact contributed to the higher reliability and rationalization of the inspection process. The data processing system for the fabrication and quality control, which was originally developed by NFI, made possible not only quick feedback of statistical quality data to the fabrication processes, but also automatic document preparation, such as inspection certificates and accountability control reports. The quality of the first loading fuel fully satisfied the design specifications for the fuel. In particular, average bare uranium fraction and SiC defective fraction of fuel compacts were 2x10-6 and 8x10-5, respectively. According to the preceding irradiation examinations being performed at JMTR, Japan Materials Testing Reactor of JAERI, the specimen sampled from the first loading fuel shows good irradiation performance. (author)
Files
32020078.pdf
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Additional details
Publishing Information
- Imprint Title
- Safety related design and economic aspects of HTGRs. Proceedings of a technical committee meeting
- Imprint Pagination
- 260 p.
- Journal Page Range
- p. 187-199
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1210
Conference
- Title
- Technical committee meeting on safety related design and economic aspects of HTGRs
- Dates
- 24 Nov 1998
- Place
- Beijing (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 32020078
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COATED FUEL PARTICLES; COMPACTING; FUEL ELEMENTS; FUEL FABRICATION PLANTS; HTTR REACTOR; PERFORMANCE TESTING; POST-IRRADIATION EXAMINATION; QUALITY CONTROL; SILICON CARBIDES; URANIUM
- Descriptors DEC
- ACTINIDES; CARBIDES; CARBON COMPOUNDS; CONTROL; ELEMENTS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FABRICATION; FUEL PARTICLES; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; HELIUM COOLED REACTORS; HTGR TYPE REACTORS; METALS; NUCLEAR FACILITIES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SILICON COMPOUNDS; TESTING
Optional Information
- Notes
- 4 refs, 11 figs, 1 tab