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Conference Article: Fabrication of HTTR first loading fuel

S. KATO, S. YOSHIMUTA, T. HASUMI, K. SATO (Nuclear Fuel Industries, Ltd., Japan),K. SAWA, S. SUZUKI, H. MOGI, S. SHIOZAWA, T. TANAKA (Japan Atomic Energy Research Institute, Japan)

Abstract

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&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 2 x 10-6 and 8 x 10- 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.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Proceedings of a Technical Committee Meeting held in Beijing, People's Republic of China, 2-4 November 1998
International Atomic Energy Agency, International Working Group on Gas-Cooled Reactors, Vienna (Austria)
IAEA-TECDOC--1210, pp:187-199