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Conference Article: Safety requirements and research and development on HTTR fuel

Saito, S.; Shiozawa, S. (Japan Atomic Energy Research Inst., Oarai Research Establishment, Oarai, Ibaraki (Japan). Dept. of HTTR Project); Fukuda, K.; Kondo, T. (Japan Atomic Energy Research Inst., Tokai Research Establishment, Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research)

Abstract

Japan Atomic Energy Research Institute (JAERI) is now proceeding with the construction of the HTTR (High Temperature Engineering Test Reactor) to achieve its first criticality in FY 1995. The HTTR is designed to produce thermal power of 30MW and reactor outlet coolant temperature of 950 deg. C using pin-in-block type fuel rod assemblies. The TRISO coated fuel particles of 920um in outer diameter will be used as the HTTR fuel. The major requirements to the HTTR fuels from a safety point of view are formulated. JAERI has performed extensive design efforts and R and D to meet the above requirements. The items for the HTTR fuel R and D are divided into three categories: fuel fabrication, irradiation behaviour of HTTR fuel under normal operating condition and safety related research under accident conditions. Substantial results have been obtained through the R and D to guarantee the fuel to fulfill its function.

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key words: Gas Cooled Reactor, Nuclear Technology
Reference:
Behaviour of gas cooled reactor fuel under accident conditions. Proceedings of a specialists meeting held in Oak Ridge, 5-8 November 1990
International Atomic Energy Agency, Vienna (Austria). International Working Group on Gas-Cooled Reactors
IWGGCR--25, pp:31-36