Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Research and development of uranium-plutonium mixed carbide and nitride fuels at JAERI

Suzuki, Y.; Arai, Y.; Handa, M.; Shiba, K. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Dept. of Fuels and Materials Research)

Abstract

The present status of the development of uranium-plutonium mixed carbide and nitride fuels at Japan Atomic Energy Research Institute (JAERI) is described. The development program covers fuel fabrication studies, fuel property measurements and irradiation tests. The fuels were prepared using the carbothermic reduction of oxides followed by sintering. Procedures for the characterization of the fuels fabricated have been established. The studies of fuel properties cover thermal conductivity, evaporation behavior, chemical potential and so on. Irradiation tests of carbide fuel pins have been carried out by the use of research thermal reactors, JRR-2 and JMTR at JAERI. The carbide and nitride fuels will be irradiated for performance tests in the experimental fast reactor (JOYO) in collaboration with Power Reactor and Nuclear Fuel Development Corporation (PNC).

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key words: fabrication; fuel pellets; fuel pins; lmfbr type reactors; microstructure; mixed carbide fuels; mixed nitride fuels; performance testing; plutonium carbides; post-irradiation examination; quality control
Reference:
Proceedings of an advisory group meeting held in Vienna, 27-29 November 1989
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--577, pp:70-79