Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Improvements in MOX fuel utilization in Japan and technological developments for an economical FBR fuel cycle

Mishima, T. (Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works)

Abstract

Japanese research and development (R and D) activities to realize Pu recycling within conventional oxide form are being carried out by the Power Reactor and Nuclear Fuel Development Corporation (PNC) with the aid of the Japan Atomic Energy Research Institute and utilities. The goals of this R and D are focussed on achieving high burnups and high heat rates, i.e., 80GWd/t average burnup and 360W/cm maximum linear heat rate in the ''MONJU'' reactor which will go critical in 1992, and 150 to 200GWd/t and 480W/cm in commercial FBRs which will appear in the early 2000s. In the meantime, efforts are also being spent to realize recycling of Pu in water reactors. In this paper, improvements in fuel fabrication, fuel performance and cladding material, and advances in fuel concepts are presented.

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key words: burnup; cost benefit analysis; fabrication; fuel assemblies; fuel cans; fuel cycle; fuel rods; mixed oxide fuels; monju reactor; performance; planning; plutonium oxides; quality control; remote handling equipment
Reference:
Proceedings of an advisory group meeting held in Vienna, 27-29 November 1989
International Atomic Energy Agency, Vienna (Austria)
IAEA-TECDOC--577, pp:44-61