Fast Reactors and Accelerator Driven Systems Knowledge Base

Conference Article: Molten salt fuels for nuclear waste transmutation in accelerator driven systems

Abstract

In order to discuss various criteria for achieving actinide reduction goals, the goals for long lived radwaste management strategy must be defined themselves. Some possible goals and the reasons behind these will be presented. An attempt is made to arrange the possible systems on order of performance with regard to their potential to limit actinide inventory in the fuel cycle, reduce actinides losses to waste, and the same time, to keep minimal uranium-235 support and minimal neutron captures outside actinides. The objective of this paper is to discuss the feasibility of molten salt reactor technology for treatment of plutonium minor actinides and fission products in accelerator driven systems. Fluid nature of the fuel gives extra flexibility to get: simpler back end of the fuel cycle due to the easy of the fuel preparation and treatment in the operation, increased burnup time in the system and as a result decreased TRU mass flow rate in the fuel cycle. This contribution aims: to review the results of the works performed, particularly in Russia, on molten salt reactor technology development and to evaluate the importance of remaining uncertainties for molten salt burner concept implementation. Fuel properties, container materials, fuel radiation stability, pump experience and cleanup of fuels with emphasis on experiments will be of priority. Recommendations are made regarding the types of experimental studies needed on a way to implement molten salt technology to back end of the fuel cycle. To solve some of the essential issues for molten salt burner concept, Russian Institutes [RFNC-All-Russian Institute of Technical Physics (Snezinsk), RRC-Kurchatov Institute (Moscow), Institute of Chemical Technology, Moscow) and Institute of High Temperature Electrochemistry (Ekaterinburg)] have submitted to the ISTC the Project # 1606 "Experimental study of molten salt technology for safe and low waste treatment of plutonium and minor actinides in accelerator driven and critical systems": The major developments that we believe should be pursed in the work of the ISTC # 1606 will be briefly discussed.

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Reference:

Proceedings of an Advisory Group meeting held inTaejon, Republic of Korea, 1–4 November 1999

International Atomic Energy Agency, Vienna (Austria)

IAEA-TECDOC--1365, pp:119-129