Molten salt fuels for nuclear waste transmutation in accelerator driven systems
Description
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. (author)
Additional details
Identifiers
Publishing Information
- ISBN
- 92-0-106803-4
- Imprint Title
- Review of national accelerator driven system programmes for partitioning and transmutation. Proceedings of an advisory group meeting
- Imprint Pagination
- 173 p.
- Journal Page Range
- p. 119-129
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1365
Conference
- Title
- Advisory group meeting on review of national accelerator driven system programmes for partitioning and transmutation
- Dates
- 1-4 Nov 1999
- Place
- Taejon (Korea, Republic of)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 34083119
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCELERATOR DRIVEN TRANSMUTATION; ACTINIDES; FEASIBILITY STUDIES; FUEL CYCLE; MOLTEN SALT FUELED REACTORS; MOLTEN SALT FUELS; PLUTONIUM; RUSSIAN ORGANIZATIONS; ZERO POWER REACTORS
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENERGY SOURCES; EXPERIMENTAL REACTORS; FLUID FUELED REACTORS; FUELS; LIQUID FUELS; MATERIALS; METALS; MOLTEN SALT REACTORS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; TRANSMUTATION; TRANSURANIUM ELEMENTS
Optional Information
- Contract/Grant/Project number
- Project ISTC 698
- Notes
- 14 refs, 1 fig, 1 tab