Materials compatibility and salt chemistry control: Case for molten salt actinide recycler and transmuter
- 1. NRC-Kurchatov Institute (Russian Federation)
Description
A study is in progress to examine the feasibility of the Molten Salt Actinide Recycler and Transmuter (MOSART) system fuelled with different compositions of transuranic elements trifluorides (TRUF3) from spent PWR fuel. In order to achieve new goals, new design options with homogeneous core and fuel salt with high enough solubility for TRUF3 are being examined. The flexibility of the single fluid MOSART concept fuel cycle with U-Th support is underlined, in particular, the possibility of its operation in self-sustainable mode using different loadings and make-up. This paper summarises the major developments concerning (1) the ability to produce and maintain a high level of purity in fuel salt, (2) effective control of the redox potential of the molten salt medium in order to minimise corrosion, (3) selected materials testing as applied to conditions of reference design. (authors)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the Twelfth Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
- Imprint Pagination
- 329 p.
- Journal Page Range
- p. 256-264
- Report number
- NEA-NSC-DOC--2013-3
Conference
- Title
- 12. Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation
- Dates
- 24-27 Sep 2012
- Place
- Prague (Czech Republic)
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 44100559
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACTINIDES; CRACK PROPAGATION; FEASIBILITY STUDIES; FISSION PRODUCTS; FLUORIDES; ISOTOPE PRODUCTION; MOLTEN SALT FUELS; NEA; PARTITION; PURIFICATION; PWR TYPE REACTORS; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTES; REDOX POTENTIAL; REDUCTIVE EXTRACTION; REPROCESSING; SPENT FUELS; TELLURIUM
- Descriptors DEC
- ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXTRACTION; FLUORINE COMPOUNDS; FUELS; HALIDES; HALOGEN COMPOUNDS; INTERNATIONAL ORGANIZATIONS; ISOTOPES; LIQUID FUELS; MANAGEMENT; MATERIALS; METALS; NUCLEAR FUELS; OECD; POWER REACTORS; PROCESSING; RADIOACTIVE MATERIALS; RADIOACTIVE WASTE MANAGEMENT; REACTOR MATERIALS; REACTORS; SEMIMETALS; SEPARATION PROCESSES; THERMAL REACTORS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS