Published 1978
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Molten fluoride mixtures as possible fission reactor fuels
Description
Molten mixtures of fluorides with UF4 as a component have been used as combined fuel and primary heat transfer agent in experimental high-temperature reactors and have been proposed for use in breeders or converters of 233U from thorium. Such use places stringent and diverse demands upon the fluid fuel. A brief review of chemical behavior of molten fluorides is given to show some of their strengths and weaknesses for such service
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 46 p.
- Report number
- CONF-780571--1
Conference
- Title
- 153. meeting of the Electrochemical Society.
- Dates
- 21 - 26 May 1978.
- Place
- Seattle, WA, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9418580
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BREEDER REACTORS; CHEMICAL REACTIONS; CORROSION; FLUORIDES; MOLTEN SALT FUELED REACTORS; MOLTEN SALT FUELS; PERFORMANCE; PLANNING; THORIUM CYCLE; URANIUM TETRAFLUORIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; ENERGY SOURCES; FLUID FUELED REACTORS; FLUORINE COMPOUNDS; FUEL CYCLE; FUELS; HALIDES; HALOGEN COMPOUNDS; LIQUID FUELS; MOLTEN SALT REACTORS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; URANIUM COMPOUNDS; URANIUM FLUORIDES