Disposition of the fluoride fuel and flush salts from the Molten Salt Reactor experiment at Oak Ridge National Laboratory
Description
The Molten Salt Reactor Experiment (MSRE) is an 8 MW reactor that was operated at Oak Ridge National Laboratory (ORNL) from 1965 through 1969. The reactor used a unique liquid salt fuel, composed of a mixture of LIF, BeF2, ZrF4, and UF4, and operated at temperatures above 600 degrees C. The primary fuel salt circulation system consisted of the reactor vessel, a single fuel salt pump, and a single primary heat exchanger. Heat was transferred from the fuel salt to a coolant salt circuit in the primary heat exchanger. The coolant salt was similar to the fuel salt, except that it contains only LiF (66%) and BeF, (34%). The coolant salt passed from the primary heat exchanger to an air-cooled radiator and a coolant salt pump, and then returned to the primary heat exchanger. Each of the salt loops was provided with drain tanks, located such that the salt could be drained out of either circuit by gravity. A single drain tank was provided for the non-radioactive coolant salt. Two drain tanks were provided for the fuel salt. Since the fuel salt contained radioactive fuel, fission products, and activation products, and since the reactor was designed such that the fuel salt could be drained immediately into the drain tanks in the event of a problem in the fuel salt loop, the fuel salt drain tanks were provided with a system to remove the heat generated by radioactive decay. A third drain tank connected to the fuel salt loop was provided for a batch of flush salt. This batch of salt, similar in composition to the coolant salt, was used to condition the fuel salt loop after it had been exposed to air and to flush the fuel salt loop of residual fuel salt prior to accessing the reactor circuit for maintenance or experimental activities. This report discusses the disposition of the fluoride fuel and flush salt
Availability note (English)
MF available from INIS under the Report Number; Also available from OSTI as DE96006708; NTIS; US Govt. Printing Office Dep.Files
27051947.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 16 p.
- Report number
- CONF-960271--2
Conference
- Title
- American Institute of Chemical Engineers (AIChE) spring meeting.
- Dates
- 26-29 Feb 1996.
- Place
- New Orleans, LA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 27051947
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BERYLLIUM FLUORIDES; ELECTROREFINING; LITHIUM FLUORIDES; MOLTEN SALT FUELS; MOLTEN SALTS; MSRE REACTOR; OAK RIDGE RESERVATION; RADIOACTIVE WASTE PROCESSING; RADIOACTIVE WASTE STORAGE; RADIOLYSIS; REMEDIAL ACTION; SEPARATION PROCESSES; URANIUM FLUORIDES; ZIRCONIUM FLUORIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALKALI METAL COMPOUNDS; ALKALINE EARTH METAL COMPOUNDS; BERYLLIUM COMPOUNDS; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; DECOMPOSITION; ELECTROLYSIS; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FLUORIDES; FLUORINE COMPOUNDS; FUELS; GRAPHITE MODERATED REACTORS; HALIDES; HALOGEN COMPOUNDS; LIQUID FUELS; LITHIUM COMPOUNDS; LITHIUM HALIDES; MANAGEMENT; MOLTEN SALT COOLED REACTORS; MOLTEN SALT REACTORS; NATIONAL ORGANIZATIONS; POWER REACTORS; RADIATION EFFECTS; REACTORS; REFINING; RESEARCH AND TEST REACTORS; SALTS; STORAGE; THERMAL REACTORS; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; US DOE; US ORGANIZATIONS; WASTE MANAGEMENT; WASTE PROCESSING; WASTE STORAGE; ZIRCONIUM COMPOUNDS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400
- Funding organization
- USDOE, Washington, DC (United States).