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Title: Disposition of the fluoride fuel and flush salts from the Molten Salt Reactor experiment at Oak Ridge National Laboratory

Disposition of the fluoride fuel and flush salts from the Molten Salt Reactor experiment at Oak Ridge National Laboratory 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, BeF{sub 2}, ZrF{sub 4}, and UF{sub 4}, 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 more » 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. « less
Authors:
Publication Date:
OSTI Identifier:206448
Report Number(s):CONF-960271--2
ON: DE96006708; TRN: 96:008760
DOE Contract Number:AC05-84OR21400
Resource Type:Conference
Data Type:
Resource Relation:Conference: American Institute of Chemical Engineers (AIChE) spring meeting, New Orleans, LA (United States), 26-29 Feb 1996; Other Information: PBD: [1996]
Research Org:Oak Ridge National Lab., TN (United States)
Sponsoring Org:USDOE, Washington, DC (United States)
Country of Publication:United States
Language:English
Subject: 05 NUCLEAR FUELS; 22 NUCLEAR REACTOR TECHNOLOGY; MSRE REACTOR; REMEDIAL ACTION; MOLTEN SALTS; RADIOACTIVE WASTE STORAGE; MOLTEN SALT FUELS; OAK RIDGE RESERVATION; SEPARATION PROCESSES; RADIOACTIVE WASTE PROCESSING; ELECTROREFINING; RADIOLYSIS; LITHIUM FLUORIDES; BERYLLIUM FLUORIDES; ZIRCONIUM FLUORIDES; URANIUM FLUORIDES