The source term and waste optimization of molten salt reactors with processing

Conference · Thu Jul 01 00:00:00 EDT 1993

OSTI ID:10172935

Gat, U ^[1]; Dodds, H L ^[2]

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1. Oak Ridge National Lab., TN (United States)
2. Tennessee Univ., Knoxville, TN (United States). Dept. of Nuclear Engineering

The source term of a molten salt reactor (MSR) with fuel processing is reduced by the ratio of processing time to refueling time as compared to solid fuel reactors. The reduction, which can be one to two orders of magnitude, is due to removal of the long-lived fission products. The waste from MSRs can be optimized with respect to its chemical composition, concentration, mixture, shape, and size. The actinides and long-lived isotopes can be separated out and returned to the reactor for transmutation. These features make MSRs more acceptable and simpler in operation and handling.

• Research Organization: Oak Ridge National Lab., TN (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 10172935
• Report Number(s): CONF-930913-13; ON: DE93017761; TRN: 93:018863
• Resource Relation: Conference: Global `93: future nuclear systems - emerging fuel cycles and waste disposal options,Seattle, WA (United States),12-17 Sep 1993; Other Information: PBD: [1993]
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
MOLTEN SALT REACTORS
SOURCE TERMS
REACTOR FUELING
RADIOACTIVE WASTE PROCESSING
ACTINIDES
TRANSMUTATION
FISSION PRODUCTS
NUCLEAR FUELS
220502
220600
052001
RADIOACTIVE EFFLUENTS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
WASTE PROCESSING