LMFBR source term experiments in the fuel aerosol simulant test (FAST) facility
Description
The transport of uranium dioxide (UO2) aerosol through liquid sodium was studied in a series of ten experiments in the Fuel Aerosol Simulant Test (FAST) facility at Oak Ridge National Laboratory. The experiments were designed to provide a mechanistic basis for evaluating the radiological source term associated with a postulated, energetic core disruptive accident in a liquid metal fast breeder reactor. Aerosol was generated by capacitor discharge vaporization of UO2 pellets which were submerged in a sodium pool under an argon cover gas. Measurements of the pool and cover gas pressures were used to study the transport of aerosol contained by vapor bubbles within the pool. Samples of cover gas were filtered to determine the quantity of aerosol released from the pool. The depth at which the aerosol was generated was found to be the most critical parameter affecting release. The mass of aerosol released from the pool was found to be a very small fraction of the original specimen. It appears that the bulk of aerosol was contained by bubbles which collapsed within the pool
Additional details
Publishing Information
- Imprint Title
- Fast reactor safety: proceedings of the international topical meeting. Volume 2
- Journal Page Range
- p. 865-875.
- Report number
- CONF-850410--Vol.2
Conference
- Title
- ANS/ENS fast reactor safety meeting.
- Dates
- 21-24 Apr 1985.
- Place
- Knoxville, TN (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17036806
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; BOILING; BUBBLES; COOLANTS; COVER GAS; FISSION PRODUCT RELEASE; HEAT TRANSFER; LMFBR TYPE REACTORS; MASS TRANSFER; ORNL; POWER-COOLING-MISMATCH ACCIDEN; REACTOR CORE DISRUPTION; REACTOR CORES; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; REACTOR VESSELS; SCRAM; SIMULATION; SODIUM; TESTING; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALKALI METALS; BREEDER REACTORS; CHALCOGENIDES; COLLOIDS; CONTAINERS; CONTROLLED ATMOSPHERES; DISPERSIONS; ELEMENTS; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; INERT ATMOSPHERE; LIQUID METAL COOLED REACTORS; METALS; NATIONAL ORGANIZATIONS; OXIDES; OXYGEN COMPOUNDS; PHASE TRANSFORMATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR SHUTDOWN; REACTORS; SAFETY; SHUTDOWN; SOLS; URANIUM COMPOUNDS; URANIUM OXIDES; US AEC; US DOE; US ERDA; US ORGANIZATIONS