Actions for LMFBR source term experiments in the Fuel Aerosol Simulant Test (FAST) facility [electronic resource].
LMFBR source term experiments in the Fuel Aerosol Simulant Test (FAST) facility [electronic resource].
- Published
- Oak Ridge, Tenn. : Oak Ridge National Laboratory, 1985.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: 41 : digital, PDF file
- Additional Creators
- Oak Ridge National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The transport of uranium dioxide (UO/sub 2/) 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 (ORNL). The experiments were designed to provide a mechanistic basis for evaluating the radiological source term associated with a postulated, energetic core disruptive accident (CDA) in a liquid metal fast breeder reactor (LMFBR). Aerosol was generated by capacitor discharge vaporization of UO/sub 2/ 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 largest release was observed in the baseline experiment where the sample was vaporized above the sodium pool. In the nine ''undersodium'' experiments aerosol was generated beneath the surface of the pool at depths varying from 30 to 1060 mm. 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. 18 refs., 11 figs., 4 tabs.
- Report Numbers
- E 1.99:conf-850410-38
conf-850410-38 - Subject(s)
- Other Subject(s)
- Lmfbr Type Reactors
- Reactor Core Disruption
- Radioactive Aerosols
- Radioactivity Transport
- Bubbles
- Evaporation
- Forecasting
- Fuel-Coolant Interactions
- Reactor Cores
- Reactor Safety
- Sodium
- Test Facilities
- Transient Overpower Accidents
- Transients
- Uranium Dioxide
- Accidents
- Actinide Compounds
- Aerosols
- Alkali Metals
- Breeder Reactors
- Chalcogenides
- Colloids
- Dispersions
- Elements
- Epithermal Reactors
- Fast Reactors
- Fbr Type Reactors
- Liquid Metal Cooled Reactors
- Metals
- Oxides
- Oxygen Compounds
- Phase Transformations
- Reactor Accidents
- Reactor Components
- Reactors
- Safety
- Sols
- Uranium Compounds
- Uranium Oxides
- Note
- Published through SciTech Connect.
01/01/1985.
"conf-850410-38"
"TI85011428"
ANS/ENS fast reactor safety meeting, Knoxville, TN, USA, 21 Apr 1985.
Longest, A.W.; Petrykowski, J.C. - Funding Information
- AC05-84OR21400
View MARC record | catkey: 14371340