Results of fission product release from intermediate-scale MCCI (molten core-concrete interaction) tests
A program of reactor-material molten core-concrete interaction (MCCI) tests and related analyses are under way at Argonne National Laboratory under sponsorship of the Electric Power Research Institute (EPRI). The particular objective of these tests is to provide data pertaining to the release of nonvolatile fission products such as La, Ba, and Sr, plus other aerosol materials, from the coupled thermal-hydraulic and chemical processes of the MCCI. The first stages of the program involving small and intermediate-scale tests have been completed. Three small-scale tests (/approximately/5 kg corium) and nine intermediate-scale tests (/approximately/30 kg corium) were performed between September 1985 and September 1987. Real reactor materials were used in these tests. Sustained internal heat generation at nominally 1 kW per kg of melt was provided by direct electrical heating of the corium mixture. MCCI tests were performed with both fully and partially oxidized corium mixtures that contained a variety of nonradioactive materials such as La/sub 2/O/sub 3/, BaO, and SrO to represent fission products. Both limestone/common sand and basaltic concrete basemats were used. The system was instrumented for characterization of the thermal hydraulic, chemical, gas release, and aerosol release processes.
- Research Organization:
- Argonne National Lab., IL (USA); Electric Power Research Inst., Palo Alto, CA (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6779936
- Report Number(s):
- CONF-881014-11; ON: DE89000596
- Resource Relation:
- Conference: International European Nuclear Society/American Nuclear Society meeting on thermal reactor safety, Avignon, France, 2 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
CONCRETES
FLUID-STRUCTURE INTERACTIONS
CORIUM
MELTDOWN
FISSION PRODUCT RELEASE
AEROSOLS
BARIUM
CHEMICAL ANALYSIS
FISSION PRODUCTS
HEAT TRANSFER
HYDRAULICS
LANTHANUM
RADIOACTIVE EFFLUENTS
REACTOR SAFETY
SCALE MODELS
STRONTIUM
TEST FACILITIES
TESTING
ACCIDENTS
ALKALINE EARTH METALS
BUILDING MATERIALS
COLLOIDS
DISPERSIONS
ELEMENTS
ENERGY TRANSFER
FLUID MECHANICS
ISOTOPES
MATERIALS
MECHANICS
METALS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RARE EARTHS
REACTOR ACCIDENTS
SAFETY
SOLS
STRUCTURAL MODELS
WASTES
220900* - Nuclear Reactor Technology- Reactor Safety
220502 - Nuclear Reactor Technology- Environmental Aspects- Radioactive Effluents