Core-concrete interactions using molten urania with zirconium on a limestone concrete basemat
- Sandia National Labs., Albuquerque, NM (United States)
- Ktech Corp., Albuquerque, NM (United States)
An inductively heated experiment SURC-1, using UO[sub 2]-ZrO[sub 2] material, was executed to measure and assess the thermal, gas, and aerosol source terms produced during core debris/concrete interactions. The SURC-1 experiment eroded a total of 27 cm of limestone concrete during 130 minutes of sustained interaction using 204.2 kg of molten prototypic UO[sub 2]-ZrO[sub 2] core debris material that included 18 kg of zr metal and 3.4 kg of fission product simulants. The melt pool temperature ranged from 2100 to 2400[degrees]C during the first 50 minutes of the test, followed by steady temperatures of 2000 to 2100[degrees]C during the middle portion of the test and temperatures of 1800 to 2000[degrees]C during the final 50 minutes of testing. The total erosion during the first 50 minutes was 16 cm with an additional 2 cm during the middle part of the test and 9 cm of ablation during the final 50 minutes. Aerosols were continuously released in concentrations ranging from 30 to 200 g/m[sup 3]. Comprehensive gas flow rates, gas compositions, and aerosol compositions were also measured during the SURC-1 test.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 7022699
- Report Number(s):
- NUREG/CR-5443; SAND--90-0087; ON: TI93001868
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AEROSOLS
BUILDING MATERIALS
CARBONATE ROCKS
CHALCOGENIDES
COLLOIDS
CONCRETES
CORIUM
DISPERSIONS
EROSION
EXPERIMENT PLANNING
INTERACTIONS
LIMESTONE
MATERIALS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXIDES
OXYGEN COMPOUNDS
PLANNING
POWER PLANTS
REACTOR ACCIDENTS
ROCKS
SEDIMENTARY ROCKS
SOLS
SOURCE TERMS
THERMAL POWER PLANTS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AEROSOLS
BUILDING MATERIALS
CARBONATE ROCKS
CHALCOGENIDES
COLLOIDS
CONCRETES
CORIUM
DISPERSIONS
EROSION
EXPERIMENT PLANNING
INTERACTIONS
LIMESTONE
MATERIALS
MELTDOWN
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
OXIDES
OXYGEN COMPOUNDS
PLANNING
POWER PLANTS
REACTOR ACCIDENTS
ROCKS
SEDIMENTARY ROCKS
SOLS
SOURCE TERMS
THERMAL POWER PLANTS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES