Core-concrete interactions using molten steel with zirconium on a basaltic basemat: The SURC-4 experiment
An experiment was performed in order to evaluate the additional effects of zirconium metal oxidation on core debris interactions using molten stainless steel as the core debris simulant. The SURC-4 experiment eroded a total of 25 cm of basalatic concrete during 62 minutes of sustained interaction. The meltpool temperatures during the test ranged from 1500/degree/C before zirconium addition to 1650/degree/C during the zirconium-steel-concrete phase of the test which lasted 42 minutes. Large increases in erosion rate, gas production, and aerosol release were also measured shortly after Zr metal was added to the melt. The data return from the test was outstanding and these results were subsequently used as input to an OECD code comparison exercise. 19 refs., 86 figs., 32 tabs.
- Research Organization:
- Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6306172
- Report Number(s):
- NUREG/CR-4994; SAND-87-2008; ON: TI89011629
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220502* -- Nuclear Reactor Technology-- Environmental Aspects-- Radioactive Effluents
220900 -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AEROSOLS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
AUSTENITIC STEELS
BUILDING MATERIALS
CHALCOGENIDES
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
COLLOIDS
COMPUTER CODES
CONCRETES
CONTAINMENT
CORIUM
CORROSION RESISTANT ALLOYS
DATA
DISPERSIONS
ELEMENTS
EXPERIMENTAL DATA
FISSION PRODUCTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
INFORMATION
IRON ALLOYS
IRON BASE ALLOYS
ISOTOPES
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
METALS
NICKEL ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
NUMERICAL DATA
O CODES
OXIDATION
OXIDES
OXYGEN COMPOUNDS
POWER PLANTS
RADIOACTIVE EFFLUENTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR ACCIDENTS
REACTOR SAFETY
SAFETY
SOLS
SOURCE TERMS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
TEMPERATURE EFFECTS
TEST FACILITIES
THERMAL POWER PLANTS
TRANSITION ELEMENTS
WASTES
ZIRCONIUM