Core-concrete interactions using molten UO sub 2 with zirconium on a basaltic basemat: The SURC-2 experiment

Technical Report · Sat Aug 01 04:00:00 EDT 1992

DOI:https://doi.org/10.2172/7002194· OSTI ID:7002194

Copus, E R; Brockmann, J E; Simpson, R B; Lucero, D A ^[1]; Blose, R E ^[2]

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1. Sandia National Labs., Albuquerque, NM (United States)
2. Ktech Corp., Albuquerque, NM (United States)

An inductively heated experiment, SURC-2, using prototypic U0{sub 2}-ZrO{sub 2} materials was executed as part of the Integral Core-Concrete Interactions Experiments Program. The purpose of this experimental program was to measure and assess the variety of source terms produced during core debris/concrete interactions. These source terms include thermal energy released to both the reactor basemat and the containment environment, as well as flammable gas, condensable vapor and toxic or radioactive aerosols generated during the course of a severe reactor accident. The SURC-2 experiment eroded a total of 35 cm of basaltic concrete during 160 minutes of sustained interaction using 203.9 kg of prototypic U0{sub 2}-ZrO{sub 2} core debris material that included 18 kg of Zr metal and 3.4 kg of fission product simulants. The meltpool temperature ranged from 2400--1900{degrees}C during the first 50 minutes of the test followed by steady temperatures of 1750--1800{degrees}C during the middle portion of the test and increased temperatures of 1800--1900{degrees}C during the final 50 minutes of testing. The total erosion during the first 50 minutes was 15 cm with an additional 7 cm during the middle part of the test and 13 cm of ablation during the final 50 minutes. Comprehensive gas flowrates, gas compositions, and aerosol release rates were also measured during the SURC-2 test. When combined with the SURC-1 results, SURC-2 forms a complete data base for prototypic U0{sub 2}-ZrO{sub 2} core debris interactions with concrete.

• 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: 7002194
• Report Number(s): NUREG/CR-5564; SAND--90-1022; ON: TI92040824
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
36 MATERIALS SCIENCE
360604 -- Materials-- Corrosion
Erosion
& Degradation
ACCIDENTS
ACTINIDE COMPOUNDS
AEROSOLS
ALKALINE EARTH METAL COMPOUNDS
BUILDING MATERIALS
CHALCOGENIDES
COLLOIDS
CONCRETES
DEHYDRATION
DISPERSIONS
EROSION
GASEOUS WASTES
MAGNESIUM COMPOUNDS
MAGNESIUM OXIDES
MATERIALS
MEASURING INSTRUMENTS
MELTDOWN
MELTING
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
SOLS
TRANSITION ELEMENT COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WASTES
ZIRCONIUM COMPOUNDS
ZIRCONIUM OXIDES