Interaction of hot solid core debris with concrete

Technical Report · Sun Jun 01 04:00:00 EDT 1986

DOI:https://doi.org/10.2172/5203250· OSTI ID:5203250

Copus, E. R.; Bradley, D. R.

The Hot Solid program is intended to measure, model, and assess the thermal, gas evolution, and fission product source terms produced as a consequence of hot, solid, core debris-concrete interactions. Two preliminary experiments, HSS-1 and HSS-3, were performed in order to compare hot solid UO/sub 2/-concrete and hot solid steel-concrete interactions. The HSS-1 experiment ablated 6 cm of limestone-common sand concrete in a little more than three hours using a 9 kg slug of 304 stainless steel at an average debris temperature of 1350/sup 0/C. The HSS-3 experiment ablated 6.5 cm of limestone-common sand concrete in four hours using a 10 kg slug of 80% UO/sub 2/-20% ZrO/sub 2/ at an average debris temperature of 1650/sup 0/C. Both experiments were inductively heated and contained in a 22 cm alumina sleeve to simulate one-dimensional axial erosion. The HOTROX computer code model was evaluated using the results from the HSS tests. HOTROX is a 1-D concrete ablation model that calculates transient conduction and gas release in the concrete as well as heatup of the hot solid slug. Using the HSS-1 power input history and geometry, HOTROX calculates 6.2 cm of concrete erosion in 200 minutes. Using the HSS-3 input conditions, HOTROX predicts 6.8 cm of erosion in 190 minutes. These results compare favorably with the experimental erosion rates. The calculated thermal response of the concrete is also close to experimentally measured values. The information from the Hot Solid Program will be used both to expand the post-accident phenomena data base and to extend the range of applicability of current accident analysis computer models such as CORCON and CONTAIN.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 5203250
• Report Number(s): NUREG/CR-4558; SAND-85-1739; ON: TI86015849
• Country of Publication: United States
• Language: English

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Erosion
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ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BUILDING MATERIALS
CHALCOGENIDES
COMPUTER CODES
COMPUTERIZED SIMULATION
CONCRETES
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FISSION PRODUCTS
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IRON BASE ALLOYS
ISOTOPES
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RADIOACTIVE MATERIALS
REACTOR ACCIDENTS
REACTOR SAFETY EXPERIMENTS
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STEELS
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URANIUM DIOXIDE
URANIUM OXIDES