Reactor Severe Accident Test Facility
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Argonne’s Large Scale Severe Accident Test Facility, Cell 4 and Cell 5
Our reactor containment houses an experiment platform for studying large-scale spreading of prototypical reactor materials containing uranium and zirconium. A thermite reaction generates “corium” (molten nuclear reactor core material) at temperatures up to ~2400°C, hot enough to melt through steel (Tmp ~1400°C). Roughly 300 kg of corium comprised chiefly of UO2 and ZrO2 is poured into a water pool where spreading occurs. Instrumentation determines the rate and extent of spreading, which is completed in seconds.
The containment once housed a zero-power research reactor. Its rugged construction makes it possible to safely conduct these spreading tests, the largest of their kind, involving large thermal and chemical energies along with radiological hazards.
Containment housing the severe accident test facility
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1 m-thick reinforced concrete walls & ceiling.
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45 kg TNT explosion rating.
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3.7 atm design over-pressure rating
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9.2 m x 12.2 m x 9.2 m high with 4500 kg crane.
Special containment features also allow us to test uranium thermites having zirconium metal that reacts with water to generate hydrogen. Up to 10 kg batches of thermite are tested for reaction temperature and pouring characteristics.
Selected Publications
- State-of-the-Art Report on Molten Corium Concrete Interaction and Ex-Vessel Molten Core Coolability
- M.T. Farmer, D. J. Kilsdonk, and R. W. Aeschlimann, Corium coolability under ex-vessel accident conditions for LWRs, Nuclear Engineering and Technology 41 5 575-602 2009
- S. Lomperski and M. T. Farmer, Performance testing of engineered corium cooling systems, Nuclear Engineering and Design, 243 311-320, 2012
- S. Lomperski and M. T. Farmer, Experimental evaluation of the water ingression mechanism for corium cooling, Nuclear Engineering and Design 237 905-917, 2007.