Postaccident heat removal: debris-bed experiments D-2 and D-3. [LMFBR]
The second and third of the fission-heated experiments simulating fast-reactor debris in liquid sodium have been performed in the Annular Core Pulse Reactor (ACPR). These experiments were designed to assess the natural cooling capability that liquid sodium may provide for particulate debris which might be produced by a severe core-disruptive accident. Enriched UO/sub 2/ particles submersed in liquid sodium were used and were subjected to power levels ranging up to 1.28 kW/kg of oxide while the bulk sodium temperatures varied from 673 to 873 K. The particles were irregular in shape and ranged in size from about 100 to 1,000 ..mu..m. The D-2 bed loading was 600 kg/m/sup 2/ of oxide and the D-3 loading was 900 kg/m/sup 2/.
- Research Organization:
- Sandia Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- EY-76-C-04-0789
- OSTI ID:
- 6494241
- Report Number(s):
- NUREG/CR-0421; SAND-78-1238
- Country of Publication:
- United States
- Language:
- English
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