Coolability of UO2 debris beds in pressurized water pools: DCC-1 and DCC-2 experiment results
Description
DCC-1 and DCC-2 (Degraded Core Coolability) have provided the first in-pile data for water-urania dryout heat flux and quench behavior. DCC-1, designed to test the laminar flow region of dryout, has displayed unexpected results. while the dryout fluxes at one atmosphere are approximately those predicted by many of the models, the pressure dependence of the dryout data is predicted by none of the models. The quench behavior of DCC-1 displays none of the fingering observed in out-of-pile experiments. The quench times extend for hours. The DCC-2 dryout data conforms in magnitude and pressure dependence with several of the models. In addition to global dryouts, in which the dry zone extends across the width of the bed, local dryouts were observed. These are zones of lower than average permeability which dry out and achieve stable temperatures without eliminating coolant flow to the bottom of the bed. The quench times in DCC-2 are only a few minutes long. Fingering, modified by the radially varying temperature of the dry particles, was observed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02; 3 as DE84017005.
Files
Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- SAND--84-1837C
Conference
- Title
- 5. information exchange meeting on debris coolability.
- Dates
- 7-9 Nov 1984.
- Place
- Los Angeles, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16054663
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACPR REACTOR; COOLING; CORIUM; DRYOUT; REACTOR ACCIDENTS; URANIUM DIOXIDE
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; CHALCOGENIDES; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MIXED SPECTRUM REACTORS; OXIDES; OXYGEN COMPOUNDS; PULSED REACTORS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-841174--6.