Experimental results of tests to investigate the effects of hole diameter resulting from bottom head failure on Direct Containment Heating (DCH) in the Surtsey Test Facility
- 1. Sandia National Labs., Albuquerque, NM (United States)
- 2. Ktech Corp., Albuquerque, NM (United States)
Description
The WC-1 and WC-3 experiments were conducted using a dry, 1:10 linear scale model of the Zion reactor cavity to obtain baseline data for comparison to future experiments that will have water in the cavity. WC-1 and WC-3 were performed with similar initial conditions except for the exit hole between the melt generator and the scaled model of the reactor cavity. For both experiments the molten core debris was simulated by a thermitically generated melt formed from 50 kg of iron oxide/aluminum/chromium powders. After the thermite was ignited in WC-1, the melt was forcibly ejected by 374 moles of slightly superheated steam at an initial driving pressure of 4.6 MPa through an exit hole with an actual diameter of 4.14 cm into the scaled model of the reactor cavity. In WC-3, the molten thermite was ejected by 300 moles of slightly superheated steam at an initial driving pressure of 3.8 MPa through an exit hole with an actual diameter of 10.1 cm into the scaled model of the reactor cavity. Because of the larger exit hole diameter, WC-3 had a shorter blowdown time than WC-1, 0.8's compared to 3.0's. WC-3 also had a higher debris velocity than WC-1, 54 m/s compared to 17.5 m/s. Posttest sieve analysis of debris recovered from the Surtsey vessel gave identical results in WC-1 and WC-3 for the sieve mass median particle diameter, i.e. 1.45 mm. The total mass ejected into the Surtsey vessel in WC-3 was 45.0 kg compared to 47.9 kg in WC-1. The peak pressure increase in Surtsey due to the high-pressure melt ejection (HPME) was 0.275 MPa in WC-3 and 0.272 in WC-1. Steam/metal reactions produced 181 moles of of hydrogen in WC-3 and 145 moles of hydrogen in WC-1
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92011519; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Additional titles
- Subtitle (English)
- The WC-1 and WC-3 Tests
Publishing Information
- Imprint Pagination
- 52 p.
- Report number
- SAND--91-2153
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23059560
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Numerical Data
- Descriptors DEI
- CONTAINMENT; CORIUM; EXPERIMENTAL DATA; FAILURES; HEAT TRANSFER; HEATING; HYDRAULICS; MELTDOWN; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR SAFETY; SCALE MODELS; SIMULATION; TEST FACILITIES; ZION-1 REACTOR; ZION-2 REACTOR
- Descriptors DEC
- ACCIDENTS; DATA; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; INFORMATION; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; STRUCTURAL MODELS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC04-76DP00789
- Funding organization
- USDOE, Washington, DC (United States).