The Integral Effects Test (IET-1) in the Surtsey Test Facility
Description
The first experiment of the Integral Effects Test (IET-1) series was conducted to investigate the effects of high pressure melt ejection (HPME) on direct containment heating (DCH). A 1:10 linear scale model of the Zion reactor pressure vessel (RPV), cavity, instrument tunnel, and subcompartment structures were constructed in the Surtsey Test Facility at Sandia National Laboratories (SNL). The RPV was modelled with a melt generator that consisted of a steel pressure barrier, a cast MgO crucible, and a thin steel inner liner. The melt generator/crucible had a semi-hemispherical bottom head containing a graphite limitor plate with a 3.5 cm exit hole to simulate the ablated hole in the RPV bottom head that would be formed by tube ejection in a severe nuclear power plant (NPP) accident. The reactor cavity model contained 3.48 kg of water with a depth of 0.9 cm that corresponded to condensate levels in the Zion plant. A steam driven iron oxide/aluminum/chromium thermite was used to simulate HPME. A relatively small steam explosion occurred in the cavity during IET-1. Steam blowthrough entrained debris into the Surtsey vessel resulting in a peak pressure increase in Surtsey of 98 kPa. The Surtsey vessel had been previously inerted with N2. The total debris mass ejected into the Surtsey vessel was 43 kg. The hydrogen concentration was 3.1 mol.% in the vessel at equilibrium. The concentration measured inside the subcompartment structures immediately following HPME transient was 20.7 mol.% H2. 4 refs., 17 figs., 5 tabs
Availability note (English)
MF available from INIS under the Report Number; OSTI as DE92004355; NTIS; INIS; US Govt. Printing Office Dep.
Files
Additional details
Publishing Information
- Imprint Pagination
- 25 p.
- Report number
- SAND--91-2613C
Conference
- Title
- 1991 water reactor safety meeting.
- Dates
- 28-30 Oct 1991.
- Place
- Washington, DC (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23031969
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; CONTAINMENT; CORIUM; GAS ANALYSIS; HEAT TRANSFER; HEATING; HYDRAULICS; MELTDOWN; PRESSURE VESSELS; SCALE MODELS; SIMULATION; TEMPERATURE MEASUREMENT; TEST FACILITIES; ZION-1 REACTOR; ZION-2 REACTOR
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; 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).
- Secondary number(s)
- CONF-9110210--4.