Experimental results of an integral effects test in a zion-like geometry to investigate the effect of a classically inert atmosphere on direct containment heating: The IET-5 experiment
- Sandia National Labs., Albuquerque, NM (United States)
- Ktech Corp., Albuquerque, NM (United States)
The fifth experiment of the Integral Effects Test (IET-5) series was conducted to investigate the effects of high pressure melt ejection on direct containment heating. Scale models of the Zion reactor pressure vessel (RPV), cavity, instrument tunnel, and subcompartment structures were constructed in the Surtsey Test Facility at Sandia National Laboratories. The RPV was modeled 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 hemispherical bottom head containing a graphite limiter plate with a 4-cm exit hole to simulate the ablated hole in the RPV bottom head that would be formed by ejection of an instrument guide tube in a severe nuclear power plant accident. The cavity contained 3.48 kg of water, and the basement floor inside the crane wall contained 71 kg of water, which corresponded to condensate levels in the Zion plant. A 43-kg initial charge of iron oxide/aluminium/chromium thermite was used to simulate corium debris on the bottom head of the RPV. Molten them-lite was ejected by 6.0 MPa of steam into the reactor cavity.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6669805
- Report Number(s):
- SAND-92-1623; ON: DE93005912
- Country of Publication:
- United States
- Language:
- English
Similar Records
Results of an experiment in a Zion-like geometry to investigate the effect of water on the containment basement floor on direct containment heating (DCH) in the Surtsey Test Facility: The IET-4 test
An Integral Effects Test to investigate the effects of condensate levels of water and preexisting hydrogen on direct containment heating in the Surtsey Test Facility. The IET-7 experiment
Related Subjects
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BLOWDOWN
CONTAINERS
CONTAINMENT
CORIUM
DATA
ENRICHED URANIUM REACTORS
EXPERIMENTAL DATA
GAS ANALYSIS
HEATING
INERT ATMOSPHERE
INFORMATION
NUMERICAL DATA
POWER REACTORS
PRESSURE MEASUREMENT
PRESSURE VESSELS
PWR TYPE REACTORS
REACTORS
SCALE MODELS
STRUCTURAL MODELS
TESTING
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZION-1 REACTOR
ZION-2 REACTOR