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
This document discusses the fourth experiment of the Integral Effects Test (IET-4) series which was conducted to investigate the effects of high pressure melt ejection on direct containment heating. Scale models (1:10) of the Zion reactor pressure vessel (RPV), cavity, instrument tunnel, and subcomp...
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ftosti:oai:osti.gov:10183813 2023-07-30T04:07:10+02:00 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 Allen, M.D. Blanchat, T.K. Pilch, M. Nichols, R.T. 2010-02-18 application/pdf http://www.osti.gov/servlets/purl/10183813 https://www.osti.gov/biblio/10183813 https://doi.org/10.2172/10183813 unknown http://www.osti.gov/servlets/purl/10183813 https://www.osti.gov/biblio/10183813 https://doi.org/10.2172/10183813 doi:10.2172/10183813 22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS PWR TYPE REACTORS CONTAINMENT HEATING TEST FACILITIES CORIUM WATER STEAM EXPLOSIONS ZION-1 REACTOR ZION-2 REACTOR CHEMICAL REACTIONS HEAT TRANSFER HYDRAULICS REACTOR SAFETY 2010 ftosti https://doi.org/10.2172/10183813 2023-07-11T11:01:42Z This document discusses the fourth experiment of the Integral Effects Test (IET-4) series which was conducted to investigate the effects of high pressure melt ejection on direct containment heating. Scale models (1:10) 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 limitor plate with a 3.5-cm exit hole to simulate the ablated hole in the RPV bottom head that would be tonned by tube ejection in a severe nuclear power plant 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 43-kg initial charge of iron oxide/aluminum/chromium thermite was used to simulate corium debris on the bottom head of the RPV. Molten thermite was ejected into the scaled reactor cavity by 6.7 MPa steam. IET-4 replicated the third experiment in the IET series (IET-3), except the Surtsey vessel contained slightly more preexisting oxygen (9.6 mol.% vs. 9.0 mol.%), and water was placed on the basement floor inside the crane wall. The cavity pressure measurements showed that a small steam explosion occurred in the cavity at about the same time as the steam explosion in IET-1. The oxygen in the Surtsey vessel in IET-4 resulted in a vigorous hydrogen bum, which caused a significant increase in the peak pressure, 262 kPa compared to 98 kPa in the IET-1 test. EET-3, with similar pre-existing oxygen concentrations, also had a large peak pressure of 246 kPa. Other/Unknown Material Surtsey SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy) Surtsey ENVELOPE(-20.608,-20.608,63.301,63.301) |
institution |
Open Polar |
collection |
SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy) |
op_collection_id |
ftosti |
language |
unknown |
topic |
22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS PWR TYPE REACTORS CONTAINMENT HEATING TEST FACILITIES CORIUM WATER STEAM EXPLOSIONS ZION-1 REACTOR ZION-2 REACTOR CHEMICAL REACTIONS HEAT TRANSFER HYDRAULICS REACTOR SAFETY |
spellingShingle |
22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS PWR TYPE REACTORS CONTAINMENT HEATING TEST FACILITIES CORIUM WATER STEAM EXPLOSIONS ZION-1 REACTOR ZION-2 REACTOR CHEMICAL REACTIONS HEAT TRANSFER HYDRAULICS REACTOR SAFETY Allen, M.D. Blanchat, T.K. Pilch, M. Nichols, R.T. 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 |
topic_facet |
22 GENERAL STUDIES OF NUCLEAR REACTORS 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS PWR TYPE REACTORS CONTAINMENT HEATING TEST FACILITIES CORIUM WATER STEAM EXPLOSIONS ZION-1 REACTOR ZION-2 REACTOR CHEMICAL REACTIONS HEAT TRANSFER HYDRAULICS REACTOR SAFETY |
description |
This document discusses the fourth experiment of the Integral Effects Test (IET-4) series which was conducted to investigate the effects of high pressure melt ejection on direct containment heating. Scale models (1:10) 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 limitor plate with a 3.5-cm exit hole to simulate the ablated hole in the RPV bottom head that would be tonned by tube ejection in a severe nuclear power plant 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 43-kg initial charge of iron oxide/aluminum/chromium thermite was used to simulate corium debris on the bottom head of the RPV. Molten thermite was ejected into the scaled reactor cavity by 6.7 MPa steam. IET-4 replicated the third experiment in the IET series (IET-3), except the Surtsey vessel contained slightly more preexisting oxygen (9.6 mol.% vs. 9.0 mol.%), and water was placed on the basement floor inside the crane wall. The cavity pressure measurements showed that a small steam explosion occurred in the cavity at about the same time as the steam explosion in IET-1. The oxygen in the Surtsey vessel in IET-4 resulted in a vigorous hydrogen bum, which caused a significant increase in the peak pressure, 262 kPa compared to 98 kPa in the IET-1 test. EET-3, with similar pre-existing oxygen concentrations, also had a large peak pressure of 246 kPa. |
author |
Allen, M.D. Blanchat, T.K. Pilch, M. Nichols, R.T. |
author_facet |
Allen, M.D. Blanchat, T.K. Pilch, M. Nichols, R.T. |
author_sort |
Allen, M.D. |
title |
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 |
title_short |
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 |
title_full |
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 |
title_fullStr |
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 |
title_full_unstemmed |
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 |
title_sort |
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 |
publishDate |
2010 |
url |
http://www.osti.gov/servlets/purl/10183813 https://www.osti.gov/biblio/10183813 https://doi.org/10.2172/10183813 |
long_lat |
ENVELOPE(-20.608,-20.608,63.301,63.301) |
geographic |
Surtsey |
geographic_facet |
Surtsey |
genre |
Surtsey |
genre_facet |
Surtsey |
op_relation |
http://www.osti.gov/servlets/purl/10183813 https://www.osti.gov/biblio/10183813 https://doi.org/10.2172/10183813 doi:10.2172/10183813 |
op_doi |
https://doi.org/10.2172/10183813 |
_version_ |
1772820312690262016 |