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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Main Authors: Allen, M.D., Blanchat, T.K., Pilch, M., Nichols, R.T.
Language:unknown
Published: 2010
Subjects:
Online Access:http://www.osti.gov/servlets/purl/10183813
https://www.osti.gov/biblio/10183813
https://doi.org/10.2172/10183813
id ftosti:oai:osti.gov:10183813
record_format openpolar
spelling 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
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