Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus...
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Sandia National Laboratories
1991
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ftunivnotexas:info:ark/67531/metadc1058322 2023-05-15T18:29:14+02:00 Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests Allen, M.D. Pilch, M. Brockmann, J.E. Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)) Sweet, D.W. (AEA Technology, Winfrith (United Kingdom)) United States. Department of Energy. 1991-08-01 Pages: (249 p) Text https://doi.org/10.2172/5081015 https://digital.library.unt.edu/ark:/67531/metadc1058322/ English eng Sandia National Laboratories other: DE92001670 rep-no: SAND-90-2138 grantno: AC04-76DP00789 doi:10.2172/5081015 osti: 5081015 https://digital.library.unt.edu/ark:/67531/metadc1058322/ ark: ark:/67531/metadc1058322 Heat Transfer Bwr Type Reactors Reactor Vessels Reactor Components Accidents Oxidation Transition Elements Computer Calculations Gas Analysis Chemical Reaction Kinetics Reactor Cooling Systems 22 General Studies Of Nuclear Reactors Reactor Accidents Energy Systems Chemical Reactions Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety 21 Specific Nuclear Reactors And Associated Plants Data Reaction Kinetics Fluid Mechanics Heating Aerosols Oxygen Sols Water Cooled Reactors Kinetics Containment Size Iron Reactor Instrumentation Particle Size Reactors Temperature Measurement Test Facilities K Codes Mechanics Reactor Safety Cooling Systems Experiment Planning Engineered Safety Systems Hydraulics Pwr Type Reactors Blowdown Planning Pressurization Experimental Data Energy Transfer Enriched Uranium Reactors Elements Metals Hydrogen Computer Codes Corium 210100 -- Power Reactors Nonbreeding Light-Water Moderated Boiling Water Cooled Numerical Data Thermal Reactors Information Dispersions Pressure Measurement Power Reactors Data Acquisition Nonmetals Colloids Containment Systems 210200 -- Power Reactors Nonboiling Water Cooled Safety C Codes Containers Report 1991 ftunivnotexas https://doi.org/10.2172/5081015 2018-02-10T23:11:21Z Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus with identical initial conditions, except that the Surtsey test vessel contained air in DCH-3 and argon in DCH-4. Inerting the vessel with argon eliminated chemical reactions between metallic debris and oxygen. Thus, a comparison of the pressure response in DCH-3 and DCH-4 gave an indication of the DCH contribution due to metal/oxygen reactions. 44 refs., 110 figs., 43 tabs. Report Surtsey University of North Texas: UNT Digital Library Surtsey ENVELOPE(-20.608,-20.608,63.301,63.301) |
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collection |
University of North Texas: UNT Digital Library |
op_collection_id |
ftunivnotexas |
language |
English |
topic |
Heat Transfer Bwr Type Reactors Reactor Vessels Reactor Components Accidents Oxidation Transition Elements Computer Calculations Gas Analysis Chemical Reaction Kinetics Reactor Cooling Systems 22 General Studies Of Nuclear Reactors Reactor Accidents Energy Systems Chemical Reactions Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety 21 Specific Nuclear Reactors And Associated Plants Data Reaction Kinetics Fluid Mechanics Heating Aerosols Oxygen Sols Water Cooled Reactors Kinetics Containment Size Iron Reactor Instrumentation Particle Size Reactors Temperature Measurement Test Facilities K Codes Mechanics Reactor Safety Cooling Systems Experiment Planning Engineered Safety Systems Hydraulics Pwr Type Reactors Blowdown Planning Pressurization Experimental Data Energy Transfer Enriched Uranium Reactors Elements Metals Hydrogen Computer Codes Corium 210100 -- Power Reactors Nonbreeding Light-Water Moderated Boiling Water Cooled Numerical Data Thermal Reactors Information Dispersions Pressure Measurement Power Reactors Data Acquisition Nonmetals Colloids Containment Systems 210200 -- Power Reactors Nonboiling Water Cooled Safety C Codes Containers |
spellingShingle |
Heat Transfer Bwr Type Reactors Reactor Vessels Reactor Components Accidents Oxidation Transition Elements Computer Calculations Gas Analysis Chemical Reaction Kinetics Reactor Cooling Systems 22 General Studies Of Nuclear Reactors Reactor Accidents Energy Systems Chemical Reactions Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety 21 Specific Nuclear Reactors And Associated Plants Data Reaction Kinetics Fluid Mechanics Heating Aerosols Oxygen Sols Water Cooled Reactors Kinetics Containment Size Iron Reactor Instrumentation Particle Size Reactors Temperature Measurement Test Facilities K Codes Mechanics Reactor Safety Cooling Systems Experiment Planning Engineered Safety Systems Hydraulics Pwr Type Reactors Blowdown Planning Pressurization Experimental Data Energy Transfer Enriched Uranium Reactors Elements Metals Hydrogen Computer Codes Corium 210100 -- Power Reactors Nonbreeding Light-Water Moderated Boiling Water Cooled Numerical Data Thermal Reactors Information Dispersions Pressure Measurement Power Reactors Data Acquisition Nonmetals Colloids Containment Systems 210200 -- Power Reactors Nonboiling Water Cooled Safety C Codes Containers Allen, M.D. Pilch, M. Brockmann, J.E. Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)) Sweet, D.W. (AEA Technology, Winfrith (United Kingdom)) Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
topic_facet |
Heat Transfer Bwr Type Reactors Reactor Vessels Reactor Components Accidents Oxidation Transition Elements Computer Calculations Gas Analysis Chemical Reaction Kinetics Reactor Cooling Systems 22 General Studies Of Nuclear Reactors Reactor Accidents Energy Systems Chemical Reactions Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety 21 Specific Nuclear Reactors And Associated Plants Data Reaction Kinetics Fluid Mechanics Heating Aerosols Oxygen Sols Water Cooled Reactors Kinetics Containment Size Iron Reactor Instrumentation Particle Size Reactors Temperature Measurement Test Facilities K Codes Mechanics Reactor Safety Cooling Systems Experiment Planning Engineered Safety Systems Hydraulics Pwr Type Reactors Blowdown Planning Pressurization Experimental Data Energy Transfer Enriched Uranium Reactors Elements Metals Hydrogen Computer Codes Corium 210100 -- Power Reactors Nonbreeding Light-Water Moderated Boiling Water Cooled Numerical Data Thermal Reactors Information Dispersions Pressure Measurement Power Reactors Data Acquisition Nonmetals Colloids Containment Systems 210200 -- Power Reactors Nonboiling Water Cooled Safety C Codes Containers |
description |
Two experiments, DCH-3 and DCH-4, were performed at the Surtsey test facility to investigate phenomena associated with a high-pressure melt ejection (HPME) reactor accident sequence resulting in direct containment heating (DCH). These experiments were performed using the same experimental apparatus with identical initial conditions, except that the Surtsey test vessel contained air in DCH-3 and argon in DCH-4. Inerting the vessel with argon eliminated chemical reactions between metallic debris and oxygen. Thus, a comparison of the pressure response in DCH-3 and DCH-4 gave an indication of the DCH contribution due to metal/oxygen reactions. 44 refs., 110 figs., 43 tabs. |
author2 |
United States. Department of Energy. |
format |
Report |
author |
Allen, M.D. Pilch, M. Brockmann, J.E. Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)) Sweet, D.W. (AEA Technology, Winfrith (United Kingdom)) |
author_facet |
Allen, M.D. Pilch, M. Brockmann, J.E. Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States)) Sweet, D.W. (AEA Technology, Winfrith (United Kingdom)) |
author_sort |
Allen, M.D. |
title |
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
title_short |
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
title_full |
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
title_fullStr |
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
title_full_unstemmed |
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests |
title_sort |
experimental results of direct containment heating by high-pressure melt ejection into the surtsey vessel: the dch-3 and dch-4 tests |
publisher |
Sandia National Laboratories |
publishDate |
1991 |
url |
https://doi.org/10.2172/5081015 https://digital.library.unt.edu/ark:/67531/metadc1058322/ |
long_lat |
ENVELOPE(-20.608,-20.608,63.301,63.301) |
geographic |
Surtsey |
geographic_facet |
Surtsey |
genre |
Surtsey |
genre_facet |
Surtsey |
op_relation |
other: DE92001670 rep-no: SAND-90-2138 grantno: AC04-76DP00789 doi:10.2172/5081015 osti: 5081015 https://digital.library.unt.edu/ark:/67531/metadc1058322/ ark: ark:/67531/metadc1058322 |
op_doi |
https://doi.org/10.2172/5081015 |
_version_ |
1766212072582938624 |