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...

Full description

Bibliographic Details
Main Authors: 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))
Other Authors: United States. Department of Energy.
Format: Report
Language:English
Published: Sandia National Laboratories 1991
Subjects:
Online Access:https://doi.org/10.2172/5081015
https://digital.library.unt.edu/ark:/67531/metadc1058322/
id ftunivnotexas:info:ark/67531/metadc1058322
record_format openpolar
spelling 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)
institution Open Polar
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