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author Spencer, B. W.
Sienicki, J. J.
Sehgal, B. R.
Merilo, M.
author_facet Spencer, B. W.
Sienicki, J. J.
Sehgal, B. R.
Merilo, M.
author_sort Spencer, B. W.
collection University of North Texas: UNT Digital Library
description The results of a series of five experiments are described addressing the severity and mitigation of direct containment heating. The tests were performed in a 1:30 linear scale mockup of the Zion PWR containment system using a reactor-material corium melt consisting of 60% UO/sub 2/, 16% ZrO/sub 2/, 24% SSt at nominally 2800C initial temperature. A ''worst-case'' type test involving unimpeded corium dispersal through an air atmosphere in a closed vessel produced an atmosphere heatup of 323K, equivalent to a DCH efficiency of 62%. With the addition of structural features which impeded the corium dispersal, representative of dispersal pathway features at Zion, the DCH efficiency was reduced to 1--5%. (This important result is scale dependent and requires larger scale tests such as the SURTSEY program at SNL plus mechanistic modeling for application to the reactor system.) With the addition of water in the cavity region, there was no measurable heatup of the atmosphere. This was attributable to the vigorous codispersal of water with corium which prevented the temperature of the atmosphere from significantly exceeding T/sub sat/. In this case the DCH load was replaced by the more benign ''steam spike'' from corium quench. Significant oxidation of the corium constituents occurred in the tests, adding chemical energy to the system and producing hydrogen. Overall, the results suggest that with consideration of realistic, plant specific, mitigating features, DCH may be no worse and possibly far less severe than the previously examined steam spike. Implications for accident management are addressed. 17 refs., 7 figs., 4 tabs.
format Article in Journal/Newspaper
genre Surtsey
genre_facet Surtsey
geographic Surtsey
geographic_facet Surtsey
id ftunivnotexas:info:ark/67531/metadc1210917
institution Open Polar
language English
long_lat ENVELOPE(-20.608,-20.608,63.301,63.301)
op_collection_id ftunivnotexas
op_relation other: DE89007372
rep-no: CONF-881014-20
grantno: W-31109-ENG-38
osti: 6519463
https://digital.library.unt.edu/ark:/67531/metadc1210917/
ark: ark:/67531/metadc1210917
op_source International European Nuclear Society/American Nuclear Society meeting on thermal reactor safety, Avignon, France, 2 Oct 1988
publishDate 1988
publisher Argonne National Laboratory
record_format openpolar
spelling ftunivnotexas:info:ark/67531/metadc1210917 2025-01-17T01:01:26+00:00 Results of EPRI/ANL DCH investigations and model development Spencer, B. W. Sienicki, J. J. Sehgal, B. R. Merilo, M. 1988-01-01 14 pages Text https://digital.library.unt.edu/ark:/67531/metadc1210917/ English eng Argonne National Laboratory other: DE89007372 rep-no: CONF-881014-20 grantno: W-31109-ENG-38 osti: 6519463 https://digital.library.unt.edu/ark:/67531/metadc1210917/ ark: ark:/67531/metadc1210917 International European Nuclear Society/American Nuclear Society meeting on thermal reactor safety, Avignon, France, 2 Oct 1988 Heat Transfer Elements Chemical Reactions Enriched Uranium Reactors Oxidation Hydraulics 22 General Studies Of Nuclear Reactors Computer Codes Nonmetals 21 Specific Nuclear Reactors And Associated Plants Fluid Mechanics Heating Power Reactors S Codes Water Cooled Reactors Containment Structural Models Accidents Thermal Reactors Reactors Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety M Codes Mechanics Testing Reactor Safety 210200 -- Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled Pwr Type Reactors Blowdown Energy Transfer H Codes Hydrogen Loss Of Coolant Oxygen Compounds Corium Scale Models Zion-1 Reactor Hydrogen Compounds Zion-2 Reactor Water Safety C Codes Reactor Accidents Article 1988 ftunivnotexas 2020-05-09T22:08:19Z The results of a series of five experiments are described addressing the severity and mitigation of direct containment heating. The tests were performed in a 1:30 linear scale mockup of the Zion PWR containment system using a reactor-material corium melt consisting of 60% UO/sub 2/, 16% ZrO/sub 2/, 24% SSt at nominally 2800C initial temperature. A ''worst-case'' type test involving unimpeded corium dispersal through an air atmosphere in a closed vessel produced an atmosphere heatup of 323K, equivalent to a DCH efficiency of 62%. With the addition of structural features which impeded the corium dispersal, representative of dispersal pathway features at Zion, the DCH efficiency was reduced to 1--5%. (This important result is scale dependent and requires larger scale tests such as the SURTSEY program at SNL plus mechanistic modeling for application to the reactor system.) With the addition of water in the cavity region, there was no measurable heatup of the atmosphere. This was attributable to the vigorous codispersal of water with corium which prevented the temperature of the atmosphere from significantly exceeding T/sub sat/. In this case the DCH load was replaced by the more benign ''steam spike'' from corium quench. Significant oxidation of the corium constituents occurred in the tests, adding chemical energy to the system and producing hydrogen. Overall, the results suggest that with consideration of realistic, plant specific, mitigating features, DCH may be no worse and possibly far less severe than the previously examined steam spike. Implications for accident management are addressed. 17 refs., 7 figs., 4 tabs. Article in Journal/Newspaper Surtsey University of North Texas: UNT Digital Library Surtsey ENVELOPE(-20.608,-20.608,63.301,63.301)
spellingShingle Heat Transfer
Elements
Chemical Reactions
Enriched Uranium Reactors
Oxidation
Hydraulics
22 General Studies Of Nuclear Reactors
Computer Codes
Nonmetals
21 Specific Nuclear Reactors And Associated Plants
Fluid Mechanics
Heating
Power Reactors
S Codes
Water Cooled Reactors
Containment
Structural Models
Accidents
Thermal Reactors
Reactors
Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
M Codes
Mechanics
Testing
Reactor Safety
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
Pwr Type Reactors
Blowdown
Energy Transfer
H Codes
Hydrogen
Loss Of Coolant
Oxygen Compounds
Corium
Scale Models
Zion-1 Reactor
Hydrogen Compounds
Zion-2 Reactor
Water
Safety
C Codes
Reactor Accidents
Spencer, B. W.
Sienicki, J. J.
Sehgal, B. R.
Merilo, M.
Results of EPRI/ANL DCH investigations and model development
title Results of EPRI/ANL DCH investigations and model development
title_full Results of EPRI/ANL DCH investigations and model development
title_fullStr Results of EPRI/ANL DCH investigations and model development
title_full_unstemmed Results of EPRI/ANL DCH investigations and model development
title_short Results of EPRI/ANL DCH investigations and model development
title_sort results of epri/anl dch investigations and model development
topic Heat Transfer
Elements
Chemical Reactions
Enriched Uranium Reactors
Oxidation
Hydraulics
22 General Studies Of Nuclear Reactors
Computer Codes
Nonmetals
21 Specific Nuclear Reactors And Associated Plants
Fluid Mechanics
Heating
Power Reactors
S Codes
Water Cooled Reactors
Containment
Structural Models
Accidents
Thermal Reactors
Reactors
Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
M Codes
Mechanics
Testing
Reactor Safety
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
Pwr Type Reactors
Blowdown
Energy Transfer
H Codes
Hydrogen
Loss Of Coolant
Oxygen Compounds
Corium
Scale Models
Zion-1 Reactor
Hydrogen Compounds
Zion-2 Reactor
Water
Safety
C Codes
Reactor Accidents
topic_facet Heat Transfer
Elements
Chemical Reactions
Enriched Uranium Reactors
Oxidation
Hydraulics
22 General Studies Of Nuclear Reactors
Computer Codes
Nonmetals
21 Specific Nuclear Reactors And Associated Plants
Fluid Mechanics
Heating
Power Reactors
S Codes
Water Cooled Reactors
Containment
Structural Models
Accidents
Thermal Reactors
Reactors
Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
M Codes
Mechanics
Testing
Reactor Safety
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
Pwr Type Reactors
Blowdown
Energy Transfer
H Codes
Hydrogen
Loss Of Coolant
Oxygen Compounds
Corium
Scale Models
Zion-1 Reactor
Hydrogen Compounds
Zion-2 Reactor
Water
Safety
C Codes
Reactor Accidents
url https://digital.library.unt.edu/ark:/67531/metadc1210917/