A demonstration experiment of steam-driven, high-pressure melt ejection
A steam blowdown test was performed at the Surtsey Direct Heating Test Facility to test the steam supply system and burst diaphragm arrangement that will be used in subsequent Surtsey Direct Containment Heating (DCH) experiments. Following successful completion of the steam blowdown test, the HIPS-1...
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Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research
1990
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ftunivnotexas:info:ark/67531/metadc1190882 2023-05-15T18:29:14+02:00 A demonstration experiment of steam-driven, high-pressure melt ejection Allen, M.D. Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA)) U.S. Nuclear Regulatory Commission 1990-08-01 Text https://doi.org/10.2172/6978726 https://digital.library.unt.edu/ark:/67531/metadc1190882/ English eng Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research Sandia National Laboratories other: TI90016113 rep-no: NUREG/CR-5373 rep-no: SAND--89-1135 grantno: AC04-76DP00789 doi:10.2172/6978726 osti: 6978726 https://digital.library.unt.edu/ark:/67531/metadc1190882/ ark: ark:/67531/metadc1190882 Heat Transfer Bwr Type Reactors Reactor Accidents Hydraulics Chemical Reaction Kinetics Oxides 22 General Studies Of Nuclear Reactors Computer Codes Demonstration Programs 21 Specific Nuclear Reactors And Associated Plants Fluid Mechanics Chalcogenides Transition Element Compounds Water Cooled Reactors Kinetics Simulation Containment Structural Models Accidents Iron Oxides Safety Reactors Temperature Measurement Test Facilities Mechanics Reactor Safety 210200 -- Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled Pwr Type Reactors Blowdown Energy Transfer Elements Meltdown Hydrogen Oxygen Compounds Corium 210100 -- Power Reactors Boiling Water Cooled Reaction Kinetics Pressure Measurement Iron Compounds Scale Models Nonmetals Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety Steam C Codes Report 1990 ftunivnotexas https://doi.org/10.2172/6978726 2020-01-18T23:09:00Z A steam blowdown test was performed at the Surtsey Direct Heating Test Facility to test the steam supply system and burst diaphragm arrangement that will be used in subsequent Surtsey Direct Containment Heating (DCH) experiments. Following successful completion of the steam blowdown test, the HIPS-10S (High-Pressure Melt Streaming) experiment was conducted to demonstrate that the technology to perform steam-driven, high-pressure melt ejection (HPME) experiments has been successfully developed. In addition, the HIPS-10S experiment was used to assess techniques and instrumentation design to create the proper timing of events in HPME experiments. This document discusses the results of this test. 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 Accidents Hydraulics Chemical Reaction Kinetics Oxides 22 General Studies Of Nuclear Reactors Computer Codes Demonstration Programs 21 Specific Nuclear Reactors And Associated Plants Fluid Mechanics Chalcogenides Transition Element Compounds Water Cooled Reactors Kinetics Simulation Containment Structural Models Accidents Iron Oxides Safety Reactors Temperature Measurement Test Facilities Mechanics Reactor Safety 210200 -- Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled Pwr Type Reactors Blowdown Energy Transfer Elements Meltdown Hydrogen Oxygen Compounds Corium 210100 -- Power Reactors Boiling Water Cooled Reaction Kinetics Pressure Measurement Iron Compounds Scale Models Nonmetals Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety Steam C Codes |
spellingShingle |
Heat Transfer Bwr Type Reactors Reactor Accidents Hydraulics Chemical Reaction Kinetics Oxides 22 General Studies Of Nuclear Reactors Computer Codes Demonstration Programs 21 Specific Nuclear Reactors And Associated Plants Fluid Mechanics Chalcogenides Transition Element Compounds Water Cooled Reactors Kinetics Simulation Containment Structural Models Accidents Iron Oxides Safety Reactors Temperature Measurement Test Facilities Mechanics Reactor Safety 210200 -- Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled Pwr Type Reactors Blowdown Energy Transfer Elements Meltdown Hydrogen Oxygen Compounds Corium 210100 -- Power Reactors Boiling Water Cooled Reaction Kinetics Pressure Measurement Iron Compounds Scale Models Nonmetals Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety Steam C Codes Allen, M.D. Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA)) A demonstration experiment of steam-driven, high-pressure melt ejection |
topic_facet |
Heat Transfer Bwr Type Reactors Reactor Accidents Hydraulics Chemical Reaction Kinetics Oxides 22 General Studies Of Nuclear Reactors Computer Codes Demonstration Programs 21 Specific Nuclear Reactors And Associated Plants Fluid Mechanics Chalcogenides Transition Element Compounds Water Cooled Reactors Kinetics Simulation Containment Structural Models Accidents Iron Oxides Safety Reactors Temperature Measurement Test Facilities Mechanics Reactor Safety 210200 -- Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled Pwr Type Reactors Blowdown Energy Transfer Elements Meltdown Hydrogen Oxygen Compounds Corium 210100 -- Power Reactors Boiling Water Cooled Reaction Kinetics Pressure Measurement Iron Compounds Scale Models Nonmetals Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety Steam C Codes |
description |
A steam blowdown test was performed at the Surtsey Direct Heating Test Facility to test the steam supply system and burst diaphragm arrangement that will be used in subsequent Surtsey Direct Containment Heating (DCH) experiments. Following successful completion of the steam blowdown test, the HIPS-10S (High-Pressure Melt Streaming) experiment was conducted to demonstrate that the technology to perform steam-driven, high-pressure melt ejection (HPME) experiments has been successfully developed. In addition, the HIPS-10S experiment was used to assess techniques and instrumentation design to create the proper timing of events in HPME experiments. This document discusses the results of this test. |
author2 |
U.S. Nuclear Regulatory Commission |
format |
Report |
author |
Allen, M.D. Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA)) |
author_facet |
Allen, M.D. Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)) Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA)) |
author_sort |
Allen, M.D. |
title |
A demonstration experiment of steam-driven, high-pressure melt ejection |
title_short |
A demonstration experiment of steam-driven, high-pressure melt ejection |
title_full |
A demonstration experiment of steam-driven, high-pressure melt ejection |
title_fullStr |
A demonstration experiment of steam-driven, high-pressure melt ejection |
title_full_unstemmed |
A demonstration experiment of steam-driven, high-pressure melt ejection |
title_sort |
demonstration experiment of steam-driven, high-pressure melt ejection |
publisher |
Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research |
publishDate |
1990 |
url |
https://doi.org/10.2172/6978726 https://digital.library.unt.edu/ark:/67531/metadc1190882/ |
long_lat |
ENVELOPE(-20.608,-20.608,63.301,63.301) |
geographic |
Surtsey |
geographic_facet |
Surtsey |
genre |
Surtsey |
genre_facet |
Surtsey |
op_relation |
other: TI90016113 rep-no: NUREG/CR-5373 rep-no: SAND--89-1135 grantno: AC04-76DP00789 doi:10.2172/6978726 osti: 6978726 https://digital.library.unt.edu/ark:/67531/metadc1190882/ ark: ark:/67531/metadc1190882 |
op_doi |
https://doi.org/10.2172/6978726 |
_version_ |
1766212075633246208 |