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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Main Authors: Allen, M.D., Pitch, M. (Sandia National Labs., Albuquerque, NM (USA)), Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA))
Other Authors: U.S. Nuclear Regulatory Commission
Format: Report
Language:English
Published: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research 1990
Subjects:
Online Access:https://doi.org/10.2172/6978726
https://digital.library.unt.edu/ark:/67531/metadc1190882/
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spelling 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
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