Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant

The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct...

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Main Authors: Blanchat, T. K., Allen, M. D., Pilch, M. M., Nichols, R. T.
Other Authors: U.S. Nuclear Regulatory Commission
Format: Report
Language:English
Published: U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. 1994
Subjects:
Online Access:https://doi.org/10.2172/10165960
https://digital.library.unt.edu/ark:/67531/metadc1338797/
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author Blanchat, T. K.
Allen, M. D.
Pilch, M. M.
Nichols, R. T.
author2 U.S. Nuclear Regulatory Commission
author_facet Blanchat, T. K.
Allen, M. D.
Pilch, M. M.
Nichols, R. T.
author_sort Blanchat, T. K.
collection University of North Texas: UNT Digital Library
description The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct containment heating (DCH) phenomena on the containment load. High-temperature, chemically reactive melt (thermite) is ejected by high-pressure steam into a scale model of a reactor cavity. Debris is entrained by the steam blowdown into a containment model where specific phenomena, such as the effect of subcompartment structures, prototypic air/steam/hydrogen atmospheres, and hydrogen generation and combustion, can be studied. Four Integral Effects Tests (IETs) have been performed with scale models of the Surry NPP to investigate DCH phenomena. The 1/61{sup th} scale Integral Effects Tests (IET-9, IET-10, and IET-11) were conducted in CTRF, which is a 1/6{sup th} scale model of the Surry reactor containment building (RCB). The 1/10{sup th} scale IET test (IET-12) was performed in the Surtsey vessel, which had been configured as a 1/10{sup th} scale Surry RCB. Scale models were constructed in each of the facilities of the Surry structures, including the reactor pressure vessel, reactor support skirt, control rod drive missile shield, biological shield wall, cavity, instrument tunnel, residual heat removal platform and heat exchangers, seal table room and seal table, operating deck, and crane wall. This report describes these experiments and gives the results.
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genre Surtsey
genre_facet Surtsey
geographic Surtsey
geographic_facet Surtsey
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long_lat ENVELOPE(-20.608,-20.608,63.301,63.301)
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doi:10.2172/10165960
osti: 10165960
https://digital.library.unt.edu/ark:/67531/metadc1338797/
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spelling ftunivnotexas:info:ark/67531/metadc1338797 2025-01-17T01:01:25+00:00 Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant Blanchat, T. K. Allen, M. D. Pilch, M. M. Nichols, R. T. U.S. Nuclear Regulatory Commission 1994-06 202 p. Text https://doi.org/10.2172/10165960 https://digital.library.unt.edu/ark:/67531/metadc1338797/ English eng U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research. Sandia National Laboratories other: TI94015005 doi:10.2172/10165960 osti: 10165960 https://digital.library.unt.edu/ark:/67531/metadc1338797/ ark: ark:/67531/metadc1338797 Heat Transfer 210200 Hydraulics Dynamic Loads Chemical Reaction Kinetics Reactor Components 22 General Studies Of Nuclear Reactors Power Reactors Nonbreeding Light-Water Moderated Nonboiling Water Cooled 21 Specific Nuclear Reactors And Associated Plants Surry-2 Reactor Surry-1 Reactor Melting Radiation Heating Containment Reactor Safety Containment Buildings Surry-4 Reactor Corium 220900 Meltdown Hydrogen Combustion Scale Models Surry-3 Reactor Report 1994 ftunivnotexas https://doi.org/10.2172/10165960 2024-11-05T15:59:41Z The Containment Technology Test Facility (CTTF) and the Surtsey Test Facility at Sandia National Laboratories are used to perform scaled experiments that simulate High Pressure Melt Ejection accidents in a nuclear power plant (NPP). These experiments are designed to investigate the effects of direct containment heating (DCH) phenomena on the containment load. High-temperature, chemically reactive melt (thermite) is ejected by high-pressure steam into a scale model of a reactor cavity. Debris is entrained by the steam blowdown into a containment model where specific phenomena, such as the effect of subcompartment structures, prototypic air/steam/hydrogen atmospheres, and hydrogen generation and combustion, can be studied. Four Integral Effects Tests (IETs) have been performed with scale models of the Surry NPP to investigate DCH phenomena. The 1/61{sup th} scale Integral Effects Tests (IET-9, IET-10, and IET-11) were conducted in CTRF, which is a 1/6{sup th} scale model of the Surry reactor containment building (RCB). The 1/10{sup th} scale IET test (IET-12) was performed in the Surtsey vessel, which had been configured as a 1/10{sup th} scale Surry RCB. Scale models were constructed in each of the facilities of the Surry structures, including the reactor pressure vessel, reactor support skirt, control rod drive missile shield, biological shield wall, cavity, instrument tunnel, residual heat removal platform and heat exchangers, seal table room and seal table, operating deck, and crane wall. This report describes these experiments and gives the results. Report Surtsey University of North Texas: UNT Digital Library Surtsey ENVELOPE(-20.608,-20.608,63.301,63.301)
spellingShingle Heat Transfer
210200
Hydraulics
Dynamic Loads
Chemical Reaction Kinetics
Reactor Components
22 General Studies Of Nuclear Reactors
Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 Specific Nuclear Reactors And Associated Plants
Surry-2 Reactor
Surry-1 Reactor
Melting
Radiation Heating
Containment
Reactor Safety
Containment Buildings
Surry-4 Reactor
Corium 220900
Meltdown
Hydrogen
Combustion
Scale Models
Surry-3 Reactor
Blanchat, T. K.
Allen, M. D.
Pilch, M. M.
Nichols, R. T.
Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title_full Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title_fullStr Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title_full_unstemmed Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title_short Experiments to investigate direct containment heating phenomena with scaled models of the Surry Nuclear Power Plant
title_sort experiments to investigate direct containment heating phenomena with scaled models of the surry nuclear power plant
topic Heat Transfer
210200
Hydraulics
Dynamic Loads
Chemical Reaction Kinetics
Reactor Components
22 General Studies Of Nuclear Reactors
Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 Specific Nuclear Reactors And Associated Plants
Surry-2 Reactor
Surry-1 Reactor
Melting
Radiation Heating
Containment
Reactor Safety
Containment Buildings
Surry-4 Reactor
Corium 220900
Meltdown
Hydrogen
Combustion
Scale Models
Surry-3 Reactor
topic_facet Heat Transfer
210200
Hydraulics
Dynamic Loads
Chemical Reaction Kinetics
Reactor Components
22 General Studies Of Nuclear Reactors
Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
21 Specific Nuclear Reactors And Associated Plants
Surry-2 Reactor
Surry-1 Reactor
Melting
Radiation Heating
Containment
Reactor Safety
Containment Buildings
Surry-4 Reactor
Corium 220900
Meltdown
Hydrogen
Combustion
Scale Models
Surry-3 Reactor
url https://doi.org/10.2172/10165960
https://digital.library.unt.edu/ark:/67531/metadc1338797/