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1
Experimental results of direct containment heating by high-pressure melt ejection into the Surtsey vessel: The DCH-3 and DCH-4 tests
by
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))
Published 1991
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2
A demonstration experiment of steam-driven, high-pressure melt ejection
by
Allen, M.D.
,
Pitch, M. (Sandia National Labs., Albuquerque, NM (USA))
,
Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA))
Published 1990
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3
Development and assessment of the CONTAIN hybrid flow solver
by
Murata, K. K.
,
Stamps, D. W.
Published 1997
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Select result number 4
4
Modeling direct containment heating phenomena with CONTAIN 1. 12
by
Griffith, R.O.
,
Russell, N.A.
,
Washington, K.E.
Published 1991
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Select result number 5
5
Results of EPRI/ANL DCH investigations and model development
by
Spencer, B. W.
,
Sienicki, J. J.
,
Sehgal, B. R.
,
Merilo, M.
Published 1988
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3
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2
Author
Allen, M.D.
2
Brockmann, J.E.
1
Griffith, R.O.
1
Merilo, M.
1
Murata, K. K.
1
Nichols, R.T. (Ktech Corp., Albuquerque, NM (USA))
1
Nichols, R.T. (Ktech Corp., Albuquerque, NM (United States))
1
Pilch, M.
1
Pitch, M. (Sandia National Labs., Albuquerque, NM (USA))
1
Russell, N.A.
1
Sehgal, B. R.
1
Sienicki, J. J.
1
Spencer, B. W.
1
Stamps, D. W.
1
Sweet, D.W. (AEA Technology, Winfrith (United Kingdom))
1
Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States))
1
Washington, K.E.
1
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Topic
C Codes
Reactor Accidents
5
22 General Studies Of Nuclear Reactors
4
Accidents
4
Computer Codes
4
Containment
4
Corium
4
Reactors
4
Water Cooled Reactors
4
21 Specific Nuclear Reactors And Associated Plants
3
210200 -- Power Reactors
3
Blowdown
3
Elements
3
Energy Transfer
3
Fluid Mechanics
3
Heat Transfer
3
Hydraulics
3
Hydrogen
3
Light-Water Moderated
3
Mechanics
3
Nonboiling Water Cooled
3
Nonbreeding
3
Nonmetals
3
Pwr Type Reactors
3
Reactor Safety
3
Safety
3
Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
3
210100 -- Power Reactors
2
Boiling Water Cooled
2
Bwr Type Reactors
2
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Content Provider
University of North Texas: UNT Digital Library
5
Geographic location
Surtsey
5
Language
English
5
Open Polar Keyword
Surtsey
5
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