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1
Regional Issue Identification and Assessment Program (RIIA). Issue Paper 4. A methodology for analyzing the water quality impacts of cooling-tower blowdown
by
Kaplan, E.
Published 1979
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2
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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3
Direct heating containment vessel interactions code (DHCVIC) and prediction of SNL ''SURTSEY'' test DCH-1
by
Ginsberg, T.
,
Tutu, N.
Published 1986
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Select result number 4
4
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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5
Experiments to investigate direct containment heating phenomena with scaled models of the Calvert Cliffs Nuclear Power Plant
by
Blanchat, T. K.
,
Pilch, M. M.
,
Allen, M. D.
Published 1997
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6
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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Select result number 7
7
Test results on direct containment heating by high-pressure melt ejection into the Surtsey vessel: The TDS test series
by
Allen, M. D.
,
Blanchat, T. K.
,
Pilch, M. M.
Published 1994
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5
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2
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Allen, M. D.
2
Allen, M.D.
2
Blanchat, T. K.
2
Pilch, M. M.
2
Brockmann, J.E.
1
Ginsberg, T.
1
Kaplan, E.
1
Merilo, M.
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
Sehgal, B. R.
1
Sienicki, J. J.
1
Spencer, B. W.
1
Sweet, D.W. (AEA Technology, Winfrith (United Kingdom))
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Tarbell, W.W. (Sandia National Labs., Albuquerque, NM (United States))
1
Tutu, N.
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Topic
Blowdown
21 Specific Nuclear Reactors And Associated Plants
5
22 General Studies Of Nuclear Reactors
5
Light-Water Moderated
5
Nonboiling Water Cooled
5
Nonbreeding
5
Pwr Type Reactors
5
210200 -- Power Reactors
4
Accidents
4
Containment
4
Corium
4
Heating
4
Meltdown
4
Reactor Accidents
4
Reactor Safety
4
Reactors
4
Scale Models
4
Water Cooled Reactors
4
Water Moderated Reactors 220900* -- Nuclear Reactor Technology-- Reactor Safety
4
C Codes
3
Computer Codes
3
Elements
3
Energy Transfer
3
Fluid Mechanics
3
Heat Transfer
3
Hydraulics
3
Hydrogen
3
Mechanics
3
Nonmetals
3
Power Reactors
3
see all ...
Content Provider
University of North Texas: UNT Digital Library
7
Geographic location
Surtsey
6
Language
English
7
Open Polar Keyword
Surtsey
6
North Atlantic
1
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