Laboratory simulations of cladding-steam reactions following loss-of-coolant accidents in water-cooled power reactors / by James C. Hesson... [et al]

Safety problems of liquid-metal-cooled fast breeder reactors /

Kelber, C. N.
U.S. Atomic Energy Commission.
Argonne National Laboratory.

January 1970

"February 1970."Includes bibliographical references (p. 199-216).Operated by the University of Chica...

Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios

Wilson, G.E.
Fletcher, C.D.
Davis, C.B.

June 1997

This report revision incorporates new experimental evidence regarding AP600 behavior during small br...

A sensitivity study of the heat transfer processes involved in a hot-leg rupture in a pressurised water-cooled system.

Green, WJ

September 1977

Series of computer experiments was performed, using the reactor thermal analysis code THETAl-B, to...

Computer simulation of loss-of-coolant accidents in pressurised-water-reactor nuclear plants

Spalding, D.B
Imperial Coll. of Science and Technology, London (United Kingdom). Computational Fluid Dynamics Unit

January 1984

SIGLEAvailable from British Library Lending Division - LD:4371.323(CFD--84/3) / BLDSC - British Libr...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Styrofoam simulation of boiling and temperature effects in the EBWR cold critical experiments /

DeShong, J. A.
Argonne National Laboratory. ANL.
U.S. Atomic Energy Commission. ANL.

January 1957

"Operated by the University of Chicago under Contract W-31-109-eng-38."At head of title: Argonne Nat...

Prototypic thermal-hydraulic experiment in NRU to simulate loss-of-coolant accident /

Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"PNL-3681.""NUREG/CR-1882.""NRC FIN B2277.""Date published: April 1981.""Pacific Northwest Laborator...

Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2 /

Russcher, G. E.
Pacific Northwest Laboratory.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...

Investigation of wet steam as a reactor coolant (CAN-2)

Weinstein, A.
Nakache, F.
Sofer, G.
Raber, M.
Israel, S.
Crane, M.
Hankel, R.
Firstenberg, H.
Stein, R. P.
U.S. Atomic Energy Commission.
United Nuclear Corporation.

Other authors or contributors for UNC-5008-2 include: M. Raber, G. Sofer, F. Nakache, A. Weinstein.O...

Analysis and modelling of steam explosion experiments /

Corradini, M. L. author.
U.S. Nuclear Regulatory Commission NUREG/CR-2072.
Sandia National Laboratories.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Sandia National Laboratories SAND80-2131.

"Date Published: April 1981.""SAND80-2131.""NUREG/CR-2072."Includes bibliographical references (page...

LOSS-OF-COOLANT ACIDENT SIMULATIONS IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

Bennett, W. D.
Goodman, R. L.
Heaberlin, S. W.
Hesson, G. M.
Nealley, C.
Kirg, L. L.
Marshall, R. K.
McNair, G. W.
Meitzler, W. D.
Neally, G. W.
Parchen, L. J.
Pilger, J. P.
Rausch, W. N.
Russcher, G. E.
Schreiber, R. E.
Wildung, N. J.

February 1981

Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...

Inpile experimental studies of transient boiling with organic reactor coolant /

Speigler, P.
Bumpus, C.F. Jr. author
Silberberg, M. author
Hopenfeld, J. (Joram), author.
U.S. Atomic Energy Commission. Technical Information Center.
North American Aviation. Atomics International Division.

"Issued: January 30, 1964""NAA-SR-9010-Reactor Technology"Includes bibliographical references (page ...

Steam-cooled power-reactor evaluation : April 1, 1961.

Nuclear Development Corporation of America.
U.S. Atomic Energy Commission.

"This study examines the technological status and economic potential of steam-cooled (nuclear superh...

A study of wet steam as a reactor coolant, joint summary report covering the period ...

Euratom.
U.S. Atomic Energy Commission.
Nuclear Development Corporation of America.

"Work performed under Project VII, Contract AT(30-1)-2303 for the United States Atomic Energy Commis...

Analysis of severe accident energetics in metallic-fueled, liquid metal cooled reactors /

Morris, E. E., author.
Tentner, A. M., author.
University of Chicago, issuing body.
Argonne National Laboratory, issuing body.

"IFR Technical Memorandum No. 235.""August 1994."Includes bibliographical references (pages 47-49)Op...

Safety problems of liquid-metal-cooled fast breeder reactors /

Kelber, C. N.
U.S. Atomic Energy Commission.
Argonne National Laboratory.

January 1970

"February 1970."Includes bibliographical references (p. 199-216).Operated by the University of Chica...

Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios

Wilson, G.E.
Fletcher, C.D.
Davis, C.B.

June 1997

This report revision incorporates new experimental evidence regarding AP600 behavior during small br...

A sensitivity study of the heat transfer processes involved in a hot-leg rupture in a pressurised water-cooled system.

Green, WJ

September 1977

Series of computer experiments was performed, using the reactor thermal analysis code THETAl-B, to...

Computer simulation of loss-of-coolant accidents in pressurised-water-reactor nuclear plants

Spalding, D.B
Imperial Coll. of Science and Technology, London (United Kingdom). Computational Fluid Dynamics Unit

January 1984

SIGLEAvailable from British Library Lending Division - LD:4371.323(CFD--84/3) / BLDSC - British Libr...

Loss-of-coolant accident simulations in the National Research Universal Reactor /

Bennett, W. D.
Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"FIN B2277.""PNL-3093.""NUREG/CR-1208.""Date published: February 1981.""Safety analysis report."Bibl...

Styrofoam simulation of boiling and temperature effects in the EBWR cold critical experiments /

DeShong, J. A.
Argonne National Laboratory. ANL.
U.S. Atomic Energy Commission. ANL.

January 1957

"Operated by the University of Chicago under Contract W-31-109-eng-38."At head of title: Argonne Nat...

Prototypic thermal-hydraulic experiment in NRU to simulate loss-of-coolant accident /

Mohr, C. L.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Pacific Northwest Laboratory.

"PNL-3681.""NUREG/CR-1882.""NRC FIN B2277.""Date published: April 1981.""Pacific Northwest Laborator...

Experiment operations plan for a loss-of-coolant accident simulation in the National Research Universal Reactor : materials tests 1 and 2 /

Russcher, G. E.
Pacific Northwest Laboratory.
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Accident Evaluation.

"PNL-3765.""NUREG/CR-1735, Addendum 1.""NRC FIN B2277.""Date published: September 1981.""Pacific Nor...

Investigation of wet steam as a reactor coolant (CAN-2)

Weinstein, A.
Nakache, F.
Sofer, G.
Raber, M.
Israel, S.
Crane, M.
Hankel, R.
Firstenberg, H.
Stein, R. P.
U.S. Atomic Energy Commission.
United Nuclear Corporation.

Other authors or contributors for UNC-5008-2 include: M. Raber, G. Sofer, F. Nakache, A. Weinstein.O...

Analysis and modelling of steam explosion experiments /

Corradini, M. L. author.
U.S. Nuclear Regulatory Commission NUREG/CR-2072.
Sandia National Laboratories.
U.S. Nuclear Regulatory Commission. Division of Reactor Safety Research.
Sandia National Laboratories SAND80-2131.

"Date Published: April 1981.""SAND80-2131.""NUREG/CR-2072."Includes bibliographical references (page...

LOSS-OF-COOLANT ACIDENT SIMULATIONS IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

Bennett, W. D.
Goodman, R. L.
Heaberlin, S. W.
Hesson, G. M.
Nealley, C.
Kirg, L. L.
Marshall, R. K.
McNair, G. W.
Meitzler, W. D.
Neally, G. W.
Parchen, L. J.
Pilger, J. P.
Rausch, W. N.
Russcher, G. E.
Schreiber, R. E.
Wildung, N. J.

February 1981

Pressurized water reactor loss-of-coolant accident (LOCA) phenomena are being simulated with a serie...

Inpile experimental studies of transient boiling with organic reactor coolant /

Speigler, P.
Bumpus, C.F. Jr. author
Silberberg, M. author
Hopenfeld, J. (Joram), author.
U.S. Atomic Energy Commission. Technical Information Center.
North American Aviation. Atomics International Division.

"Issued: January 30, 1964""NAA-SR-9010-Reactor Technology"Includes bibliographical references (page ...

Steam-cooled power-reactor evaluation : April 1, 1961.

Nuclear Development Corporation of America.
U.S. Atomic Energy Commission.

"This study examines the technological status and economic potential of steam-cooled (nuclear superh...

A study of wet steam as a reactor coolant, joint summary report covering the period ...

Euratom.
U.S. Atomic Energy Commission.
Nuclear Development Corporation of America.

"Work performed under Project VII, Contract AT(30-1)-2303 for the United States Atomic Energy Commis...

Analysis of severe accident energetics in metallic-fueled, liquid metal cooled reactors /

Morris, E. E., author.
Tentner, A. M., author.
University of Chicago, issuing body.
Argonne National Laboratory, issuing body.

"IFR Technical Memorandum No. 235.""August 1994."Includes bibliographical references (pages 47-49)Op...

Safety problems of liquid-metal-cooled fast breeder reactors /

Kelber, C. N.
U.S. Atomic Energy Commission.
Argonne National Laboratory.

January 1970

"February 1970."Includes bibliographical references (p. 199-216).Operated by the University of Chica...

Phenomena identification and ranking tables for Westinghouse AP600 small break loss-of-coolant accident, main steam line break, and steam generator tube rupture scenarios

Wilson, G.E.
Fletcher, C.D.
Davis, C.B.

June 1997

This report revision incorporates new experimental evidence regarding AP600 behavior during small br...

A sensitivity study of the heat transfer processes involved in a hot-leg rupture in a pressurised water-cooled system.

Green, WJ

September 1977

Series of computer experiments was performed, using the reactor thermal analysis code THETAl-B, to...

Laboratory simulations of cladding-steam reactions following loss-of-coolant accidents in water-cooled power reactors / by James C. Hesson... [et al]

Abstract

Extracted data

Laboratory simulations of cladding-steam reactions following loss-of-coolant accidents in water-cooled power reactors / by James C. Hesson... [et al]

Abstract

Extracted data

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