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

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Gilberto Espinosa-Paredes
Raúl Camargo-Camargo
Alejandro Nuñez-Carrera

January 2012

The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...

Simulation of containment pressurization in a large break-loss of coolant accident using single cell and multicell models and CONTAIN code

Noorikalkhoran, Omid
Shirani, Amir Saied
Ahangari, Rohollah

October 2016

Since the inception of nuclear power as a commercial energy source, safety has been recognized as a ...

ANALYSIS OF LOSS OF COOLANT ACCIDENT IN MTR POOL TYPE RESEARCH REACTOR

Tewfik Hamidouche
Anis Bousbia-salah
El Khider Si-ahmed

October 2015

The present work focuses on a simulation of total purge of the pool of an hypothetic research reacto...

The computer simulation of pressure transients in the condenser of a cooling water system

Millington, J.

January 1997

SIGLEAvailable from British Library Document Supply Centre-DSC:DXN020364 / BLDSC - British Library D...

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...

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...

Analysis of Loss of Coolant Accident in MTR Pool Type Research Reactors

HAMIDOUCHE T
BOUSBIA SALAH A
EL KHIDER SI-AHMED
D'AURIA F.

January 2005

Abstract During the operation lifetime of a Nuclear Research Reactors, the frequency of occurrence...

UKAEA modelling studies of clad ballooning and rupture following loss of coolant in a PWR using MABEL

Gibson, I.H.
Sweet, D.W.
Haste, T.J.
Fell, J.
UKAEA, Winfrith. Atomic Energy Establishment (United Kingdom)

January 1982

SIGLELD:9091.9F(AEEW-R--1595) / BLDSC - British Library Document Supply CentreGBUnited Kingdo

EXPERIMENT OPERATIONS PLAN FOR A LOSS-OF-COOLANT ACCIDENT SIMULATION IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

Russcher, G. E.
Cannon, L. W.
Goodman, R. L.
Hesson, G. M.
King, L. L.
McDuffie, P. N.
Marshall, R. K.
Nealley, C.
Pilger, J. P.
Mohr, C. L.

April 1981

Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of ex...

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

Barnes, Charles.
Nishio, Kazuo.
Wilson, Richard E.
Ivins, Richard O.
Hesson, James C.
U.S. Atomic Energy Commission.
Argonne National Laboratory. Reactor Engineering Division.

January 1970

"January 1970."Includes bibliographical references (p. 39).Operated by the University of ChicagoMode...

Computer simulation techniques for turbulent flows

Markatos, N.C
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--84/11) / BLDSC - British Lib...

Thermal hydraulics in water-cooled nuclear reactors

F. D'Auria

January 2017

An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...

Thermal hydraulics in water-cooled nuclear reactors

F. D'Auria

January 2017

An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...

Advanced nuclear reactor safety analysis: the simulation of a small break loss of coolant accident in the simplified boiling water reactor using RELAP5/MOD3.1.1

Faust, Christophor Randall

January 1995

Due to the character of the original source materials and the nature of batch digitization, quality ...

The dynamic analysis of nuclear power plant models with special reference to the pressurised water reactor

Walker, S.A
Council for National Academic Awards, London (United Kingdom)
Royal Naval Coll., Greenwich (United Kingdom)

January 1984

Available from British Library Lending Division - LD:D54756/85 / BLDSC - British Library Document Su...

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Gilberto Espinosa-Paredes
Raúl Camargo-Camargo
Alejandro Nuñez-Carrera

January 2012

The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...

Simulation of containment pressurization in a large break-loss of coolant accident using single cell and multicell models and CONTAIN code

Noorikalkhoran, Omid
Shirani, Amir Saied
Ahangari, Rohollah

October 2016

Since the inception of nuclear power as a commercial energy source, safety has been recognized as a ...

ANALYSIS OF LOSS OF COOLANT ACCIDENT IN MTR POOL TYPE RESEARCH REACTOR

Tewfik Hamidouche
Anis Bousbia-salah
El Khider Si-ahmed

October 2015

The present work focuses on a simulation of total purge of the pool of an hypothetic research reacto...

The computer simulation of pressure transients in the condenser of a cooling water system

Millington, J.

January 1997

SIGLEAvailable from British Library Document Supply Centre-DSC:DXN020364 / BLDSC - British Library D...

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...

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...

Analysis of Loss of Coolant Accident in MTR Pool Type Research Reactors

HAMIDOUCHE T
BOUSBIA SALAH A
EL KHIDER SI-AHMED
D'AURIA F.

January 2005

Abstract During the operation lifetime of a Nuclear Research Reactors, the frequency of occurrence...

UKAEA modelling studies of clad ballooning and rupture following loss of coolant in a PWR using MABEL

Gibson, I.H.
Sweet, D.W.
Haste, T.J.
Fell, J.
UKAEA, Winfrith. Atomic Energy Establishment (United Kingdom)

January 1982

SIGLELD:9091.9F(AEEW-R--1595) / BLDSC - British Library Document Supply CentreGBUnited Kingdo

EXPERIMENT OPERATIONS PLAN FOR A LOSS-OF-COOLANT ACCIDENT SIMULATION IN THE NATIONAL RESEARCH UNIVERSAL REACTOR

Russcher, G. E.
Cannon, L. W.
Goodman, R. L.
Hesson, G. M.
King, L. L.
McDuffie, P. N.
Marshall, R. K.
Nealley, C.
Pilger, J. P.
Mohr, C. L.

April 1981

Pressurized water reactor loss-of-coolant accident phenomena are being simulated with a series of ex...

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

Barnes, Charles.
Nishio, Kazuo.
Wilson, Richard E.
Ivins, Richard O.
Hesson, James C.
U.S. Atomic Energy Commission.
Argonne National Laboratory. Reactor Engineering Division.

January 1970

"January 1970."Includes bibliographical references (p. 39).Operated by the University of ChicagoMode...

Computer simulation techniques for turbulent flows

Markatos, N.C
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--84/11) / BLDSC - British Lib...

Thermal hydraulics in water-cooled nuclear reactors

F. D'Auria

January 2017

An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...

Thermal hydraulics in water-cooled nuclear reactors

F. D'Auria

January 2017

An attempt is made in the Book to provide a vision of nuclear thermal-hydraulics as it appears follo...

Advanced nuclear reactor safety analysis: the simulation of a small break loss of coolant accident in the simplified boiling water reactor using RELAP5/MOD3.1.1

Faust, Christophor Randall

January 1995

Due to the character of the original source materials and the nature of batch digitization, quality ...

The dynamic analysis of nuclear power plant models with special reference to the pressurised water reactor

Walker, S.A
Council for National Academic Awards, London (United Kingdom)
Royal Naval Coll., Greenwich (United Kingdom)

January 1984

Available from British Library Lending Division - LD:D54756/85 / BLDSC - British Library Document Su...

Severe Accident Simulation of the Laguna Verde Nuclear Power Plant

Gilberto Espinosa-Paredes
Raúl Camargo-Camargo
Alejandro Nuñez-Carrera

January 2012

The loss-of-coolant accident (LOCA) simulation in the boiling water reactor (BWR) of Laguna Verde Nu...

Simulation of containment pressurization in a large break-loss of coolant accident using single cell and multicell models and CONTAIN code

Noorikalkhoran, Omid
Shirani, Amir Saied
Ahangari, Rohollah

October 2016

Since the inception of nuclear power as a commercial energy source, safety has been recognized as a ...

ANALYSIS OF LOSS OF COOLANT ACCIDENT IN MTR POOL TYPE RESEARCH REACTOR

Tewfik Hamidouche
Anis Bousbia-salah
El Khider Si-ahmed

October 2015

The present work focuses on a simulation of total purge of the pool of an hypothetic research reacto...

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

Abstract

Extracted data

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

Abstract

Extracted data

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