2000 and before
Assessment Of Retran-3d Against Experimental Loss Of Coolant Scenarios
R. Macian, P. Coddington
Proc. Icone-8, Baltimore, Md, Usa 2000.
Assessment Of Retran-3d And Vipre-02 Void Predictions Against Experimental Data
R. Macian, Y. Aounallah, P. Coddington P. Stangroom
Proc. Icone-8, Baltimore, Md, Usa 2000.
Towards A Best-Estimate Approach To A Steady-State And Transient Analysis Using The Coretran Code
H. Ferroukhi, P. Coddington, F. Holzgrewe
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Development And Assessment Of Trac-Bf1 For Bwr Loca Applications
G. Th Analytis, P. Coddington
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Validation Of Casmo-4 Against Sims Measured Spatial Nuclide Distributions Inside A 9 Wt% Gd Bwr Pin
F. Holzgrewe, Et Al.
Proc. Int. **Topical Meeting On Light Water Reactor Fuel Performance, Park City, Ut, Usa, April 2000.
Current And Future Applications Of Thermal-Hydraulic And Neutronic Best-Estimate Methods In Support Of The Swiss Licensing Process
M. A. Zimmermann, W. Van Doesburg
Proc. Csni/Oecd Workshop On Advanced Thermal-Hydraulic And Neutronic Codes: Current And Future Applications, Barcelona, Spain, April 10-13, 2000.
A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Proc. Int. Meeting On Trends in Numerical And Physical Modelling For Industrial Multiphase Flows , Cargese, Corsica, September 27-29, 2000.
Remarks On Regional Power Oscillations In Bwr'S
D. Ginestar, D. Hennig, R. Miro, G. Verdu
Proc. Int. Conference On Mathematics And Computation, Reactor Physics And Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept 27-30, 1999
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran- 3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Vipre-02 Subchannel Validation Against Nupec Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Meeeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Analysis Of Rod Bundle And Subchannel, Subcooled Boiling Experiments Using Retran-3d, Trac-Bf1 And Vipre-02
P. Coddington, Y. Aounallah, D. Maier, D. Reedha
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 Bwr
G. Th. Analytis, D. Hennig, J. K-H. Karlsson
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Drain Lain Melt Through Experiment Under Water-free Conditions
K. Nakada, B.S. Jäckel, H. Hirschmann, J.A. Patorski, G. Duijvestijn
7th ICONE Conference
Assessment Of The Slip Options In Retran-3d Against A Wide Range Of Rod Bundle Void Data
D. Maier, P. Coddington
Proc. Icone6, 6th Int. Conference On Nuclear Engineering, May 10-15, 1998, San Diego, California, Usa
Einige Bemerkungen Zum Physikalischen Mechanismus Der Entstehung Von Oszillatorischen InstabilitäTen In Siedewasserreaktoren
D. Hennig
Proc. Jahrestagung Kerntechnik Mai 1998, MüNchen.
Evaluation Of The Slip Options In Retran-3d
D. Maier, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Bwr Stability Analysis At Psi
D. Hennig
Proc. Int. Conference On The Physics of Nuclear Science And Technology, Oct. 5 - 8, 1998, Long Island, New York
Behavior of a passive heat removal system following a severe accident
A. Dehbi, D.J. Suckow, S. Güntay
Annual Meeting on Nuclear Technology
Evaluation Of The Trac-Bf1 Code Against Bwr/6 Start-Up Tests
B. Brodbeck, P. Coddington
Proc. Icone5, Nice France, May 26-30, 1997, Paper No. 2461.
Review Of Wide Range Void Correlations Against An Extensive Database Of Rod Bundle Void Measurements
D. Maier, P. Coddington
Proc. Icone5, Nice, France, May 26-30, 1997, Paper No. 2434.
Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, S. Güntay, J. Lopez Jimenez, G.F. de Santi, M. Valisi
FISA-97 Symposium on EU Research on Severe Accidents
ESBWR passive aerosol removal - Maintaining plant simplicity for offsite dose reduction
S. Güntay, D.J. Suckow, N.B. Siccama, S.S. Khorana
Economic Nuclear Power for the 21st Century
Further Assessment of the Chemical Modelling of Iodine in IMPAIR 3 Code using ACE/RTF Data
R.C. Cripps, S. Güntay
4th CSNI Workshop on the Chemistry of Iodine in Reactor Safety
Primary Circuit Iodine Model Addition to IMPAIR-3
D.J. Osetek, D.L.Y. Louie, S. Güntay, R.C. Cripps
4th CSNI Workshop on the Chemistry of Iodine in Reactor Safety
Experimental Investigations of Mixed Convection
D.J. Suckow, U. Müller, L. Krebs
Proceedings of the 10th International Heat Transfer Conference
Simulation of pool scrubbing experiments using BUSCA
A. Dehbi, S. Güntay
3rd International Conference on Containment Design and Operation
Model of condensation in stagnant steam-noncondensable gas mixtures
A. Dehbi, M.W. Golay, M.S. Kazimi
Transactions of the American Nuclear Society
The transferability to reactor conditions of thermo-hydraulics model investigations of decay heat removal
D. Weinberg, D.J. Suckow, U. Müller, H. Hoffmann
Proceedings of the 1990 International Fast Reactor Safety Meeting
Theoretical investigations on thermal behaviour of nuclear fuel and NEPTUN heater element
S.N. Aksan, S. Güntay, V. Varadi
Transactions of the American Nuclear Society
Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society
Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society
R. Macian, P. Coddington
Proc. Icone-8, Baltimore, Md, Usa 2000.
Assessment Of Retran-3d And Vipre-02 Void Predictions Against Experimental Data
R. Macian, Y. Aounallah, P. Coddington P. Stangroom
Proc. Icone-8, Baltimore, Md, Usa 2000.
Towards A Best-Estimate Approach To A Steady-State And Transient Analysis Using The Coretran Code
H. Ferroukhi, P. Coddington, F. Holzgrewe
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Development And Assessment Of Trac-Bf1 For Bwr Loca Applications
G. Th Analytis, P. Coddington
Proc. Int. Meeting On Best-Estimate Methods in Nuclear Installation Safety Analysis, Washington, Dc, Usa, Nov. 2000
Validation Of Casmo-4 Against Sims Measured Spatial Nuclide Distributions Inside A 9 Wt% Gd Bwr Pin
F. Holzgrewe, Et Al.
Proc. Int. **Topical Meeting On Light Water Reactor Fuel Performance, Park City, Ut, Usa, April 2000.
Current And Future Applications Of Thermal-Hydraulic And Neutronic Best-Estimate Methods In Support Of The Swiss Licensing Process
M. A. Zimmermann, W. Van Doesburg
Proc. Csni/Oecd Workshop On Advanced Thermal-Hydraulic And Neutronic Codes: Current And Future Applications, Barcelona, Spain, April 10-13, 2000.
A Study Of The Performance Of Void Fraction Correlations Used In The Context Of Drift-Flux Two-Phase Flow Models
P. Coddington, R. Macian
Proc. Int. Meeting On Trends in Numerical And Physical Modelling For Industrial Multiphase Flows , Cargese, Corsica, September 27-29, 2000.
Remarks On Regional Power Oscillations In Bwr'S
D. Ginestar, D. Hennig, R. Miro, G. Verdu
Proc. Int. Conference On Mathematics And Computation, Reactor Physics And Environmental Analysis in Nuclear Applications, Madrid, Spain, Sept 27-30, 1999
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran- 3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Vipre-02 Subchannel Validation Against Nupec Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Meeeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Analysis Of Rod Bundle And Subchannel, Subcooled Boiling Experiments Using Retran-3d, Trac-Bf1 And Vipre-02
P. Coddington, Y. Aounallah, D. Maier, D. Reedha
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
The Physical Mechanism Of Core-Wide And Local Instabilities At The Forsmark-1 Bwr
G. Th. Analytis, D. Hennig, J. K-H. Karlsson
Proc. 9th Int. Meeting On Nuclear Reactor Thermal Hydraulics, Oct 4-8, 1999, San Francisco, Ca
Drain Lain Melt Through Experiment Under Water-free Conditions
K. Nakada, B.S. Jäckel, H. Hirschmann, J.A. Patorski, G. Duijvestijn
7th ICONE Conference
Assessment Of The Slip Options In Retran-3d Against A Wide Range Of Rod Bundle Void Data
D. Maier, P. Coddington
Proc. Icone6, 6th Int. Conference On Nuclear Engineering, May 10-15, 1998, San Diego, California, Usa
Einige Bemerkungen Zum Physikalischen Mechanismus Der Entstehung Von Oszillatorischen InstabilitäTen In Siedewasserreaktoren
D. Hennig
Proc. Jahrestagung Kerntechnik Mai 1998, MüNchen.
Evaluation Of The Slip Options In Retran-3d
D. Maier, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Vipre-02 Subchannel Validation Against Nupec Bwr Void Fraction Data
Y. Aounallah, P. Coddington
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Implementation Of An Improved Interfacial Mass And Energy Transfer Model In Retran-3d
R. Macian, P. Cebull, P. Coddington, M. Paulsen
Proc. 9th Int. Retran Meeting, June 7-10, 1998, Monterey, Ca, Usa
Bwr Stability Analysis At Psi
D. Hennig
Proc. Int. Conference On The Physics of Nuclear Science And Technology, Oct. 5 - 8, 1998, Long Island, New York
Behavior of a passive heat removal system following a severe accident
A. Dehbi, D.J. Suckow, S. Güntay
Annual Meeting on Nuclear Technology
Evaluation Of The Trac-Bf1 Code Against Bwr/6 Start-Up Tests
B. Brodbeck, P. Coddington
Proc. Icone5, Nice France, May 26-30, 1997, Paper No. 2461.
Review Of Wide Range Void Correlations Against An Extensive Database Of Rod Bundle Void Measurements
D. Maier, P. Coddington
Proc. Icone5, Nice, France, May 26-30, 1997, Paper No. 2434.
Containment behaviour in the event of core melt with gaseous and aerosol releases (CONGA)
E. Friesen, S. Güntay, J. Lopez Jimenez, G.F. de Santi, M. Valisi
FISA-97 Symposium on EU Research on Severe Accidents
ESBWR passive aerosol removal - Maintaining plant simplicity for offsite dose reduction
S. Güntay, D.J. Suckow, N.B. Siccama, S.S. Khorana
Economic Nuclear Power for the 21st Century
Further Assessment of the Chemical Modelling of Iodine in IMPAIR 3 Code using ACE/RTF Data
R.C. Cripps, S. Güntay
4th CSNI Workshop on the Chemistry of Iodine in Reactor Safety
Primary Circuit Iodine Model Addition to IMPAIR-3
D.J. Osetek, D.L.Y. Louie, S. Güntay, R.C. Cripps
4th CSNI Workshop on the Chemistry of Iodine in Reactor Safety
Experimental Investigations of Mixed Convection
D.J. Suckow, U. Müller, L. Krebs
Proceedings of the 10th International Heat Transfer Conference
Simulation of pool scrubbing experiments using BUSCA
A. Dehbi, S. Güntay
3rd International Conference on Containment Design and Operation
Model of condensation in stagnant steam-noncondensable gas mixtures
A. Dehbi, M.W. Golay, M.S. Kazimi
Transactions of the American Nuclear Society
The transferability to reactor conditions of thermo-hydraulics model investigations of decay heat removal
D. Weinberg, D.J. Suckow, U. Müller, H. Hoffmann
Proceedings of the 1990 International Fast Reactor Safety Meeting
Theoretical investigations on thermal behaviour of nuclear fuel and NEPTUN heater element
S.N. Aksan, S. Güntay, V. Varadi
Transactions of the American Nuclear Society
Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society
Sensitivity Analysis of PWR and HGTR Fuel Cycle Costs
S. Güntay
Transactions of the American Nuclear Society