Conference Publications (2001 to 2005)
2005
Mechanical Modeling Of Pressure Tube Tests Using The Feat Code
W. Barten, A. Hermann, H. Wallin
Jahrestagung Kerntechnik 2005, 10-12 May 2005, Nuremberg, Germany, 2005
Assessment Of A Bwr Analytical Reduced Order Model Against The System Code Ramona: Applicability And Limitations
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 13th Int. Conference On Nuclear Engineering (Icone13), 16-20 May 2005, Beijing, China, 2005
A Reactor Noise Analysis Methodology For Bwr Core Stability Evaluation: Application And Assessment To Leibstadt Stability Tests
A. Dokhane, H. Ferroukhi, M. Zimmermann, Aguirre. A,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Evaluation Of The Pwr Rea Pulse Width For Realistic Uo2/Mox Cores
H. Ferroukhi, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Assessment Of Trace Code Against Chf Experiments
A. Jasiulevicius, Juan. Macian, Coddington. R, Sanchez. P,
Proc. 11th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-11), 2-6 October 2005, Avignon, France, 2005
Loss Of Residual Heat Removal System: Simulation By Tracev4.00 Simulation Of A Pkl Experiment
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 442-443, June 2005
Chf Experiments In Single Tubes Tracev4.050 Code Validation
A. Jasiulevicius, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 430-432, June 2005
Effect Of The Power Pulse Shape On The Fuel Thermal-Mechanical Response To Rias: A Study Using Falcon And Scanair
A. Romano, M. Zimmermann,
Proc. Water Reactor Fuel Performance Meeting, Wrfpm05, 2-6 October 2005, Kyoto, Japan, 2005
Analysis Of Mcnpx/Jef-2.2 And Jendl-3.3 Results For A Suite Of The Low-Enriched Thermal Compound Uranium Benchmarks
A. Vasiliev, J. Lebenhaft, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Optimization Of Uo2 Fueled Pwr Core Design
E. Greenspan, F. Ganda, Z. Shayer, N. Todreas, J. Malen, C. Shuffler, J. Trant, A. Romano, B. Petrovic, H. Garkish
Proc. Int. Congress On Advances in Nuclear Power Plants, 15-19 May 2005, Seoul, Korea, 2005
W. Barten, A. Hermann, H. Wallin
Jahrestagung Kerntechnik 2005, 10-12 May 2005, Nuremberg, Germany, 2005
Assessment Of A Bwr Analytical Reduced Order Model Against The System Code Ramona: Applicability And Limitations
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 13th Int. Conference On Nuclear Engineering (Icone13), 16-20 May 2005, Beijing, China, 2005
A Reactor Noise Analysis Methodology For Bwr Core Stability Evaluation: Application And Assessment To Leibstadt Stability Tests
A. Dokhane, H. Ferroukhi, M. Zimmermann, Aguirre. A,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Evaluation Of The Pwr Rea Pulse Width For Realistic Uo2/Mox Cores
H. Ferroukhi, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Assessment Of Trace Code Against Chf Experiments
A. Jasiulevicius, Juan. Macian, Coddington. R, Sanchez. P,
Proc. 11th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-11), 2-6 October 2005, Avignon, France, 2005
Loss Of Residual Heat Removal System: Simulation By Tracev4.00 Simulation Of A Pkl Experiment
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 442-443, June 2005
Chf Experiments In Single Tubes Tracev4.050 Code Validation
A. Jasiulevicius, Juan. Macian,
Trans.Am.Nuc.Soc., Volume 92, Pp 430-432, June 2005
Effect Of The Power Pulse Shape On The Fuel Thermal-Mechanical Response To Rias: A Study Using Falcon And Scanair
A. Romano, M. Zimmermann,
Proc. Water Reactor Fuel Performance Meeting, Wrfpm05, 2-6 October 2005, Kyoto, Japan, 2005
Analysis Of Mcnpx/Jef-2.2 And Jendl-3.3 Results For A Suite Of The Low-Enriched Thermal Compound Uranium Benchmarks
A. Vasiliev, J. Lebenhaft, M. Zimmermann,
Int. **Topical Meeting On Mathematics And Computation (M&C 2005), 12-15 September 2005, Avignon, France, 2005
Optimization Of Uo2 Fueled Pwr Core Design
E. Greenspan, F. Ganda, Z. Shayer, N. Todreas, J. Malen, C. Shuffler, J. Trant, A. Romano, B. Petrovic, H. Garkish
Proc. Int. Congress On Advances in Nuclear Power Plants, 15-19 May 2005, Seoul, Korea, 2005
2004
Boilling Suppression In Convective Flow
Y. Aounallah
Proc. Icapp04, 13-17 June 2004, Pittsburgh, Usa
Retran-3d Analysis Of The Extreme Cases Of Phase 3 Of The Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington
Jahrestagung Kerntechnik, 25-27 May 2004, DüSseldorf, Germany, Vol. Tagungsband, 3-8, 2004
Bifurcation Analysis Using The System Code Ramona
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 12th Int. Conference On Nuclear Engineering (Icone 12), 25-29 April 2004, Arlington, Usa, 2004
Uncertainty Analysis Applied To Fuel Depletion Calculations
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
Assessment Of Casmo-4 Predictions Of The Iso**Topic Inventory Of High Burn-Up Mox Fuel
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
Y. Aounallah
Proc. Icapp04, 13-17 June 2004, Pittsburgh, Usa
Retran-3d Analysis Of The Extreme Cases Of Phase 3 Of The Peach Bottom 2 Turbine Trip Benchmark
W. Barten, P. Coddington
Jahrestagung Kerntechnik, 25-27 May 2004, DüSseldorf, Germany, Vol. Tagungsband, 3-8, 2004
Bifurcation Analysis Using The System Code Ramona
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. 12th Int. Conference On Nuclear Engineering (Icone 12), 25-29 April 2004, Arlington, Usa, 2004
Uncertainty Analysis Applied To Fuel Depletion Calculations
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
Assessment Of Casmo-4 Predictions Of The Iso**Topic Inventory Of High Burn-Up Mox Fuel
Macian-Juan R., Zimmermann M.A., Chawla R..
Physor 2004, 25-29 April 2004, Chicago, Usa, 2004
2003
Level-Swell Prediction With Retran-3d And Its Application To A Bwr Steam Line Break Analysis
Y. Aounallah, K. Hofer
Proc. Int. Congress On Advanced Nuclear Power Plants (Icapp'03), 4-7 May 2003, CóRdoba, Spain
Peach Bottom Bwr Turbine Trip Benchmark Phase 3: Analysis Of Full Plant System With 3d-Neutronics Using Retran-3d
W. Barten, P. Coddington
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Validation Of Monteburns For Mox Fuel Using Ariane Experimental Results
J.R. Lebenhaft, H.R. Trellue
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 1 - The Effects Of Using Drift Flux Versus Homogeneous Equilibrium Models
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 2 - Stability Limits Of In-Phase And Out-Of-Phase Modes
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
Y. Aounallah, K. Hofer
Proc. Int. Congress On Advanced Nuclear Power Plants (Icapp'03), 4-7 May 2003, CóRdoba, Spain
Peach Bottom Bwr Turbine Trip Benchmark Phase 3: Analysis Of Full Plant System With 3d-Neutronics Using Retran-3d
W. Barten, P. Coddington
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Validation Of Monteburns For Mox Fuel Using Ariane Experimental Results
J.R. Lebenhaft, H.R. Trellue
Proc. Mathematics & Computations 2003, 6-10 April 2003, Gatlinburg, Tennessee, Usa
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 1 - The Effects Of Using Drift Flux Versus Homogeneous Equilibrium Models
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
Nuclear-Coupled Thermal-Hydraulic Nonlinear Stability Analysis Using A Novel Bwr Reduced Order Model: Part 2 - Stability Limits Of In-Phase And Out-Of-Phase Modes
A. Dokhane, D. Hennig, R. Chawla, Rizwan-Uddin
Proc. Icone11, 20-23 April 2003, Tokyo, Japan
2002
Peach Bottom Bwr Turbine Trip Benchmark: Psi Analysis Of Exercise 1 Using Retran-3d
W. Barten, P. Coddington, H. Ferroukhi
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Stability And Bifurcation Analyses Of Two-Phase Flow Using A Drift Flux Model And Bifurcation Code Bifdd
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Tenth Int. Conference On Nuclear Engineering (Icone-10), 14-18 April 2002, Arlington, Virginia, Usa
A Parametric Study Of Heated Channels With Two-Phase Flow Using Bifurcation Analysis
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. American Nuclear Society Annual Meeting, June 9-13, 2002, Florida, Usa, Trans. Ans, Vol. 86, 131-133 (2002)
Nonlinear Stability Analysis With A Novel Bwr Reduced Order Model
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Transient 3-D Neutron Kinetic Analysis With Coretran Of A Core Thermal-Hydraulic Boundary Condition Model - Peach Bottom 2 Turbine Trip Benchmark Phase 2
H. Ferroukhi, W. Barten, P. Coddington
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
W. Barten, P. Coddington, H. Ferroukhi
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Stability And Bifurcation Analyses Of Two-Phase Flow Using A Drift Flux Model And Bifurcation Code Bifdd
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Tenth Int. Conference On Nuclear Engineering (Icone-10), 14-18 April 2002, Arlington, Virginia, Usa
A Parametric Study Of Heated Channels With Two-Phase Flow Using Bifurcation Analysis
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. American Nuclear Society Annual Meeting, June 9-13, 2002, Florida, Usa, Trans. Ans, Vol. 86, 131-133 (2002)
Nonlinear Stability Analysis With A Novel Bwr Reduced Order Model
A. Dokhane, D. Hennig, Uddin. Rizwan, R. Chawla
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
Transient 3-D Neutron Kinetic Analysis With Coretran Of A Core Thermal-Hydraulic Boundary Condition Model - Peach Bottom 2 Turbine Trip Benchmark Phase 2
H. Ferroukhi, W. Barten, P. Coddington
Proc. Physor 2002, 7-10 October 2002, Seoul, Korea
2001
Analysis And Sensitivity Studies With Coretran And Retran-3d Of The Neacrp Rod Ejection Benchmark
H. Ferroukhi, P. Coddington
Proc. Icone-9, Nice France, April 8-12, 2001.
Development Of A Model For Retran-3d For Pressure Losses At T-Junctions
W. Barten, P. Coddington, J. Sullivan
Proc. Icone-9, Nice France, April 8-12, 2001.
Analysis Of Different Hypothetical Recirculation Line Sb-Locas In Kkm By Trac-Bf1/V98.1
G. Analytis, Coddington. Th,
Proc. Icone-9, Nice France, April 8-12, 2001.
Best Estimate Analysis Of The Thermal Expansion Scenario During Shutdown In A Pwr
R. Macian, L. Nechvatal
Proc. Icone-9, Nice France, April 8-12, 2001.
Coretran/Vipre Assembly Critical Power Assessment Against Nupec Bwr Experiments
Y. Aounallah
Proc. Icone-9, Nice, France, April 8-12, 2001.
Retran-3d Results And One-Dimensional Analytical Model For The Critical Power Of A Rod Bundle With Cosine-Shape Heating
W. Barten
Proc. Jahrestagung Kerntechnik 2001, Dresden, Germany, May 15-17, 2001.
Uncontrolled Rod Bank Withdrawal Benchmark Analysis With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
Limited Burnup Credit For Increased Fuel Enrichments In A Swiss Pwr Storage Pool
J-M. Parratte, P. Grimm
Proc. Ans **Topical Meeting On Practical Implementation of Nuclear Criticality Safety, Ncsd, Reno, Nevada, Usa, November 11-15, 2001
Some Remarks To Time Series Analysis For Bwr Stability Analysis
B. Askari, K. Behringer, D. Hennig
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
H. Ferroukhi, P. Coddington
Proc. Icone-9, Nice France, April 8-12, 2001.
Development Of A Model For Retran-3d For Pressure Losses At T-Junctions
W. Barten, P. Coddington, J. Sullivan
Proc. Icone-9, Nice France, April 8-12, 2001.
Analysis Of Different Hypothetical Recirculation Line Sb-Locas In Kkm By Trac-Bf1/V98.1
G. Analytis, Coddington. Th,
Proc. Icone-9, Nice France, April 8-12, 2001.
Best Estimate Analysis Of The Thermal Expansion Scenario During Shutdown In A Pwr
R. Macian, L. Nechvatal
Proc. Icone-9, Nice France, April 8-12, 2001.
Coretran/Vipre Assembly Critical Power Assessment Against Nupec Bwr Experiments
Y. Aounallah
Proc. Icone-9, Nice, France, April 8-12, 2001.
Retran-3d Results And One-Dimensional Analytical Model For The Critical Power Of A Rod Bundle With Cosine-Shape Heating
W. Barten
Proc. Jahrestagung Kerntechnik 2001, Dresden, Germany, May 15-17, 2001.
Uncontrolled Rod Bank Withdrawal Benchmark Analysis With Coretran And Retran-3d
H. Ferroukhi, P. Coddington
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
Limited Burnup Credit For Increased Fuel Enrichments In A Swiss Pwr Storage Pool
J-M. Parratte, P. Grimm
Proc. Ans **Topical Meeting On Practical Implementation of Nuclear Criticality Safety, Ncsd, Reno, Nevada, Usa, November 11-15, 2001
Some Remarks To Time Series Analysis For Bwr Stability Analysis
B. Askari, K. Behringer, D. Hennig
Proc. Ans Int. Meeting On Mathematical Methods For Nuclear Applications, Mc-2001, Salt Lake City, September 2001.
