Info message
Ce contenu n'est pas disponible en français.Conference Publications 2011
Oecd/Nea Main Steam Line Break Pwr Benchmark Simulation By Trace/S3k Coupled Code
K. Nikitin, A. Manera, H. Ferroukhi, J. Judd, G.M. Grandi
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Post-Test Thermal-Hydraulic Analysis Of Two Intermediate Loca Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Testing Of The Quicktest-Ultimate Algorithm To Solve The Dissolved Convection Equation During A Boron Dilution Test At The Pkl Facility
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Validation Of Star-Ccm+ For Bouyancy Driven Mixing In A Pwr Reactor Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Analysis Of The Performance Of The Kerena Emergency Condenser
A. Manera, H.M. Prasser, S. Leyer
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Prediction Of Void Fraction In A Subchannel And Bundle Geometry With Flica4 And Trace
T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Revisiting Temporal Accuracy In Neutronics/T-H Code Coupling Using The Nuresim Lwr Simulation Platform
O. Zerkak, I. Gajev, A. Manera, T. Kozlowski, A. Gommlich, S. Zimmer, S. Kliem, N. Crouzet, M.A. Zimmermann
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Pre-Calculation Using The Falcon Fuel Behaviour Code Of The Fuel Rod Design Parameters And The Test Conditions For A Two-Run Halden Loca Tests With Kkl Bwr High-Burnup Fuel.
G. Khvostov, E. Kolstad, G. Ledergerber, M.A. Zimmermann, W. Wiesenack, O. Bremond, R. Restani, H. Wiese, M. Martin
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011
Post-Test Analysis Of The Halden Loca Experiment Ifa-650.7 Using The Falcon Code.
G. Khvostov, W. Wiesenack, B.C. Oberlander, E. Kolstad, G. Ledergerber, M.A. Zimmermann
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011
Assessment Of Mcnpx/Cinder For Burnup Calculations
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Criticality Safety Evaluation Of A Swiss Wet Storage Pool Including Limited Buc And Uncertainty Analysis
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Towards Advanced Modelling Of Mps-Assisted Cladding Failure During Power Ramps Using The Falcon Code
G. Khvostov, M.A. Zimmerman, W. Lyon, M. Pytel
Proc. Water Reactor Fuel Performance Meeting 2011, Chengdu, China, September 11-14, 2011
Development And Test Validation Of A Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss Bwrs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
A Trend Analysis Methodology For Enhanced Validation Of 3-D Lwr Core Simulations
W. Wieselquist, H. Ferroukhi, K. Bernatowicz
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Towards An Uncertainty Quantification Methodology With Casmo-5
W. Wieselquist, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Development And Validation Of A Coupled Cfd/System-Code Tool
D. Bertolotto, A. Manera, R. Chawla
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp2011), Nice, France, May 2-5, 2011
Presentation Of The Multi-Physics Subproject Of The Nurisp European Project
J. Jimenez,M.A. Zimmermann, O. Zerkak ,Ph. Emonot
Proc. Annual Meeting of The Spanish Nuclear Society 2011
Vipre-W/Mefisto-T - A Mechanistic Toll For Transient Predictions Of Dryout In Bwr Fuel
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Transient Void, Pressure Drop And Critical Power Bfbt Benchmark Analysis And Results With Vipre-W/Mefisto-T
J-M. Le Corre, C. Adamsson, P. Alvarez
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
On A Best-Estimate Approach To Calculation Of Dryout Probability During Bwr Transients
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Discted Dynamic Event Tree Analysis Of Mloca Using Ads-Trace Ads-Trace
D.R. Karanki, V.N. Dang, T-W. Kim
Proc. Top. Meetg. On Probabilistic Safety Assessment And Analysis, Ans Psa2011, Wilimington, Us, March 13-17, 2011
K. Nikitin, A. Manera, H. Ferroukhi, J. Judd, G.M. Grandi
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Post-Test Thermal-Hydraulic Analysis Of Two Intermediate Loca Tests At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Testing Of The Quicktest-Ultimate Algorithm To Solve The Dissolved Convection Equation During A Boron Dilution Test At The Pkl Facility
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Validation Of Star-Ccm+ For Bouyancy Driven Mixing In A Pwr Reactor Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Analysis Of The Performance Of The Kerena Emergency Condenser
A. Manera, H.M. Prasser, S. Leyer
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Prediction Of Void Fraction In A Subchannel And Bundle Geometry With Flica4 And Trace
T-W. Kim, A. Manera
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Revisiting Temporal Accuracy In Neutronics/T-H Code Coupling Using The Nuresim Lwr Simulation Platform
O. Zerkak, I. Gajev, A. Manera, T. Kozlowski, A. Gommlich, S. Zimmer, S. Kliem, N. Crouzet, M.A. Zimmermann
Proc. Int. Top.Meetg. Nuclear Reactor Thermalhydraulics, Nureth-14, Toronto, Canada, September 25-30, 2011
Pre-Calculation Using The Falcon Fuel Behaviour Code Of The Fuel Rod Design Parameters And The Test Conditions For A Two-Run Halden Loca Tests With Kkl Bwr High-Burnup Fuel.
G. Khvostov, E. Kolstad, G. Ledergerber, M.A. Zimmermann, W. Wiesenack, O. Bremond, R. Restani, H. Wiese, M. Martin
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011
Post-Test Analysis Of The Halden Loca Experiment Ifa-650.7 Using The Falcon Code.
G. Khvostov, W. Wiesenack, B.C. Oberlander, E. Kolstad, G. Ledergerber, M.A. Zimmermann
Proc. Enlarged Halden Project Group Meeting, Sandefjord, Norway, October 2-7, 2011
Assessment Of Mcnpx/Cinder For Burnup Calculations
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Criticality Safety Evaluation Of A Swiss Wet Storage Pool Including Limited Buc And Uncertainty Analysis
E. Kolbe, P. Grimm, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Criticality Icnc 2011, Edinburgh, Scotland, September 19-22, 2011
Towards Advanced Modelling Of Mps-Assisted Cladding Failure During Power Ramps Using The Falcon Code
G. Khvostov, M.A. Zimmerman, W. Lyon, M. Pytel
Proc. Water Reactor Fuel Performance Meeting 2011, Chengdu, China, September 11-14, 2011
Development And Test Validation Of A Computational Scheme For High-Fidelity Fluence Estimations Of The Swiss Bwrs
A. Vasiliev, W. Wieselquist, H. Ferroukhi, S. Canepa
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
A Trend Analysis Methodology For Enhanced Validation Of 3-D Lwr Core Simulations
W. Wieselquist, H. Ferroukhi, K. Bernatowicz
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Towards An Uncertainty Quantification Methodology With Casmo-5
W. Wieselquist, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Mathematics And Computational Methods Applied To Nucl. Science And Engineering,(M&C2011), Rio De Janeiro, Brazil, May 8-12, 2011
Development And Validation Of A Coupled Cfd/System-Code Tool
D. Bertolotto, A. Manera, R. Chawla
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp2011), Nice, France, May 2-5, 2011
Presentation Of The Multi-Physics Subproject Of The Nurisp European Project
J. Jimenez,M.A. Zimmermann, O. Zerkak ,Ph. Emonot
Proc. Annual Meeting of The Spanish Nuclear Society 2011
Vipre-W/Mefisto-T - A Mechanistic Toll For Transient Predictions Of Dryout In Bwr Fuel
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Transient Void, Pressure Drop And Critical Power Bfbt Benchmark Analysis And Results With Vipre-W/Mefisto-T
J-M. Le Corre, C. Adamsson, P. Alvarez
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
On A Best-Estimate Approach To Calculation Of Dryout Probability During Bwr Transients
C. Adamsson, J-M. Le Corre,
Proc. Nureth-14, Toronto, Canada, September 25-30, 2011
Discted Dynamic Event Tree Analysis Of Mloca Using Ads-Trace Ads-Trace
D.R. Karanki, V.N. Dang, T-W. Kim
Proc. Top. Meetg. On Probabilistic Safety Assessment And Analysis, Ans Psa2011, Wilimington, Us, March 13-17, 2011
