2010
Quantitative Analysis Of Effect Of Power Uprate On Core Damage Frequency Of Mbloca
T.W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Thermal-Hydraulic Analysis Of An Intermediate Loca Test At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Analysis Of Fuel Rod Behaviour In Epr During Base Irradiation And Loca-Transient Utilizing Falcon
Y. Yun, G. Khvostov, J. Freixa, M.A. Zimmermann
Proc. Lwr Fuel Performance Topfuel 2010 Meeting, Orlando, Florida, Usa, September 26-29, 2010
Development And Validation Of A Cfd Model For The Epr Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Set-Up Of A Validation Strategy For The Coupled Code Cfx/Trace In The Floris Facility With The Aid Of Cfd Simulations
D. Bertolloto,
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis Of A Bwr Nuclear Heating Transient
H. Ferroukhi, K. Hofer
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Peach Bottom 2 Turbine Trip 2 Simulation By Trace/S3k Coupled Code
K. Nikitin, J. Judd, G.M. Grandi, A. Manera, H. Ferroukhi
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Verification Of Pwr In- And Ex- Vessel Neutron Fluence Calculations With Mcnpx, Based On The H.B. Robinson-2 Dosimetry Benchmark
A. Vasiliev, R. Pittarello, H. Ferroukhi, E. Kolbe
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Assessment Of The Jeff-3.1.1 Neutron Data Library For Cse Of Lwr Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Comparison Of Neutron Data Libraries For The Analysis Of The H.B.Robinson-2 Pressure Vessel Benchmark With The Mcnpx Code
A. Vasiliev, R. Pittarello, E. Kolbe, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The Loca Based On Hrp Experiments And Results Of Calculation By Falcon Coupled With The Frelax Model
G. Khvostov, M.A. Zimmermann, W. Wiesenack, G. Ledergerber
Proc. Enlarged Halden Group Meeting, Norway, 14-19 March 2010
Core-Shell Vs Rigid-Ion Model For The Study Of Point Defects In Uo2
F. Devynck, M. Krack
Proc. Nuclear Materials 2010 Conference (Numath2010), Zkm, Karlsruhe, Germany, October 4-7, 2010
Benchmarking Of Transient Codes Against Cycle 19 Measurements At Leibstadt Nuclear Power Plant (Kkl)
C. Aguirre, S. Opel, H. Ferroukhi, G. Grandi, L. Belblidia, M. Thunman, C. Rotander,B-G. Bergdahl, S. Baumgartner, G. Ledergerber
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Oecd/Nea Expert Group On Uncertainty Analysis For Criticality Safety Assessment: Current Activities
T. Ivanova, F. Fernex, E. Kolbe, A. Vasiliev, G-S. Lee, S-W. Woo, D. Mennerdahl, Y. Nagaya, J-C. Neuber, A. Hoefer, B. Rearden, D. Mueller, Y. Rugama
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
A Low-Order Quasidiffusion Discretization Via Linear-Continuous Finite-Elements On Unstructure Triangular Meshes
W. Wieselquist
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
T.W. Kim, V.N. Dang, M.A. Zimmermann, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Thermal-Hydraulic Analysis Of An Intermediate Loca Test At The Rosa Facility Including Uncertainty Evaluation
J. Freixa, T-W. Kim, A. Manera
Proc. Int. Mtg. On Nucl. Thermal-Hydraulics, Operation And Safety Nuthos-8, Shanghai, China, October 10-14, 2010
Analysis Of Fuel Rod Behaviour In Epr During Base Irradiation And Loca-Transient Utilizing Falcon
Y. Yun, G. Khvostov, J. Freixa, M.A. Zimmermann
Proc. Lwr Fuel Performance Topfuel 2010 Meeting, Orlando, Florida, Usa, September 26-29, 2010
Development And Validation Of A Cfd Model For The Epr Pressure Vessel
V. Petrov, A. Manera
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Set-Up Of A Validation Strategy For The Coupled Code Cfx/Trace In The Floris Facility With The Aid Of Cfd Simulations
D. Bertolloto,
Proc. Int. Congress On Advances in Nuclear Power Plants (Icapp'10), San Diego, California, Usa, June 13-17, 2010
Coupled 3-D Neutronics/Thermal-Hydraulic Core Analysis Of A Bwr Nuclear Heating Transient
H. Ferroukhi, K. Hofer
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Peach Bottom 2 Turbine Trip 2 Simulation By Trace/S3k Coupled Code
K. Nikitin, J. Judd, G.M. Grandi, A. Manera, H. Ferroukhi
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Verification Of Pwr In- And Ex- Vessel Neutron Fluence Calculations With Mcnpx, Based On The H.B. Robinson-2 Dosimetry Benchmark
A. Vasiliev, R. Pittarello, H. Ferroukhi, E. Kolbe
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Assessment Of The Jeff-3.1.1 Neutron Data Library For Cse Of Lwr Fuel Storage Pools
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Comparison Of Neutron Data Libraries For The Analysis Of The H.B.Robinson-2 Pressure Vessel Benchmark With The Mcnpx Code
A. Vasiliev, R. Pittarello, E. Kolbe, H. Ferroukhi
Proc. Int. Conf. On Nuclear Data For Science And Technology, Nd2010, Jeju Island, Korea, 26-30 April, 2010
Some Insights Into The Role Of Axial Gas Flow In Fuel Rod Behaviour During The Loca Based On Hrp Experiments And Results Of Calculation By Falcon Coupled With The Frelax Model
G. Khvostov, M.A. Zimmermann, W. Wiesenack, G. Ledergerber
Proc. Enlarged Halden Group Meeting, Norway, 14-19 March 2010
Core-Shell Vs Rigid-Ion Model For The Study Of Point Defects In Uo2
F. Devynck, M. Krack
Proc. Nuclear Materials 2010 Conference (Numath2010), Zkm, Karlsruhe, Germany, October 4-7, 2010
Benchmarking Of Transient Codes Against Cycle 19 Measurements At Leibstadt Nuclear Power Plant (Kkl)
C. Aguirre, S. Opel, H. Ferroukhi, G. Grandi, L. Belblidia, M. Thunman, C. Rotander,B-G. Bergdahl, S. Baumgartner, G. Ledergerber
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
Oecd/Nea Expert Group On Uncertainty Analysis For Criticality Safety Assessment: Current Activities
T. Ivanova, F. Fernex, E. Kolbe, A. Vasiliev, G-S. Lee, S-W. Woo, D. Mennerdahl, Y. Nagaya, J-C. Neuber, A. Hoefer, B. Rearden, D. Mueller, Y. Rugama
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
A Low-Order Quasidiffusion Discretization Via Linear-Continuous Finite-Elements On Unstructure Triangular Meshes
W. Wieselquist
Proc. Int. Conf. Advances in Reactor Physics To Power The Nuclear Renaissance, Physor 2010 Pittsburgh, Usa, May 9-14, 2010
2009
Trace And Relap5 Thermal-Hydraulic Analysis On Boron Dilution Tests At The Pkl Facility
J. Freixa, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Effect Of Power Uprate On Exceedance Frequency During Mbloca With Minimum Specifications For Success
T-W. Kim, A. Manera, M.A. Zimmermann, V.N. Dang
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Toward The Prediction Of Temperature Fluctuations By Means Of Steady Rans For The Estimation Of Thermal Fatigue
A. Manera, H.M. Prasser, R. Lechner, T. Frank
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Simulation Of Reflood Experiments Using The Best-Estimate Thermal-Hydraulic Code Trace
K. Nikitin, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Assessment Of S(Alpha,Beta) Libraries For Criticality Safety Evaluations Of Wet Storage Pools By Refined Trend Analyses
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Criticality Safety Division **Topical Meeting Ncsd 2009, Richland, Washington, Us, September 13-17, 2009
Parametric Study Of Fuel Rod Behaviour During The Ria Using The Modified Falcon Code
G. Khvostov, M.A. Zimmermann, G. Ledergerber
Proc. Oecd/Nea Workshop On Nuclear Fuel Behaviour During Reactivity Initiated Accidents, Paris, France, September 9-11, 2009
A Dynamic Model For Fission Gas Release And Gaseous Swelling Integrated Into The Falcon Fuel Analysis And Licensing Code
G. Khvostov
Proc. **Top Fuel 2009, Paris, France, September 6-10, 2009
Towards Quantification Of Plant Safety Margins - A Status Report
M.A. Zimmermann, T-W. Kim, S. Laroche, A. Ui, S. Ebata, J-J. Jeong, H-G. Lim, S-H. Ahn, M. Gavrilas, J. Hortal
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan , September 27-October 2, 2009
Toward The Prediction Of Temperature Fluctuations By Means Of Steady Rans For The Estimation Of Thermal Fatigue
A. Manera, H.M. Prasser, R. Lechner, T. Frank
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan, September 27-October 2, 2009
Insights Into Fuel Rod Performance Codes During Ramps: Results Of A Code Benchmark Based On The Scip Project
L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou
Proc. of Top Fuel 2009, Paris, France, September 2009
A Quasidiffusion Method For Unstructured Quadrilateral Meshes In 2d Xy Geometry
W.A. Wieselquist, D. Y. Anistratov
Proc. Int. Conf. On Mathematics, Computational Methods And Reactor Physics (Mc2009), Saratoga Springs, New York, May 3-7, 2009
J. Freixa, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Effect Of Power Uprate On Exceedance Frequency During Mbloca With Minimum Specifications For Success
T-W. Kim, A. Manera, M.A. Zimmermann, V.N. Dang
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Toward The Prediction Of Temperature Fluctuations By Means Of Steady Rans For The Estimation Of Thermal Fatigue
A. Manera, H.M. Prasser, R. Lechner, T. Frank
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Simulation Of Reflood Experiments Using The Best-Estimate Thermal-Hydraulic Code Trace
K. Nikitin, A. Manera
Proc. 13th Int. **Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan September 27-October 2, 2009
Assessment Of S(Alpha,Beta) Libraries For Criticality Safety Evaluations Of Wet Storage Pools By Refined Trend Analyses
E. Kolbe, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Criticality Safety Division **Topical Meeting Ncsd 2009, Richland, Washington, Us, September 13-17, 2009
Parametric Study Of Fuel Rod Behaviour During The Ria Using The Modified Falcon Code
G. Khvostov, M.A. Zimmermann, G. Ledergerber
Proc. Oecd/Nea Workshop On Nuclear Fuel Behaviour During Reactivity Initiated Accidents, Paris, France, September 9-11, 2009
A Dynamic Model For Fission Gas Release And Gaseous Swelling Integrated Into The Falcon Fuel Analysis And Licensing Code
G. Khvostov
Proc. **Top Fuel 2009, Paris, France, September 6-10, 2009
Towards Quantification Of Plant Safety Margins - A Status Report
M.A. Zimmermann, T-W. Kim, S. Laroche, A. Ui, S. Ebata, J-J. Jeong, H-G. Lim, S-H. Ahn, M. Gavrilas, J. Hortal
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan , September 27-October 2, 2009
Toward The Prediction Of Temperature Fluctuations By Means Of Steady Rans For The Estimation Of Thermal Fatigue
A. Manera, H.M. Prasser, R. Lechner, T. Frank
Proc. 13th Int. Topical. Meetg. On Nuclear Reactor Thermal Hydraulics Nureth-13, Kanazawa, Japan, September 27-October 2, 2009
Insights Into Fuel Rod Performance Codes During Ramps: Results Of A Code Benchmark Based On The Scip Project
L.E. Herranz, I. Vallejo, G. Khvostov, J. Sercombe, G. Zhou
Proc. of Top Fuel 2009, Paris, France, September 2009
A Quasidiffusion Method For Unstructured Quadrilateral Meshes In 2d Xy Geometry
W.A. Wieselquist, D. Y. Anistratov
Proc. Int. Conf. On Mathematics, Computational Methods And Reactor Physics (Mc2009), Saratoga Springs, New York, May 3-7, 2009
2008
Single-Phase Mixing Studies By Means Of A Directly Coupled Cfd/System-Code Tool
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Cd-Rom,Fp412)
Cfd Simulations Of A Single-Phase Mixing Experiment
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Youth. Nuclear Congress Iync 2008 September 20-26, 2008, Interlaken, Switzerland
Estimation Of The Fast Neutron Fluence At Control Rod Tips Using A 3-D Diffusion/2-D Transport Calculation Scheme
H. Ferroukhi H., J-M. Hollard, M.A. Zimmermann, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Core Modelling And Analysis Of The Swiss Nuclear Power Plants For Qualified R&D Applications
H. Ferroukhi , K. Hofer, J-M. Hollard, A. Vasiliev, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Comparative Study Of Coretran And Simulate-3k For Main Steam Line Break Analyses
H. Ferroukhi , O. Zerkak, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Parametric Study Of The Behaviour Of A Pre-Irradiated Bwr Fuel Rod Under Conditions Of Loca Simulated In The Halden In-Pile Test System With The Falcon Code
G. Khvostov, M.A. Zimmermann , G. Ledergerber, E. Kolstad, R. Montgomery
Proc.Water Reactor Fuel Performance Meetg.,Wrfpm 2008, 19-23 October 2008, Seoul, Korea
On The Use Of The Falcon Code For Modeling The Behaviour Of High Burn-Up Bwr Fuel During The Ls-1 Pulse-Irradiation Test
G. Khvostov, M.A. Zimmermann, T. Sugiyama, T. Fuketa
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Definition Of Optimal Parameters Of Fuel Rod Design And Test Conditions For The High Temperature Loca Experiment Ifa-650.7 Using The Falcon Fuel Behaviour Code
G. Khvostov, M.A. Zimmermann, R. Stoenescu, G. Ledergerber
Enlarged Halden Programme Group Meeting Ehpgm 2008, 18-23 May 2008, Loen, Norway
On The Use Of Importance Factors From Monte Carlo Calculations For Efficient Fast Neutron Fluence Prediction
A. Vasiliev, H. Ferroukhi, E. Kolbe, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Propagation Of Void Fraction Uncertainty Measures In The Retran-3d Simulation Of The Peach Bottom Turbine Trip
P. Vinai, R. Macian-Juan, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Fp607)
Effects Of The Core Inlet Mixing Modelling On A Main Steam Line Break Analysis At Hot Full Power
O. Zerkak, H. Ferroukhi
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Effect Of Longitudinal Pitch On The Heat Transfer Characteristics Of Aligned Tube Banks In Crossflow
T-W. Kim
Proc. Nuthos-7, 5-9 October 2008, Seoul, Korea
Code-To-Code Comparison For Blowdown Transients At Supercritical Conditions
A. Manera, O. Antoni
Proc. Jahrestagung Kerntechnik 2008, 27-29 May 2008, Hamburg, Germany
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Cd-Rom,Fp412)
Cfd Simulations Of A Single-Phase Mixing Experiment
D. Bertolotto , A. Manera, B.L. Smith, H.M. Prasser, R. Chawla
Proc.Int.Youth. Nuclear Congress Iync 2008 September 20-26, 2008, Interlaken, Switzerland
Estimation Of The Fast Neutron Fluence At Control Rod Tips Using A 3-D Diffusion/2-D Transport Calculation Scheme
H. Ferroukhi H., J-M. Hollard, M.A. Zimmermann, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Core Modelling And Analysis Of The Swiss Nuclear Power Plants For Qualified R&D Applications
H. Ferroukhi , K. Hofer, J-M. Hollard, A. Vasiliev, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Comparative Study Of Coretran And Simulate-3k For Main Steam Line Break Analyses
H. Ferroukhi , O. Zerkak, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Parametric Study Of The Behaviour Of A Pre-Irradiated Bwr Fuel Rod Under Conditions Of Loca Simulated In The Halden In-Pile Test System With The Falcon Code
G. Khvostov, M.A. Zimmermann , G. Ledergerber, E. Kolstad, R. Montgomery
Proc.Water Reactor Fuel Performance Meetg.,Wrfpm 2008, 19-23 October 2008, Seoul, Korea
On The Use Of The Falcon Code For Modeling The Behaviour Of High Burn-Up Bwr Fuel During The Ls-1 Pulse-Irradiation Test
G. Khvostov, M.A. Zimmermann, T. Sugiyama, T. Fuketa
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Definition Of Optimal Parameters Of Fuel Rod Design And Test Conditions For The High Temperature Loca Experiment Ifa-650.7 Using The Falcon Fuel Behaviour Code
G. Khvostov, M.A. Zimmermann, R. Stoenescu, G. Ledergerber
Enlarged Halden Programme Group Meeting Ehpgm 2008, 18-23 May 2008, Loen, Norway
On The Use Of Importance Factors From Monte Carlo Calculations For Efficient Fast Neutron Fluence Prediction
A. Vasiliev, H. Ferroukhi, E. Kolbe, M.A. Zimmermann
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Propagation Of Void Fraction Uncertainty Measures In The Retran-3d Simulation Of The Peach Bottom Turbine Trip
P. Vinai, R. Macian-Juan, R. Chawla
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland (Fp607)
Effects Of The Core Inlet Mixing Modelling On A Main Steam Line Break Analysis At Hot Full Power
O. Zerkak, H. Ferroukhi
Proc.Int.Conf.On The Physics of Reactors, Physor'08, September 14-19, 2008, Interlaken, Switzerland
Effect Of Longitudinal Pitch On The Heat Transfer Characteristics Of Aligned Tube Banks In Crossflow
T-W. Kim
Proc. Nuthos-7, 5-9 October 2008, Seoul, Korea
Code-To-Code Comparison For Blowdown Transients At Supercritical Conditions
A. Manera, O. Antoni
Proc. Jahrestagung Kerntechnik 2008, 27-29 May 2008, Hamburg, Germany
2007
Assessment Of The Capability Of The Trace Code To Model Propagation Of Linear Acoustic Pressure Waves In One-Dimensional Flow
W. Barten, A. Manera, Juan. Macian,
Nureth-12, 30 September- 4 October 2007, Pittsburgh, Usa
Pwr Cell Calculations Using Apollo-2 Within The Nuresim Benchmark Framework
H. Ferroukhi, J. Hollard, Zerkak. M, Coddington. O,
Trans.American.Nuclear.Society, Vol. 97, Pp 703-704 (2007)
Assessment Of The Chf Models In Trace Code Against Rod Bundle Experimental Data
A. Jasiulevicius, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Simulation Of Rosa-V Test 6.2 Using Trace V.4.274 Code
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Modeling The Effects Of Axial Fuel Relocation In The Ifa-650.4. Loca Test
G. Khvostov, A. Romano, M. Zimmermann,
Enlarged Halden Project Group Meeting, 11-16 March 2007, Storefjell, Norway
Validation Of Standard Neutron Data Libraries For Lwr Storage Pools And Transport Casks Criticality Safety Evaluation
E. Kolbe, A. Vasiliev, M. Zimmermann,
Nuclear Data Conference, Nd-2007, 22-27 April 2007, Nice, France
Assessment Of Trace Film Condensation Models With And Without Non-Condensable Gases
A. Manera, Juan. Macian,
Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa
On The Observation Of Discrepancies In The O-16 (N,Alpha) Data Between Different Evaluated Nuclear Data Files,
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Nd-2007, 22-27 April 2007, Nice, France
Lwr Multi-Physics Developments And Applications Within The Framework Of The Nuresim Europen Project
O. Zerkak, P. Coddington, N. Crouzet, E. Rover, J. Jimenez, D. Cuervo
Proc. Int. Top.Meetg. On Mathematics &Computation And Supercomputing in Nuclear Applications, M&C+Sna 2007, 15-19 April 2007, Monterey, Usa
Stability Effect Of The Lateral Lift Force In Homogeneous Bubbly Flow
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Proc. Icmf2007, 9-13 July 2007, Leipzig, Germany
Comparison Between Wire-Mesh Sensor And Conductive Needle-Probes For Measurement Of Interfacial Area Densities
A. Manera, S. Paranjape, B. Ozar, M. Ishii, Hm. Prasser
Proc. Icone-15, 22-26 April 2007, Nagoya, Japan
Investigations On Mixing Phenomena In Single-Phase Flows In A T-Junction Geometry
R. Zboray, A. Manera, B. Niceno, Hm. Prasser
Proc. Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa, Cd-Rom
W. Barten, A. Manera, Juan. Macian,
Nureth-12, 30 September- 4 October 2007, Pittsburgh, Usa
Pwr Cell Calculations Using Apollo-2 Within The Nuresim Benchmark Framework
H. Ferroukhi, J. Hollard, Zerkak. M, Coddington. O,
Trans.American.Nuclear.Society, Vol. 97, Pp 703-704 (2007)
Assessment Of The Chf Models In Trace Code Against Rod Bundle Experimental Data
A. Jasiulevicius, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Simulation Of Rosa-V Test 6.2 Using Trace V.4.274 Code
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Icone-15, 22-26 April 2007, Nagoya, Japan
Modeling The Effects Of Axial Fuel Relocation In The Ifa-650.4. Loca Test
G. Khvostov, A. Romano, M. Zimmermann,
Enlarged Halden Project Group Meeting, 11-16 March 2007, Storefjell, Norway
Validation Of Standard Neutron Data Libraries For Lwr Storage Pools And Transport Casks Criticality Safety Evaluation
E. Kolbe, A. Vasiliev, M. Zimmermann,
Nuclear Data Conference, Nd-2007, 22-27 April 2007, Nice, France
Assessment Of Trace Film Condensation Models With And Without Non-Condensable Gases
A. Manera, Juan. Macian,
Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa
On The Observation Of Discrepancies In The O-16 (N,Alpha) Data Between Different Evaluated Nuclear Data Files,
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Nd-2007, 22-27 April 2007, Nice, France
Lwr Multi-Physics Developments And Applications Within The Framework Of The Nuresim Europen Project
O. Zerkak, P. Coddington, N. Crouzet, E. Rover, J. Jimenez, D. Cuervo
Proc. Int. Top.Meetg. On Mathematics &Computation And Supercomputing in Nuclear Applications, M&C+Sna 2007, 15-19 April 2007, Monterey, Usa
Stability Effect Of The Lateral Lift Force In Homogeneous Bubbly Flow
D. Lucas, E. Krepper, H. Prasser, Manera. M,
Proc. Icmf2007, 9-13 July 2007, Leipzig, Germany
Comparison Between Wire-Mesh Sensor And Conductive Needle-Probes For Measurement Of Interfacial Area Densities
A. Manera, S. Paranjape, B. Ozar, M. Ishii, Hm. Prasser
Proc. Icone-15, 22-26 April 2007, Nagoya, Japan
Investigations On Mixing Phenomena In Single-Phase Flows In A T-Junction Geometry
R. Zboray, A. Manera, B. Niceno, Hm. Prasser
Proc. Nureth-12, 30 September - 4 October 2007, Pittsburgh, Usa, Cd-Rom
2006
Simulations Of The Halden Ifa-650.3/.4 High Burnup Loca Test With Trace And Falcon: A Preliminary Study On Axial Relocation
Y. Aounallah, G. Khvostov, A. Romano, H. Wallin, M. Zimmermann, Kolstad. A, Ek. E, Kekkonen. M,
Int. Meeting On Lwr Fuel Performance (**Topfuel 2006), 22-26 October 2006, Salamanca, Spain
Analysis Of Umsicht Water Hammer Benchmark Tests: Results From Psi Using Trace And Relap5 Codes
W. Barten, A. Jasiulevicius, O. Zerkak, Juan. Macian,
7th Int. Conference On Hydroinformatics (Hic 2006), 4-8 September 2006, Nice, France, Vol. Ii, 1227-1234, 2006
Investigation Of Heat Transfer Mechanismus Under Shutdown Plant Conditions With Tracev4. 160
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Impact Of Different Correlation On Tracev4.160 Predicted Critical Heat Flux
A. Jasiulevicius, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Predictions Of Critical Heat Flux In Annular Pipes With Tracev4.160 Code
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Steady-State Film Boiling Heat Transfer Simulated With Tracev4.160
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Assessment Of Standard Point-Wise Neutron Data Libraries For Criticality Safety Analysis With A Monte Carlo Code
E. Kolbe, A. Vasiliev, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
Casmo-4/Simulate-3/Mcnpx Analysis Of A Reactor Pressure Vessel Scraping Test
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
A Methodology For The Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, Juan. Macian, Chawla. R,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1087-1098, 2006
Y. Aounallah, G. Khvostov, A. Romano, H. Wallin, M. Zimmermann, Kolstad. A, Ek. E, Kekkonen. M,
Int. Meeting On Lwr Fuel Performance (**Topfuel 2006), 22-26 October 2006, Salamanca, Spain
Analysis Of Umsicht Water Hammer Benchmark Tests: Results From Psi Using Trace And Relap5 Codes
W. Barten, A. Jasiulevicius, O. Zerkak, Juan. Macian,
7th Int. Conference On Hydroinformatics (Hic 2006), 4-8 September 2006, Nice, France, Vol. Ii, 1227-1234, 2006
Investigation Of Heat Transfer Mechanismus Under Shutdown Plant Conditions With Tracev4. 160
A. Jasiulevicius, O. Zerkak, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Impact Of Different Correlation On Tracev4.160 Predicted Critical Heat Flux
A. Jasiulevicius, Juan. Macian,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1820-1828, 2006
Predictions Of Critical Heat Flux In Annular Pipes With Tracev4.160 Code
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Steady-State Film Boiling Heat Transfer Simulated With Tracev4.160
A. Jasiulevicius, Juan. Macian,
14th Int. Conference On Nuclear Engineering (Icone14),17-20 July 2006, Miami, Usa, 2006
Assessment Of Standard Point-Wise Neutron Data Libraries For Criticality Safety Analysis With A Monte Carlo Code
E. Kolbe, A. Vasiliev, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
Casmo-4/Simulate-3/Mcnpx Analysis Of A Reactor Pressure Vessel Scraping Test
A. Vasiliev, H. Ferroukhi, M. Zimmermann,
Proc. Physor-2006, 10-14 September 2006, Vancouver, Canada, 2006
A Methodology For The Quantification Of Uncertainty In Best Estimate Code Physical Models
P. Vinai, Juan. Macian, Chawla. R,
Int. Congress On Advances in Nuclear Power Plants (Icapp'06), 4-8 June 2006, Reno, Usa, 1087-1098, 2006