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Ce contenu n'est pas disponible en français.Conference Publications 2015
Complink: A Versatile Tool For Automatizing The Representation Of Material Data In Mcnp Models
M. Pecchia, J. J. Herrero, H. Ferroukhi, A. Vasiliev, S. Canepa, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Towards Application Of Neutron Cross-Section Uncertainty Propagation Capability In The Criticality Safety Methodology
A. Vasiliev, D. Rochman, T. Zhu, M. Pecchia, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Computational Scheme For Burnup Credit Applied To Long Term Waste Disposal
J.J. Herrero, M. Pecchia, H. Ferroukhi, S. Canepa, A. Vasiliev, S. Caruso
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Modeling Of Axial Distribution Of Released Fission Gas In Kkl Bwr Fuel Rods During Base Irradiation
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Proc. Water Reactor Fuel Performance Meeting Topfuel 2015, Zurich, Switzerland, September 13-17, 2015
Ranking Of Uncertain Parameters For Dynamic Event Tree Analysis: A Case Study Based On A Station Blackout Scenario
S. Rahman, D.R. Karanki, A. Epiney, O. Zerkak, V.N. Dang
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Assessment Of Openfoam Cfd Toolbox For Gravity Driven Mixing Flows In A Reactor Pressure Vessel
R. Puragliesi, Q. Zhou, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Computational Fluid Dynamics Analysis Of The Fluid Flow And Heat Transfer In The Core Bypass Region Of A Pwr
I. Clifford, A. Vasiliev, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Methodology For Global Sensitivity Analysis Of Transient Code Output Applied To A Reflood Experiment Model Using Trace
D. Wicaksono, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Trace/Simulate-3k Analysis Of The Nea/Oecd Oskarshamn-2 Stability Benchmark
A. Dokhane, O. Zerkak, H. Ferroukhi, I. Gajev, J. Judd, T. Kozlowski
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Towards A Consolidated Approach For The Validation Of Plant System Codes And Models: A Case Study For A Bwr Fast Depressurization Event
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Development, Verification And Test Application Of A Hybrid Casmo-5/Serpent Depletion Scheme
O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz, H.Perrier
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Preparation Of Pin-By-Pin Nuclear Libraries With Superhomogenization Method For Ntracer And Dort Core Calculations
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Bwr Full Core Analysis With Serpent/Simulate-3 Hybrid Stochastic/Determinstic Code Sequence
M. Hursin, L. Rossinelli, H. Ferroukhi And A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Scalability Benchmarking Methodology For Hybrid Parallel Core Calculations With The Code Ntracer
S. Canepa, M. Krack, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Peak Cladding Temperature Prediction And Assessment For The Leibstadt Npp Using Simulate-3k
D. Chionis, K. Hofer, A.Pautz
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015
Enhancement And Validation Of Bwr Mcnp Activation Simulations For Swiss Decommissioning Planning
V. Bykov
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015
M. Pecchia, J. J. Herrero, H. Ferroukhi, A. Vasiliev, S. Canepa, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Towards Application Of Neutron Cross-Section Uncertainty Propagation Capability In The Criticality Safety Methodology
A. Vasiliev, D. Rochman, T. Zhu, M. Pecchia, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Computational Scheme For Burnup Credit Applied To Long Term Waste Disposal
J.J. Herrero, M. Pecchia, H. Ferroukhi, S. Canepa, A. Vasiliev, S. Caruso
Proc. Int. Conf. Nuclear Criticality Safety, Icnc 2015, Charlotte, Nc, Usa, September 13-17, 2015
Modeling Of Axial Distribution Of Released Fission Gas In Kkl Bwr Fuel Rods During Base Irradiation
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Proc. Water Reactor Fuel Performance Meeting Topfuel 2015, Zurich, Switzerland, September 13-17, 2015
Ranking Of Uncertain Parameters For Dynamic Event Tree Analysis: A Case Study Based On A Station Blackout Scenario
S. Rahman, D.R. Karanki, A. Epiney, O. Zerkak, V.N. Dang
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Assessment Of Openfoam Cfd Toolbox For Gravity Driven Mixing Flows In A Reactor Pressure Vessel
R. Puragliesi, Q. Zhou, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Computational Fluid Dynamics Analysis Of The Fluid Flow And Heat Transfer In The Core Bypass Region Of A Pwr
I. Clifford, A. Vasiliev, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Methodology For Global Sensitivity Analysis Of Transient Code Output Applied To A Reflood Experiment Model Using Trace
D. Wicaksono, O. Zerkak, A. Pautz
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Trace/Simulate-3k Analysis Of The Nea/Oecd Oskarshamn-2 Stability Benchmark
A. Dokhane, O. Zerkak, H. Ferroukhi, I. Gajev, J. Judd, T. Kozlowski
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Towards A Consolidated Approach For The Validation Of Plant System Codes And Models: A Case Study For A Bwr Fast Depressurization Event
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Proc. Int. Top.Meetg. Nucl. Reactor Thermal-Hydraulics Nureth-16, Chicago, Usa, August 30 - September 4, 2015
Development, Verification And Test Application Of A Hybrid Casmo-5/Serpent Depletion Scheme
O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz, H.Perrier
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Preparation Of Pin-By-Pin Nuclear Libraries With Superhomogenization Method For Ntracer And Dort Core Calculations
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Bwr Full Core Analysis With Serpent/Simulate-3 Hybrid Stochastic/Determinstic Code Sequence
M. Hursin, L. Rossinelli, H. Ferroukhi And A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Scalability Benchmarking Methodology For Hybrid Parallel Core Calculations With The Code Ntracer
S. Canepa, M. Krack, H. Ferroukhi, A. Pautz
Proc. Joint Int. Conf. On Mathematics And Computation, Supercomputing in Nuclear Applications And The Monte Carlo Method, M&C+Sna+Mc 2015, Tennessee, Usa, April 19-23, 2015
Peak Cladding Temperature Prediction And Assessment For The Leibstadt Npp Using Simulate-3k
D. Chionis, K. Hofer, A.Pautz
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015
Enhancement And Validation Of Bwr Mcnp Activation Simulations For Swiss Decommissioning Planning
V. Bykov
Proc. American Nucl. Societ Student Conference 2015, College Station, Tx Texas A&M University, April 9-11, 2015
