Conference Publications of the STARS Program
2019
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Alcayne V, Kimura A, Mendoza E, Cano-Ott D, Aberle O, Amaducci S, et al.
Measurement of the 244Cm and 246Cm neutron-induced cross sections at the n_TOF facility
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019. https://doi.org/10.1007/978-3-030-22204-8_4
DORA PSI -
Babiano-Suarez V, Caballero L, Domingo-Pardo C, Ladarescu I, Aberle O, Alcayne V, et al.
Characterization and first test of an i-TED prototype at CERN n_TOF
In: García-Ramos J-E, Andrés MV, Pérez-Bernal F, Valera JA, Moro AM, eds. Basic concepts in nuclear physics: theory, experiments and applications. 2018 La Rábida international scientific meeting on nuclear physics. Vol. 225. Springer proceedings in physics. Cham: Springer; 2019. https://doi.org/10.1007/978-3-030-22204-8_18
DORA PSI -
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Measurement of the gas velocity in a water-air mixture in crocus by neutron noise technique
Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
DORA PSI -
Hursin M, Park J, Kim W, Siefman D, Perret G, Vasiliev A, et al.
Uncertainty quantification of LWR-proteus phase II experiments using CASMO-5
Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, OR, USA.
DORA PSI -
Lamirand V, Laureau A, Rochman D, Perret G, Gruel A, Leconte P, et al.
An experimental programme optimized with uncertainty propagation: PETALE in the CROCUS reactor
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019. https://doi.org/10.1051/epjconf/201921103003
DORA PSI -
Laureau A, Lamirand V, Rochman D, Pautz A
Total Monte Carlo acceleration for the PETALE experimental programme in the CROCUS reactor
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ web of conferences. sine loco: EDP Sciences; 2019. https://doi.org/10.1051/epjconf/201921103002
DORA PSI -
Massimi C, Aberle O, Alcayne V, Andrzejewski J, Audouin l., Bécares V, et al.
Data for the s process from n_TOF
In: Formicola A, Junker M, Gialanella L, Imbriani G, eds. Nuclei in the cosmos XV. Vol. 219. Springer proceedings in physics. Cham: Springer; 2019. https://doi.org/10.1007/978-3-030-13876-9_11
DORA PSI -
Papadionysiou M, Seongchan K, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Assessment of nTRACER and parcs performance for VVER configurations
Presented at: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019); August 25-29, 2019; Portland, USA.
DORA PSI -
Pecchia M, Vasiliev A, Perret G, Ferroukhi H
Benchmark Monte Carlo calculations with ENDF/B-VIII.0 and JEFF-3.3 libraries for LWR criticality safety assessments
Presented at: ICNC 2019 - 11th international conference on nuclear criticality safety; September 15-20, 2019; Paris, France.
DORA PSI -
Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
Comparison of computational fluid dynamics and subchannel numerical solutions of fuel assemblies characterized by bowing
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park: American Nuclear Society (ANS); 2019.
DORA PSI -
Rais A, Lamirand V, Pakari O, Laureau A, Pohlus J, Pohl C, et al.
Towards the validation of neutron noise simulators: qualification of data acquisition systems
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019.
DORA PSI -
Scolaro A, Clifford I, Fiorina C, Pautz A
Cladding plasticity modeling with the multidimensional fuel performance code OFFBEAT
In: Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019.
DORA PSI -
Scolaro A, Robert Y, Fiorina C, Clifford I, Pautz A
Coupling methodology for the multidimensional fuel performance code OFFBEAT and the Monte Carlo neutron transport code Serpent
In: Global/Top Fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019.
DORA PSI -
Tassan-Got L, Colonna N, Diakaki M, Eleme Z, Manna A, Sekhar A, et al.
Fission program at n_TOF
In: Serot O, Chebboubi A, eds. WONDER-2018 - 5th international workshop on nuclear data evaluation for reactor applications. Vol. 211. EPJ Web of Conferences. sine loco: EDP Sciences; 2019. https://doi.org/10.1051/epjconf/201921103006
DORA PSI -
Verma V, Demazière C, Vinai P, Ricciardi G, Jacqmin R
Assessment of the neutron noise induced by stationary fuel assembly vibrations in a light water reactor
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). Illinois: American Nuclear Society (ANS); 2019.
DORA PSI -
Wolfertz A, Adams R, Perret G
First tests of a gamma-blind fast neutron detector prototype based on ZnS and wavelength-shifting fibers
Presented at: ANS annual meeting 2019. The value of nuclear; June 9-13, 2019; Minneapolis, USA.
DORA PSI
2018
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Casanovas A, Domingo-Pardo C, Guerrero C, Lerendegui-Marco J, Calviño F, Tarifeño-Saldivia A, et al.
Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
In: Sun Y, ed. 16th international symposium on capture gamma-ray spectroscopy and related topics (CGS16). Vol. 178. EPJ web of conferences. sine loco: EDP Sciences; 2018. https://doi.org/10.1051/epjconf/201817803004
DORA PSI -
Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part I - simulation of stochastic phenomena with simulate-3K
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Chionis D, Dokhane A, Ferroukhi H, Girardin G, Pautz A
PWR neutron noise phenomenology: part II - qualitative comparison against plant data
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Cozzo C, Khvostov G
ATF developments in FALCON V1 at PSI
In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018.
DORA PSI -
De Sousa Ribeiro F, Calivá F, Chionis D, Dokhane A, Mylonakis A, Demazière C, et al.
Towards a deep unified framework for nuclear reactor perturbation analysis
In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018. https://doi.org/10.1109/SSCI.2018.8628637
DORA PSI -
Dokhane A, Vasiliev A, Rochman D, Ferroukhi H, Grandi G
Analyses of the SPERT-III RIA experiments with nuclear data uncertainty quantification using three different covariance matrix libraries
In: Proceedings of the PHYTRA4 conference. sine loco: American Nuclear Society (ANS); 2018.
DORA PSI -
Griffin PJ, Koning A, Rochman D
Importance of treating correlations in the uncertainty quantification of radiation damage metrics
In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018.
DORA PSI -
Hursin M, Siefman D, Perret G, Rochman D, Vasiliev A, Ferroukhi H
Determination of sobol sensitivity indices for correlated inputs with SHARK-X
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Lamirand V, Perret G, Radman S, Siefman D, Frajtag P, Hursin M, et al.
Design of separated element reflector experiments in CROCUS: PETALE
In: Sparks MH, DePriest KR, Vehar DW, eds. Reactor dosimetry: 16th international symposium. West Conshohocken, USA: ASTM International; 2018. https://doi.org/10.1520/STP160820170090
DORA PSI -
Lamirand V, De Izzarra G, Krasa A, Perret G, Pakari O, Frajtag P, et al.
Intercomparison of neutron noise measurement systems in the CROCUS reactor
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Mukin R, Clifford I, Ferroukhi H, Niffenegger M
Pressurized Thermal Shock (PTS) transient scenarios analysis with TRACE
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018. https://doi.org/10.1115/ICONE26-81749
DORA PSI -
Mukin R, Seidl M, Clifford I, Ferroukhi H
Sensitivity of CTF solution to subchannel window size
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Thermal hydraulics and safety analyses. New York: American Society of Mechanical Engineers (ASME); 2018. https://doi.org/10.1115/ICONE26-82546
DORA PSI -
Ngayam-Happy R, Cozzo C, Khvostov G, Krack M, Ferroukhi H
Fuel thermo-mechanical simulations with uncertainty quantification and sensitivity analysis of the OECD/NEA RIA code benchmark using FALCON and URANIE
Presented at: ANS Best estimate plus uncertainty International conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
DORA PSI -
Pakari O, Lamirand V, Perret G, Godat D, Hursin M, Frajtag P, et al.
Investigation of spatial effects on neutron noise measurements in the zero power reactor CROCUS
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Perret G, Rahman S, Wicaksono D
Deterministic sampling and Gaussian Process metamodel approach applied to a station black out accident model
Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
DORA PSI -
Puragliesi R, Mukin R, Clifford I, Ferroukhi H, Seidl M
Computational fluid dynamics as a tool for deriving subchannel model parameters - The PSBT case study
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Computational fluid dynamics (CFD); nuclear education and public acceptance. Vol. 8. New York: American Society of Mechanical Engineers (ASME); 2018. https://doi.org/10.1115/ICONE26-81743
DORA PSI -
Rochman D, Vasiliev A, Ferroukhi H, Janin D, Seidl M
Best estimate plus uncertainty analysis for the 244CM prediction in spent fuel characterization
Presented at: ANS best estimate plus uncertainty international conference (BEPU 2018); May 13-18, 2018; Lucca, Italy.
DORA PSI -
Scolaro A, Clifford I, Fiorina C, Pautz A
First steps towards the development of a 3D nuclear fuel behaviour solver with OpenFOAM
In: Proceedings of the 26th international conference on nuclear engineering (ICONE26). Nuclear fuel and material, reactor physics, and transport theory. Vol. 3. sine loco: American Society of Mechanical Engineers (ASME); 2018. https://doi.org/10.1115/ICONE26-82381
DORA PSI -
Siefman D, Hursin M, Aufiero M, Bidaud A, Pautz A
Convergence analysis and criterion for data assimilation with sensitivities from Monte Carlo neutron transport codes
In: Proceedings of the PHYSOR 2018. LaGrange Park, IL, USA: American Nuclear Society; 2018.
DORA PSI -
Sublet J-C, Koning A, Rochman D
TENDL-2017: the making of multi-faceted technological nuclear data library
In: Radiation protection and shielding division 20th topical meeting. Illinois: American Nuclear Society (ANS); 2018.
DORA PSI -
Tambouratzis T, Chionis D, Dokhane A
General regression neural networks for the concurrent, timely and reliable identification of detector malfunctions and/or nuclear reactor deviations from steady-state operation
In: Sundaram S, ed. Proceedings of the 2018 IEEE symposium series on computational intelligence (SSCI 2018). Piscataway: IEEE; 2018. https://doi.org/10.1109/SSCI.2018.8628700
DORA PSI
Impact of Nuclear Data Uncertainty in the Modeling of Recoil Atom Energy Distributions in Silicon
P.J. Griffin, A. Koning, D. Rochman
ANS RPSD 2018, 20th Topical Meeting of the Radiation Protection & Shielding Division of ANS Santa Fe, NM, August 26 31, 2018
Effect of Nuclear Data on the DNBR Preduction with Subchannel code COBRA-TF
R. Mukin, D. Rochman, I. Clifford, A. Vasiliev, H. Ferrouhki
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018
Global Sensitivity Analysis and Registration Strategy for Temperature Profiles of Reflood Experiment Simulations
G. Perret, D. Wicaksono
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018
Criticality Safety Evaluations for the concept of Swiss PWR Soent Fuel Geological Repository
A. Vasiliev, J. Herrero, D. Rochman, M. Pecchia, H. Ferroukhi, S. Caruso
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018
Representativity Analysis of the LWR-PROTEUS Phase II Experiments Using SHARKX Stochastic Sampling Method
M. Hursin, D. Siefman, G. Perret, A. Pautz
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018
The Importance of Experimental Uncertainty in the BEPU Approach
M. Hursin
BEPU 2018: Best Estimate Plus Uncertainty International Conference Lucca, Italy, May 13-18, 2018
Determination of Sobol Sensitivity Indices for Correlated Inputs with Shark-X
M. Hursin, D. Siefman, G. Perret, D. Rochman, A. Vasiliev, H. Ferrouhki
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018
Studies Of Intra-Pin Power Distributions In Operated Bwr Fuel Assemblies Using Mcnp With A Cycle Check-Up Methodology
M. Pecchia, H. Ferroukhi, A. Vasiliev, P. Grimm
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018
Studies On The Effects Of Local Power Peaking On Heat Transfer Under Dryout Conditions In Bwrs
I.Clifford, M. Pecchia, R. Mukin, H. Ferroukhi, A. Gorzel
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018
Towards Systematic And Continuous Tracking Of Neutron And Process Noise Signatures During Lwr Operation
A. Dokhane, D. Chionis, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018
On The Importance Of The Neutron Scattering Angular Distributions For The Lwr Fast Neutron Dosimetry
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems Cancun, Mexico, April 22-26, 2018
Optimization And Sensitivity Studies Towards Pwr Structures Activation Characterization Using The Mcnp Code
B. Jung, A. Vasiliev, M. Pecchia, H. Ferroukhi
Ans Student Conference 2018, University of Florida, Gainesville Fl, Usa, April 5 - 7 2018,
2017
Sic Caldding Behaviour: Experiments And Modelling At Psi
C. Cozzo, J. Bertsch, L. Fave, S. Rahman, A. Dokhane, M. Krack, M.A. Pouchon, Y. Dai, J-C. Chen, M. Pytel
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017
New Insights In The Fuel Grain Subdivision During In-Plant Irraditaion Up To High Burnup
M. Chollet, C. Cozzo, J. Bertsch, M. Martin, D. Grolimund, V-A. Samson
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017
Thermal Mixing Assessment Using 3d Thermal-Hydraulic And Cfd Codes
R. Mukin, R. Puragliesi, S. C. Ceuca, H. Austregesilo, A. Bousbia Salah
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017
Thermal Hydraulic Analysis Of Pwr Assembly Bowing Using Subchannel Code Cobra-Tf
R. Mukin, I. Clifford, H. Ferroukhi, M. Seidl
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017
Characterization Of The Energy-Dependent Uncertainty And Correlation In Silicon Neutron Displacement Damage Metrics
P. Griffin, D. Rochman, A. Koning
Epj Web of Conferences 146, 02008, Nd2016 (2017)
Talys/Tendl Verification And Validation Processes: Outcomes And Recommendations
M. Fleming, J-C. Sublet, M. R. Gilbert, A. Koning, D. Rochman
Epj Web of Conferences 146, 02033, (2017)
Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements
H.Sjostrand, S. Conroy, P. Helgesson, S. A. Hernandez, A. Koning, S. Pomp, D. Rochman
Epj Web of Conferences 146, 02034 (2017)
The Role Of Nuclear Data For Fusion Nuclear Technology
U. Fischer, M. Angelone, M. Avrigeanu, V. Avrigeanu, C. Bachmann, N. Dzysiuk, M. Fleming, A. Konobeev, I. Kodeli, A. Koning, H. Leeb, D. Leichtle, F. Ogando, P. Pereslavtsev, D. Rochman, P. Sauvan, S. Simakov
Proc. Int. Conf. Fusion Nuclear Technology Conference, Kyoto, September 25 -29, 2017
Trace/S3k Code Coupling Simulations Of A Bwr/4 Anticipated Transient Without Scram
Y. Aounallah
Proc. Canadian Nuclear Soeciety Meeting Niagara Falls, Canada, June 4-7, 2017
Simulations With Trace Of A Bwr/4 Steam Line Break Under Hot Standby Conditions
Y. Aounallah
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017
Simulate-3k Analyses Of Neutron Noise Response To Fuel Assembly Vibrations And Thermal-Hydraulics Parameters Fluctuations
D. Chionis, A. Dokhane, L. Belblidia, M. Pecchia, G. Girardin, H. Ferroukhi, A. Pautz
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Nodal And Pin-By-Pin Calculations Comparison With Codes Simulate-5 And Dyn3d
P. Mala, A. Pautz, S. Canepa, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Bowing Effects On Power And Burn-Up Distributions For Simplified Full Pwr And Bwr Cores
D. Rochman, P. Mala, H. Ferroukhi, A. Vasiliev, M. Seidl, D. Janin, J. Li
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Nuclear Data Uncertainty Decomposition For Spert-Iii Ria Experiments Using Simulate-3k And Shark-X
A. Dokhane, G. Grandi, O. Leray, D. Rochman, A. Vasiliev, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
C. Cozzo, J. Bertsch, L. Fave, S. Rahman, A. Dokhane, M. Krack, M.A. Pouchon, Y. Dai, J-C. Chen, M. Pytel
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017
New Insights In The Fuel Grain Subdivision During In-Plant Irraditaion Up To High Burnup
M. Chollet, C. Cozzo, J. Bertsch, M. Martin, D. Grolimund, V-A. Samson
Proc. 2017 Water Reactor Fuel Performance Meeting (Wrfpm2017), Jeju Island, Korea, September 10-14, 2017
Thermal Mixing Assessment Using 3d Thermal-Hydraulic And Cfd Codes
R. Mukin, R. Puragliesi, S. C. Ceuca, H. Austregesilo, A. Bousbia Salah
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017
Thermal Hydraulic Analysis Of Pwr Assembly Bowing Using Subchannel Code Cobra-Tf
R. Mukin, I. Clifford, H. Ferroukhi, M. Seidl
Proc. 17th Int. **Topical Meeting On Nuclear Reactor Thermal Hydraulics (Nureth-17), Xian, China, 3-9 September 2017
Characterization Of The Energy-Dependent Uncertainty And Correlation In Silicon Neutron Displacement Damage Metrics
P. Griffin, D. Rochman, A. Koning
Epj Web of Conferences 146, 02008, Nd2016 (2017)
Talys/Tendl Verification And Validation Processes: Outcomes And Recommendations
M. Fleming, J-C. Sublet, M. R. Gilbert, A. Koning, D. Rochman
Epj Web of Conferences 146, 02033, (2017)
Propagation Of Nuclear Data Uncertainties For Fusion Power Measurements
H.Sjostrand, S. Conroy, P. Helgesson, S. A. Hernandez, A. Koning, S. Pomp, D. Rochman
Epj Web of Conferences 146, 02034 (2017)
The Role Of Nuclear Data For Fusion Nuclear Technology
U. Fischer, M. Angelone, M. Avrigeanu, V. Avrigeanu, C. Bachmann, N. Dzysiuk, M. Fleming, A. Konobeev, I. Kodeli, A. Koning, H. Leeb, D. Leichtle, F. Ogando, P. Pereslavtsev, D. Rochman, P. Sauvan, S. Simakov
Proc. Int. Conf. Fusion Nuclear Technology Conference, Kyoto, September 25 -29, 2017
Trace/S3k Code Coupling Simulations Of A Bwr/4 Anticipated Transient Without Scram
Y. Aounallah
Proc. Canadian Nuclear Soeciety Meeting Niagara Falls, Canada, June 4-7, 2017
Simulations With Trace Of A Bwr/4 Steam Line Break Under Hot Standby Conditions
Y. Aounallah
Proc. Canadian Nuclear Society Meeting Niagara Falls, Canada, June 4-7, 2017
Simulate-3k Analyses Of Neutron Noise Response To Fuel Assembly Vibrations And Thermal-Hydraulics Parameters Fluctuations
D. Chionis, A. Dokhane, L. Belblidia, M. Pecchia, G. Girardin, H. Ferroukhi, A. Pautz
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Nodal And Pin-By-Pin Calculations Comparison With Codes Simulate-5 And Dyn3d
P. Mala, A. Pautz, S. Canepa, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Bowing Effects On Power And Burn-Up Distributions For Simplified Full Pwr And Bwr Cores
D. Rochman, P. Mala, H. Ferroukhi, A. Vasiliev, M. Seidl, D. Janin, J. Li
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
Nuclear Data Uncertainty Decomposition For Spert-Iii Ria Experiments Using Simulate-3k And Shark-X
A. Dokhane, G. Grandi, O. Leray, D. Rochman, A. Vasiliev, H. Ferroukhi
Proc. Mathematics & Computations M&C 2017, Jeju, Korea, April 16-20, 2017
2016
Simulations Of Level-Swell Experiments With Trace
Y. Aounallah
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
System Code Validation Series Based On A Consistent Plant Nodalisation Of The Rosa/Lstf Integral Test Facility Using Trace V5.0 Patch 4
I. Clifford, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Modeling And Analysis Of Selected Oecd Pkl3 Station-Blackout Experiments Using Trace
R. Mukin, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Influence Of Urans Turbulence Models On In-Vessel Flow Mixing During Cold Leg Accumulator Injection
R. Puragliesi, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Bayesian Calibration Of Thermal-Hydraulics Model With Time-Dependent Output
D. Wicaksono, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Evaluation Of Deterministic Sampling For Uncertainty Quantification In A Probabilistic Accident Analysis Model
S. Rahman, D.R. Karanki, D. Wicaksono, O. Zerkak, V.N. Dang
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
The Tendl Library: Hope, Reality And Future
D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. Van Der Marck, H. SjöStrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, A. Vasiliev
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016
Impact Of Nuclear Data Uncertainty On Safety Calculations For Spent Nuclear Fuel Geological Disposal
J.J. Herrero, D. Rochman, O. Leray, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09028, 2017)
Impact Of Implicit Effects On Uncertainties And Sensitivities Of The Doppler Coefficient Of A Lwr Pin Cell
M. Hursin, O. Leray, G.Perret, A.Pautz, F. Bostelmann, A. Aures, W. Zwermann
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09034, 2017)
Fission Yield Covariances For Jeff: A Bayesian Monte Carlo Method
O. Leray, D. Rochman, M. Fleming, J-C. Sublet, A. Koning, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09023, 2017)
Full Core Loca Analysis For Bwr/6 - Methodology And First Results
C. Cozzo, A. Epiney, S. Canepa, H. Ferroukhi, O. Zerkak, G. Khvostov,V. Brankov, A. Gorzel
Topfuel 2016, Boise, Idaho, Usa, September 11-16, 2016
Comparison Of Fission Yield Perturbation Methodologies On Nuclide Composition For A Pwr Uo2 Fuel Assembly
O. Leray, L. Fiorito, D. Rochman, H. Ferroukhi, A. Pautz, A. Stankovskiy, G. Van Den Eynde
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Validation Of Simulate-3k Against Spert-Iii Ria Experiments With Quantification Of Nuclear Data Uncertainties
A. Dokhane, O. Leray, D. Rochman, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Solution Of The Beavrs Benchmark Using Casmo-5 / Simulate-5 Code Sequence
V. Bykov, A. Vasiliev, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
On Causality Analysis Of Nuclear Reactor Noise Using Partial Directed Coherence
D. Chionis, A. Dokhane, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Comparative Study Of Casmo-5/Simulate-5 And Ntracer For Epr Core Analyses
S. Canepa, H. Ferroukhi, R. Min, H.G. Joo
Icapp 2016, San Francisco, Ca, Usa, April 17-20, 2016
Towards Analysis Of The Bowing Effect On Burnt Nuclear Fuel Compositions Using Serpent
J. Li, D. Rochman, J. Herrero, H. Ferroukhi, A. Vasiliev, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016
Extention Of Psi Fnf Modeling Methodology Validation Using Bwr Dosimetry Data
R. Savelli, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016
Y. Aounallah
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
System Code Validation Series Based On A Consistent Plant Nodalisation Of The Rosa/Lstf Integral Test Facility Using Trace V5.0 Patch 4
I. Clifford, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Modeling And Analysis Of Selected Oecd Pkl3 Station-Blackout Experiments Using Trace
R. Mukin, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Influence Of Urans Turbulence Models On In-Vessel Flow Mixing During Cold Leg Accumulator Injection
R. Puragliesi, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Bayesian Calibration Of Thermal-Hydraulics Model With Time-Dependent Output
D. Wicaksono, O. Zerkak, A. Pautz
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
Evaluation Of Deterministic Sampling For Uncertainty Quantification In A Probabilistic Accident Analysis Model
S. Rahman, D.R. Karanki, D. Wicaksono, O. Zerkak, V.N. Dang
Nuthos-11, Gyeongju, Korea, October 9-13, 2016
The Tendl Library: Hope, Reality And Future
D. Rochman, A.J. Koning, J.Ch. Sublet, M. Fleming, E. Bauge, S. Hilaire, P. Romain, B. Morillon, H. Duarte, S. Goriely, S.C. Van Der Marck, H. SjöStrand, S. Pomp, N. Dzysiuk, O. Cabellos, H. Ferroukhi, A. Vasiliev
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016
Impact Of Nuclear Data Uncertainty On Safety Calculations For Spent Nuclear Fuel Geological Disposal
J.J. Herrero, D. Rochman, O. Leray, A. Vasiliev, M. Pecchia, H. Ferroukhi, S. Caruso
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09028, 2017)
Impact Of Implicit Effects On Uncertainties And Sensitivities Of The Doppler Coefficient Of A Lwr Pin Cell
M. Hursin, O. Leray, G.Perret, A.Pautz, F. Bostelmann, A. Aures, W. Zwermann
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09034, 2017)
Fission Yield Covariances For Jeff: A Bayesian Monte Carlo Method
O. Leray, D. Rochman, M. Fleming, J-C. Sublet, A. Koning, A. Vasiliev, H. Ferroukhi
Proc. Nuclear Data 2016, Bruges, Belgium, September 11-16, 2016 (Epj Web of Conferences 146, 09023, 2017)
Full Core Loca Analysis For Bwr/6 - Methodology And First Results
C. Cozzo, A. Epiney, S. Canepa, H. Ferroukhi, O. Zerkak, G. Khvostov,V. Brankov, A. Gorzel
Topfuel 2016, Boise, Idaho, Usa, September 11-16, 2016
Comparison Of Fission Yield Perturbation Methodologies On Nuclide Composition For A Pwr Uo2 Fuel Assembly
O. Leray, L. Fiorito, D. Rochman, H. Ferroukhi, A. Pautz, A. Stankovskiy, G. Van Den Eynde
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Validation Of Simulate-3k Against Spert-Iii Ria Experiments With Quantification Of Nuclear Data Uncertainties
A. Dokhane, O. Leray, D. Rochman, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Solution Of The Beavrs Benchmark Using Casmo-5 / Simulate-5 Code Sequence
V. Bykov, A. Vasiliev, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
On Causality Analysis Of Nuclear Reactor Noise Using Partial Directed Coherence
D. Chionis, A. Dokhane, H. Ferroukhi, A. Pautz
Physor 2016, Sun Valley, Idaho, Usa, May 1-5, 2016
Comparative Study Of Casmo-5/Simulate-5 And Ntracer For Epr Core Analyses
S. Canepa, H. Ferroukhi, R. Min, H.G. Joo
Icapp 2016, San Francisco, Ca, Usa, April 17-20, 2016
Towards Analysis Of The Bowing Effect On Burnt Nuclear Fuel Compositions Using Serpent
J. Li, D. Rochman, J. Herrero, H. Ferroukhi, A. Vasiliev, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016
Extention Of Psi Fnf Modeling Methodology Validation Using Bwr Dosimetry Data
R. Savelli, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2016 Student Conference, University of Wisconsin, Madison, Usa, March 31-April 3, 2016
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
2014
Assessment Of Trace Against Single-Tube Post-Dryout Heat Transfer Experiments
Y. Aounallah
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Post-Test Analysis Of Oecd/Nea Rosa-2 Test 4 Using Trace
I. Clifford, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Uncertainty And Sensitivity Analysis Of Cobra-Tf For The Simulation Of Selected Oecd/Nrc Bfbt Void Experiments
A. Epiney, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Assessment Of Cfd Urans Models For Buoyancy Driven Mixing Flows Based On Rocom Experiments
R. Puragliesi, O. Zerkak And A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Treatment Of Epistemic And Aleatory Uncertainties In Det Simulations: Computational Framework With Ads-Trace
S. Rahman, D.R. Karanki, O. Zerkak, V.N. Dang
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Exploring Variability In Reflood Simulation Results: An Application Of Functional Data Analysis
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Sensitivity Analysis Of A Bottom Reflood Simulation Using The Morris Screening Method
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Analysis Of The Oecd/Nea Oskarshamn-2 Feedwater Transient And Stability Benchmark With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Uncertainty And Sensitivity Study Of Fuel Thermal Behaviour Within Oecd/Nea Uam Programme
Y. Yun, C. Cozzo, O. Leray, H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Nuss-Rf: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Stochastic Sampling-Based Tool For Nuclear Data Sensitivity Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Youth. Nucl. Congress Iync2014, Burgos, Spain, July 6-12, 2014
Uncertainty Quantification Of Spent Fuel Nuclide Compositions Due To Cross-Sections, Decay Constants And Fission Yields
O. Leray, P. Grimm, M. Hursin, H. Ferroukhi And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Quantification Of Code. Library And Cross-Section Uncertainty Effects On The Void Reactivity Coefficient Of A Bwr Uo2 Assembly
O. Leray, P. Grimm, H. Ferroukhi, And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Effects Of Advanced Radial Submeshing Methods On Pin Power Reconstruction For An Epr Core Design
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
New Psi Methodology For Manufacturing And Technological Uncertainty Quantification
M. Pecchia, A. Vasiliev, O. Leray, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Updated Validation Of The Psi Criticality Safety Evaluation Methodology Using Mcnpx2.7 And Endf/B-Vii.1
M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Validation Of Two Monte Carlo Codes For Lwr Burnup Calculations
D. Wicaksono, P. Grimm, A.Vasiliev, M. Hursin, G. Perret, And H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Analysis Of Axial Fuel Relocation Based On Gamma Scan Data From Oecd Halden Reactor Project Loca Tests
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Water Reactor Fuel Performance Meeting Wrfpm2014, Sendai, Japan, September 14-17, 2014
Fuel Relocation In Ifa-650 Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014
Reactivity Benchmark Analysis And Code Reactivity Prediction For A Pwr Fuel Assembly
H. Perrier, O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
Neutronic Data Generation For Bwr Models, Comparison Of Serpent And Casmo-5
L. Rossinelli, M. Hursin. H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
Validation Enhancements Of The Psi Fast Neutron Fluence Computational Scheme Using Operational Pwr Experimental Data
A. Dupre, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
Y. Aounallah
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Post-Test Analysis Of Oecd/Nea Rosa-2 Test 4 Using Trace
I. Clifford, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Uncertainty And Sensitivity Analysis Of Cobra-Tf For The Simulation Of Selected Oecd/Nrc Bfbt Void Experiments
A. Epiney, O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Assessment Of Cfd Urans Models For Buoyancy Driven Mixing Flows Based On Rocom Experiments
R. Puragliesi, O. Zerkak And A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Treatment Of Epistemic And Aleatory Uncertainties In Det Simulations: Computational Framework With Ads-Trace
S. Rahman, D.R. Karanki, O. Zerkak, V.N. Dang
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Exploring Variability In Reflood Simulation Results: An Application Of Functional Data Analysis
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Sensitivity Analysis Of A Bottom Reflood Simulation Using The Morris Screening Method
D. Wicaksono,O. Zerkak, A. Pautz
Proc. Int. Conf. Nucl. Thermal-Hydraulics Nuthos-10, Okinawa, Japan, December 14 - 18, 2014
Analysis Of The Oecd/Nea Oskarshamn-2 Feedwater Transient And Stability Benchmark With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Uncertainty And Sensitivity Study Of Fuel Thermal Behaviour Within Oecd/Nea Uam Programme
Y. Yun, C. Cozzo, O. Leray, H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Nuss-Rf: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Stochastic Sampling-Based Tool For Nuclear Data Sensitivity Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Youth. Nucl. Congress Iync2014, Burgos, Spain, July 6-12, 2014
Uncertainty Quantification Of Spent Fuel Nuclide Compositions Due To Cross-Sections, Decay Constants And Fission Yields
O. Leray, P. Grimm, M. Hursin, H. Ferroukhi And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Quantification Of Code. Library And Cross-Section Uncertainty Effects On The Void Reactivity Coefficient Of A Bwr Uo2 Assembly
O. Leray, P. Grimm, H. Ferroukhi, And A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Effects Of Advanced Radial Submeshing Methods On Pin Power Reconstruction For An Epr Core Design
P. Mala, S. Canepa, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
New Psi Methodology For Manufacturing And Technological Uncertainty Quantification
M. Pecchia, A. Vasiliev, O. Leray, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Updated Validation Of The Psi Criticality Safety Evaluation Methodology Using Mcnpx2.7 And Endf/B-Vii.1
M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Validation Of Two Monte Carlo Codes For Lwr Burnup Calculations
D. Wicaksono, P. Grimm, A.Vasiliev, M. Hursin, G. Perret, And H. Ferroukhi
Proc. Int. Conf. Reactor Physics, Physor2014, Kyoto, Japan, September 28 - October 3, 2014
Analysis Of Axial Fuel Relocation Based On Gamma Scan Data From Oecd Halden Reactor Project Loca Tests
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Water Reactor Fuel Performance Meeting Wrfpm2014, Sendai, Japan, September 14-17, 2014
Fuel Relocation In Ifa-650 Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A.Pautz
Proc. Enlarged Halden Project Group Meeting, Roeso, Norway, September 7-12, 2014
Reactivity Benchmark Analysis And Code Reactivity Prediction For A Pwr Fuel Assembly
H. Perrier, O. Leray, M. Pecchia, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
Neutronic Data Generation For Bwr Models, Comparison Of Serpent And Casmo-5
L. Rossinelli, M. Hursin. H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
Validation Enhancements Of The Psi Fast Neutron Fluence Computational Scheme Using Operational Pwr Experimental Data
A. Dupre, A. Vasiliev, H. Ferroukhi, A. Pautz
American Nuclear Society 2014 Student Conference, Psu, Pennsylvania, Usa, April 3-5, 2013
2013
Analysis Of A Halden Loca Test With The Bwr High Burnup Fuel
G. Khvotsov, A. Pautz, E. Kolstad, G. Ledergerber
Proc. Lwr Fuel Performance Meeting - **Top Fuel 2013, Charlotte, Usa, September 15-19, 2013
Investigation Of The Influence Of Off-Stoichiometry On The Radiation Damage Evolution In Uranium Dioxide
R. Ngayam-Happy, M. Krack
Proc. European Material Research Socitey Meeting E-Mrs 2013, Strasbourg, France, May 27-31, 2013
Thermal-Hydraulic System Code Performance For Sbloca Phenomonelogy Using Different Geometries And Scales
J. Freixa, S. Belaid, O. Zerkak
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Post-Analysis Of A Turbine Trip Test At A Bwr/6 Using The Trace/S3k Coupled Code
K. Nikitin, T. Gudmunsson, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Implementation And Validation Of A Condensation Heat Transfer Model For Slightly Inclined Horizontal Pipes For Relap5
R. Szijarto, J. Freixa, H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Simulation Of International Standard Problem Isp-42 Phase B Using In-House Coupled Code Gothic-Trace
C. Adamsson, D. Papini, O. Zerkak And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Simulation Of International Standard Problem Isp-42 Phase B Using The Containment Code Gothic
D. Papini, C. Adamsson, M. Andreani And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
On Bwr Regional Oscillations With Rotational Symmetry Line Using Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Application Of Power Time-Projection On The Operator Splitting Coupling Scheme Of The Trace/S3k Coupled Code
D. Wicaksono, O. Zerkak, K. Nikitin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Comparision Of Serpent And Casmo-5m For Pressurized Water Reactors Models
M. Hursin, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Preparation Of Nuclear Libraries With Deterministic And Stochastic Methods For Lwr Reflectors
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Convergence Studies Of Deterministic Methods For Lwr Explicit Reflector Methodology
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Comparison Of U.S Nrc Parcs Against Studsvik Simulate-3 Core Simulator For Modeling And Analysis Of Swiss Pwrs
S. Bogetic, M. Hursin, A. Dokhane, H. Ferroukhi, S. Canepa, A. Pautz
Proc. America Nuclear Society 2013 Student Conference, Mit, Boston, April 4-6, 2013
Study Of Nuclear Decay Data Contribution To Uncertainties In Heat Load Estimations For Spent Fuel Pools
H. Ferroukhi, O. Leray, M. Hursin, A. Vasiliev, G. Perret, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Nuclear Data Library E Ects On Fast To Thermal Flux Shapes Around Pwr Control Rod Tips
A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Application Of The Psi-Nuss Tool For The Estimation Of Nuclear Data Related K-Eff Uncertainties For The Oecd/Nea Wpncs Uacsa Phase I Benchmark
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Comparison Of Two Approaches For Nuclear Data Uncertainty Propagation In Mcnp(X) For Selected Fast Spectrum Critical Benchmarks
T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Multi-Scale Approach To Advanced Fuel Modelling For Enhanced Safety
F. Ribeiro, G. Khvostov
Proc. Eurosafe Meeting, Cologne, Germany, November 4-5, 2013 <
Deposition Of Inertial Drops In Eulerian Formulation
D. Caraghiaur, C. Adamsson, H. Anglart
Proc. Nureth-15, Pisa, Italy, May 12-17, 2013
G. Khvotsov, A. Pautz, E. Kolstad, G. Ledergerber
Proc. Lwr Fuel Performance Meeting - **Top Fuel 2013, Charlotte, Usa, September 15-19, 2013
Investigation Of The Influence Of Off-Stoichiometry On The Radiation Damage Evolution In Uranium Dioxide
R. Ngayam-Happy, M. Krack
Proc. European Material Research Socitey Meeting E-Mrs 2013, Strasbourg, France, May 27-31, 2013
Thermal-Hydraulic System Code Performance For Sbloca Phenomonelogy Using Different Geometries And Scales
J. Freixa, S. Belaid, O. Zerkak
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Post-Analysis Of A Turbine Trip Test At A Bwr/6 Using The Trace/S3k Coupled Code
K. Nikitin, T. Gudmunsson, S. Canepa, O. Zerkak, H. Ferroukhi, A. Pautz
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Implementation And Validation Of A Condensation Heat Transfer Model For Slightly Inclined Horizontal Pipes For Relap5
R. Szijarto, J. Freixa, H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Simulation Of International Standard Problem Isp-42 Phase B Using In-House Coupled Code Gothic-Trace
C. Adamsson, D. Papini, O. Zerkak And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
Simulation Of International Standard Problem Isp-42 Phase B Using The Containment Code Gothic
D. Papini, C. Adamsson, M. Andreani And H.M. Prasser
Proc. Nuclear Reactor Thermal-Hydraulics Nureth-15, Pisa, Italy, May 12-17, 2013
On Bwr Regional Oscillations With Rotational Symmetry Line Using Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Application Of Power Time-Projection On The Operator Splitting Coupling Scheme Of The Trace/S3k Coupled Code
D. Wicaksono, O. Zerkak, K. Nikitin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Comparision Of Serpent And Casmo-5m For Pressurized Water Reactors Models
M. Hursin, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Preparation Of Nuclear Libraries With Deterministic And Stochastic Methods For Lwr Reflectors
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Convergence Studies Of Deterministic Methods For Lwr Explicit Reflector Methodology
S. Canepa, M. Hursin, H. Ferroukhi, A. Pautz
Proc. Mathematics And Computations M&C 2013, Sun Valley, Usa, May 5-9, 2013
Comparison Of U.S Nrc Parcs Against Studsvik Simulate-3 Core Simulator For Modeling And Analysis Of Swiss Pwrs
S. Bogetic, M. Hursin, A. Dokhane, H. Ferroukhi, S. Canepa, A. Pautz
Proc. America Nuclear Society 2013 Student Conference, Mit, Boston, April 4-6, 2013
Study Of Nuclear Decay Data Contribution To Uncertainties In Heat Load Estimations For Spent Fuel Pools
H. Ferroukhi, O. Leray, M. Hursin, A. Vasiliev, G. Perret, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Nuclear Data Library E Ects On Fast To Thermal Flux Shapes Around Pwr Control Rod Tips
A. Vasiliev, H. Ferroukhi, T. Zhu, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Application Of The Psi-Nuss Tool For The Estimation Of Nuclear Data Related K-Eff Uncertainties For The Oecd/Nea Wpncs Uacsa Phase I Benchmark
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Comparison Of Two Approaches For Nuclear Data Uncertainty Propagation In Mcnp(X) For Selected Fast Spectrum Critical Benchmarks
T. Zhu, D. Rochman, A. Vasiliev, H. Ferroukhi, W. Wieselquist, A. Pautz
Proc. Nuclear Data Conference Nd2013, New York City, Usa, March 4-8, 2013
Multi-Scale Approach To Advanced Fuel Modelling For Enhanced Safety
F. Ribeiro, G. Khvostov
Proc. Eurosafe Meeting, Cologne, Germany, November 4-5, 2013 <
Deposition Of Inertial Drops In Eulerian Formulation
D. Caraghiaur, C. Adamsson, H. Anglart
Proc. Nureth-15, Pisa, Italy, May 12-17, 2013
