Conference Publications of the STARS Program

2020

Bernal A, Pecchia M, Rochman D, Vasiliev A, Ferroukhi H
Methodology for high-fidelity deterministic modelling of Swiss LWR fuel assemblies
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1197 (8 pp.).
DORA PSI
Hursin M, Rochman D, Vasiliev A, Ferroukhi H, Pautz A
Impact of various source of covariance information on integral parameters uncertainty during depletion calculations with CASMO-5
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1172 (10 pp.).
DORA PSI
Hursin M, Pakari O, Perret G, Frajtag P, Lamirand V, Pázsit I, et al.
Validation of axial void profile measured by neutron noise techniques in CROCUS
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1173 (8 pp.).
DORA PSI
Lamirand V, Rais A, Pakari O, Hursin M, Laureau A, Polhus J, et al.
Analysis of the first COLIBRI fuel rods oscillation campaign in the CROCUS reactor for the European project CORTEX
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1573 (9 pp.).
DORA PSI
Mala P, Pautz A, Ferroukhi H, Vasiliev A
Development of 3D pin-by-pin core solver tortin and coupling with thermal-hydraulics
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1583 (8 pp.).
DORA PSI
Mylonakis AG, Demazière C, Vinai P, Lamirand V, Rais A, Pakari O, et al.
CORE SIM+ simulations of COLIBRI fuel rods oscillation experiments and comparison with measurements
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1207 (9 pp.).
DORA PSI
Papadionysiou M, Kim S, Hursin M, Vasiliev A, Ferroukhi H, Pautz A, et al.
Coupling of nTRACER to COBRA-TF for high-fidelity analysis of VVERs
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1285 (8 pp.).
DORA PSI
Perret G, Rochman D, Vasiliev A, Ferroukhi H
Neutron emission measurements of PWR spent fuel segments and preliminary validation of depletion calculations
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1174 (10 pp.).
DORA PSI
Pázsit I, Hursin M, Nylén H, Dykin V
Reconstructing the axial void velocity profile in BWRs from measurements of the in-core neutron noise
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1337 (8 pp.).
DORA PSI
Vasiliev A, Pecchia M, Rochman D, Ferroukhi H
Enhancement of validation studies for reactor dosimetry and ativation predictions with the nuclear data sampling methodology
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1427 (8 pp.).
DORA PSI
Verma V, Chionis D, Dokhane A, Ferroukhi H
Modelling and analysis of fuel assembly vibrational modes in PWRs using SIMULATE-3K
In: Proceedings of the PHYSOR 2020. Cambridge: Nuclear Energy Group; 2020:1270 (8 pp.).
DORA PSI

2019

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; 2019:117-122. 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; 2019:169-173. https://doi.org/10.1007/978-3-030-22204-8_18
DORA PSI
Barbagallo M, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Bécares V, et al.
(n,cp) reactions study at the n_TOF facility at CERN: results for the cosmological lithium problem
In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:259-264.
DORA PSI
Chionis D, Dokhane A, Ferroukhi H, Pautz A
Spatial localization of perturbation propagation in LWRs using causality and connectivity analysis
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). LaGrange Park, USA: American Nuclear Society (ANS); 2019:1960-1969.
DORA PSI
Clifford I, Cozzo C, Ferroukhi H
First assessments of the dynamic gap conductance model in TRACE
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:4624-4636.
DORA PSI
Cozzo C, Ngayam-Happy R, Chen J-C, Pecchia M, Girardin G
Modeling of the U₃Si₂/SiC fuel system behavior for a RIA scenario
In: Global/top fuel 2019. LaGrange Park, IL, USA: American Nuclear Society (ANS); 2019:643-647.
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; 2019:03003 (5 pp.). 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; 2019:03002 (5 pp.). https://doi.org/10.1051/epjconf/201921103002
DORA PSI
Mala P, Pautz A, Ferroukhi H
EPR fuel cycle depletion with pin-by-pin code tortin and nodal code SIMULATE5
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:1640-1649.
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; 2019:63-70. https://doi.org/10.1007/978-3-030-13876-9_11
DORA PSI
Mora DF, Mukin R, Costa Garrido O, Niffenegger M
Fracture mechanics analysis of a PWR under PTS using XFEM and input from TRACE
In: Materials and fabrication: advanced and additive manufacturing and material technologies. Vol. 6A. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94019 (7 pp.). https://doi.org/10.1115/PVP2019-94019
DORA PSI
Mukin R, Clifford I, Costa Garrido O, Mora DF, Niffenegger M, Niceno B, et al.
Screening analysis for pressurized thermal shock (PTS) transient scenarios
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). La Grange Park, USA: American Nuclear Society (ANS); 2019:2536-2549.
DORA PSI
Niffenegger M, Garrido OC, Mora DF, Qian G, Mukin R, Sharabi M, et al.
Uncertainties in pressurized thermal shock analyses
In: Design and analysis: 4th international symposium on coke drum life cycle management. Vol. 3. PVP - American Society of Mechanical Engineers. Pressure vessels and piping division. sine loco: American Society of Mechanical Engineers (ASME); 2019:PVP2019-94076 (10 pp.). https://doi.org/10.1115/PVP2019-94076
DORA PSI
Nikitin K, Clifford I, Ferroukhi H
PMSYS: plant management system as a part of Swiss Simulation Platform
In: 18th international topical meeting on nuclear reactor thermal hydraulics (NURETH-18). LaGrange Park, USA: American Nuclear Society (ANS); 2019:2943-2954.
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
In: International conference on mathematics and computational methods applied to nuclear science and engineering (M&C 2019). La Grange Park, USA: American Nuclear Society; 2019:700-709.
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); 2019:2209-2222.
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); 2019:2638-2647.
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); 2019:47-55.
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); 2019:1174-1183.
DORA PSI
Siefman D, Hursin M, Pautz A
Data assimilation of post irradiation examination experiments to adjust fission yields
In: ND 2019: international conference on nuclear data for science and technology. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2019:(5 pp.).
DORA PSI
Tagliente G, Aberle O, Alcayne V, Andrzejewski J, Audouin L, Babiano-Suarez V, et al.
Nuclear astrophysics at n_TOF facility, CERN
In: Cerutti F, Ferrari A, Kawano T, Salvat-Pujol F, Talou P, eds. Proceedings of the 15th international conference on nuclear reaction mechanisms. Geneva: CERN; 2019:251-258.
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; 2019:03006 (9 pp.). 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); 2019:1124-1133.
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

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; 2018:03004 (5 pp.). 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; 2018:1001-1012.
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; 2018:1013-1024.
DORA PSI
Cozzo C, Khvostov G
ATF developments in FALCON V1 at PSI
In: Topfuel 2018. Part 4. Brussels: European Nuclear Society; 2018:A0112 (9 pp.).
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; 2018:120-127. 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); 2018:91-102.
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:(10 pp.).
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:(12 pp.).
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; 2018:1-14. 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:(11 pp.).
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:ICONE26-81749 (7 pp.). 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:ICONE26-82546 (11 pp.). 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, Braun L, Frajtag P, Pautz A
Current mode neutron noise measurements in the zero power reactor CROCUS
In: Lyoussi A, Carette M, Giot M, Le Dû P, Reynard-Carette C, Schyns M, et al., eds. ANIMMA 2017 - advancements in nuclear instrumentation measurement methods and their applications. Vol. 170. EPJ web of conferences. Les Ulis Cedex A: EDP Sciences; 2018:04017 (5 pp.). https://doi.org/10.1051/epjconf/201817004017
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:(12 pp.).
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:ICONE26-81743 (13 pp.). 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:ICONE26-82381 (10 pp.). 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:(10 pp.).
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:(7 pp.).
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; 2018:524-531. 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

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

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

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

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