Conference Articles

 

 

 

 

 

2014

  • Aounallah Y
    Assessment of TRACE against single-tube post-dryout heat transfer experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Badreddine H, Sato Y, Niceno B
    Scale resolving simulation of dispersed bubbly flows
    In: Proceedings of the 2014 international congress on advances in nuclear power plants. Vol. 3. La Grange Park, IL, USA: American Nuclear Society; 2014:1623-1633. https://www.ans.org/store/item-700385/.
    DORA PSI
  • Clifford I, Zerkak O, Pautz A
    Post-test analysis of OECD/NEA ROSA-2 test 4 using TRACE
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Dokhane A, Ferroukhi H, Pautz A
    Analysis of the OECD/NEA Oskarshamn-2 feedwater transient and stability benchmark with simulate-3K
    In: Proceedings of the international conference on physics of reactors (PHYSOR 2014). PHYSOR 2014 – the role of reactor physics toward a sustainable future. ; 2014:1101708 (14 pp.).
    DORA PSI
  • Dupont J, Mignot G, Zboray R, Prasser H-MP
    Characterization and validation of the near infrared film thickness profile technique
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Epiney A, Zerkak O, Pautz A
    Uncertainty- and sensitivity analysis of COBRA-TF for the simulation of selected OECD/NRC BFBT void experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Grimm P, Perret G, Ferroukhi H
    CASMO-4E AND CASMO-5 analysis of the isotopic compositions of the LWR-PROTEUS phase II burnt PWR UO2 fuel samples
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Hursin M, Ferroukhi H, Pautz A
    Neutronic Data Generation for BWR Models, Comparison OF SERPENT and CASMO-5
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Hursin M, Scriven M, Perret G, Grimm P, Pautz A
    Pinpower uncertainty quantification of LWR-PROTEUS phase III experiments
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Hursin M, Siefman D, Rais A, Girardin G, Pautz A
    Verification of a reactor physics calculation scheme for the CROCUS reactor
    In: 3rd international technical meeting on small reactors. Vol. 1. Toronto, Canada: Canadian nuclear society; 2014. https://infoscience.epfl.ch/record/253153/files/ITSMR_2014.pdf.
    DORA PSI
  • Jaeckel B, Birchley J, Fernandez-Moguel L
    Spent fuel pool under severe accident conditions
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V003T06A029 (7 pp.). https://doi.org/10.1115/ICONE22-30729
    DORA PSI
  • Janssens KGF, Niffenegger M, Sharabi M
    Computational analyses of the thermal stress induced by coolant mixing in a T-joint
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V001T02A005 (9 pp.). https://doi.org/10.1115/ICONE22-30218
    DORA PSI
  • Karanki DR, Zerkak O, Dang VN
    Treatment of epistemic and aleatory uncertainties in DET simulations: computational framework with ADS-TRACE
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Leray O, Grimm P, Ferroukhi H, Pautz A
    Quantification of code, library and cross-section uncertainty effects on the void reactivity coefficient of a BWR UO2 assembly
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Leray O, Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    Reactivity benchmark Analysis and Code Reactivity Prediction for a PWR Fuel Assembly
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Leray O, Grimm P, Hursin M, Ferroukhi H, Pautz A
    Uncertainty quantification of spent fuel nuclide compositions due to cross sections, decay constants and fission yields
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Mala P, Canepa S, Ferroukhi H, Pautz A
    Effects of advanced radial submeshing methods on pin power reconstruction for an EPR core design
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Mukin R, Dehbi A
    Simulation of a gas jet in the secondary side of a steam generator bundle following a tube rupture sequence
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V004T10A018 (9 pp.). https://doi.org/10.1115/ICONE22-30517
    DORA PSI
  • Ngayam-Happy RA, Krack M
    Radiation damage characterization in non-stoichiometric uranium dioxide by molecular dynamics simulations
    In: Caruge D, Calvin C, Diop CM, Malvagi F, Trama J-C, eds. SNA + MC 2013 - joint international conference on supercomputing in nuclear applications + monte carlo. sine loco: EDP sciences; 2014:01301 (2 pp.). https://doi.org/10.1051/snamc/201401301
    DORA PSI
  • Paladino D, Mignot G, Kapulla R, Paranjape S, Andreani M, Studer E, et al.
    OECD/NEA HYMERES project: for the analysis and mitigation of a severe accident leading to hydrogen release into a nuclear plant containment
    In: International congress on advances in nuclear power plants (ICAPP 2014). Vol. 2. Illinois: American Nuclear Society (ANS); 2014:1314-1322.
    DORA PSI
  • Paranjape S, Mignot G, Paladino D
    Effect of thermal stratification on full cone spray performance in reactor containment for a scaled scenario
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V02BT09A020 (14 pp.). https://doi.org/10.1115/ICONE22-30755
    DORA PSI
  • Pecchia M, Vasiliev A, Ferroukhi H, Pautz A
    Updated validation of the PSI criticality safety evaluation methodology using MCNPX2.7 and ENDF/B-VII.1
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A
    Assessment of CFD uRANS models for buoyancy driven mixing flows based on ROCOM experiments
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Rais A, Siefman D, Girardin G, Hursin M, Pautz A
    PARCS few-group homogenized parameters generation using Serpent Monte Carlo code at the CROCUS reactor
    In: 16h meeting of the international group on research reactors. sine loco: IGORR; 2014:(11 pp.). https://www.igorr.com/Documents/2014-BARILOCHE/AdolfoRAIS-CROCUS.pdf.
    DORA PSI
  • Rydl A, Jaeckel B, Birchley JC, Lind T
    Long-term SBO with selected mitigative measures: MELCOR parametric calculations for a 2-loop PWR
    In: Proceedings of the 2014 22nd international conference on nuclear engineering (ICONE22). New York: American Society of Mechanical Engineers (ASME); 2014:V006T15A012 (10 pp.). https://doi.org/10.1115/ICONE22-30351
    DORA PSI
  • Vasiliev A, Ferroukhi H, Pautz A
    Validation Enhancements of the PSI Fast Neutron Fluence Computational Scheme using Operational PWR Experimental Data
    Presented at: ANS student conference 2014; April 3-6, 2014; University Park, PA, USA.
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Exploring variability in reflood simulation results: an application of functional data analysis
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Sensitivity analysis of a bottom reflood simulation using the Morris screening method
    Presented at: 10th international topical meeting on nuclear thermal-hydraulics, operation and safety (NUTHOS-10); December 14-18, 2014; Okinawa, Japan.
    DORA PSI
  • Wicaksono D, Grimm P, Vasiliev A, Hursin M, Perret G, Ferroukhi H
    Validation of two Monte Carlo codes for LWR burnup calculations
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI
  • Yun Y, Leray O, Ferroukhi H
    Uncertainty and sensitivity analysis of OECD/NEA UAM fuel thermal behaviour benchmark using a Falcon/URANIE methodology
    Presented at: International conference on physics of reactors (PHYSOR 2014); September 28-October 3, 2014; Kyoto, Japan.
    DORA PSI

Simulations And Measurements Of Adiabatic Annular Flows In A Triangular, Tigth Lattice Nuclear Fuel Bundle Model
A Saxena, R Zboray, H Prasser
Cfd4nrs-5: Proceedings Of The Oecd/Nea & Iaea Workshop On Computational Fluid Dynamics For Nuclear Safety Research, Eth Zuerich, Switzerland, Sep. 9-11, 2014 1, 10 (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

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

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


Large Eddy Simulations of Flow Inside a Cubical Differentially Heated Cavity under Realistic Boundary Conditions
A. Dehbi, F. Han, J. Kalilainen
5th CFD4NRS, Zürich, Switzerland

The hydrodynamics of two-phase flow in a tube bundle and a bare channel
T.T. Betschart, D.J. Suckow, V. Brankov, H.-M. Prasser
ICAPP, Charlotte, USA

Large Eddy Simulations of Flow inside a Cubical Differentially Heated Cavity under Realistic Boundary Conditions
A. Dehbi, F. Han, J. Kalilainen
ICAPP, Charlotte, USA

Remaining Issues in Pool Scrubbing: Major Drivers for Experimentation within the EU-PASSAM Project
L.E. Herranz, R.D. Tardáguila, T.T. Berschart, T.M. Lind, S. Morandi
ICAPP, Charlotte, USA

Assessment of RELAP5/TRACE against VEFITA Thermal-Hydraulic Level Swell Tests
J. Yang, D.J. Suckow, H.-M. Prasser, M. Furrer, T.M. Lind
ICAPP, Charlotte, USA

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Telephone: +41 56 310 40 62
E-mail: hakim.ferroukhi@psi.ch

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