Conference Articles

 

 

 

 

 

2016

  • Albiol T, Herranz L, Riera E, Dalibart C, Lind T, Del Corno A, et al.
    Preliminary insights from the PASSAM project: investigation on enhancement of source term mitigation
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P0580 (14 pp.).
    DORA PSI
  • Andreani M, Daqiang Y, Gaikwad AJ, Ganju S, Gera B, Grigoryev S, et al.
    Synthesis of a blind CFD benchmark exercise based on a test in the PANDA facility addressing the stratification erosion by a vertical jet in presence of a flow obstruction
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(13 pp.).
    DORA PSI
  • Aounallah Y
    Simulations of level-swell experiments with TRACE
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Bocharov D, Krack M, Kalinko A, Purans J, Rocca F, Ali SE, et al.
    Ab initio molecular dynamics simulations of the Sc K-edge EXAFS of scandium trifluoride
    In: Grunwaldt J-D, Hagelstein M, Rothe J, eds. 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:012009 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012009
    DORA PSI
  • Bocharov D, Chollet M, Krack M, Bertsch J, Grolimund D, Martin M, et al.
    Interpretation of the U L3-edge EXAFS in uranium dioxide using molecular dynamics and density functional theory simulations
    In: 16th international conference on X-ray absorption fine structure (XAFS16). Vol. 712. Journal of physics: conference series. Bristol, Philadelphia: IOP Publishing; 2016:12091 (4 pp.). https://doi.org/10.1088/1742-6596/712/1/012091
    DORA PSI
  • Bykov V, Vasiliev A, Ferroukhi H, Pautz A
    Solution of the BEAVRS benchmark using CASMO-5 / SIMULATE-5 code sequence
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1960-1968.
    DORA PSI
  • Canepa S, Ferroukhi H, Min R, Joo HG
    Comparative study of CASMO-5/simulate-5 and nTRACER for EPR core analyses
    In: International congress on advances in nuclear power plants, ICAPP 2016. Vol. 2. American Nuclear Society; 2016:1436-1445.
    DORA PSI
  • Chionis D, Dokhane A, Ferroukhi H, Pautz A
    On causality analysis of nuclear reactor noise using partial directed coherence
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1162-1171.
    DORA PSI
  • Clifford I, Zerkak O, Pautz A, Yao H, Freixa J
    System code validation series based on a consistent plant nodalisation of the ROSA/LSTF integral test facility using TRACE v5.0 Patch 4
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Cozzo C, Epiney A, Canepa S, Ferroukhi H, Zerkak O, Khvostov G, et al.
    Full core LOCA analysis for BWR/6 - methodology and first results
    In: Top Fuel 2016. LWR fuels with enhanced safety and performance. LaGrange Park, IL, USA: American Nuclear Society; 2016:1135-1144.
    DORA PSI
  • Dehbi A, Han F, Kalilainen J
    Large Eddy Simulations of flow inside a cubical differentially heated cavity under realistic boundary conditions
    In: Computational fluid dynamics for nuclear reactor safety-5 (CFD4NRS-5). Workshop proceedings. Paris: OECD; 2016:(13 pp.).
    DORA PSI
  • Dehbi A, Kalilainen J
    Large Eddy Simulations of free convection particle transport inside cavities at Rayleigh numbers up to 1010
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(16 pp.).
    DORA PSI
  • Dokhane A, Leray O, Rochman D, Ferroukhi H, Pautz A, Grandi G
    Validation of SIMULATE-3K against SPERT-III RIA experiments with quantification of nuclear data uncertainties
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:3803-3812.
    DORA PSI
  • Grimm P, Hursin M, Perret G, Siefman D, Ferroukhi H
    CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-proteus PHASE II
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:2518-2527.
    DORA PSI
  • Halouane Y, Dehbi A
    Comparison of hydrogen flame acceleration predictions using the Eddy-Dissipation and the Turbulent Flame Closure
    In: Computational fluid dynamics for nuclear reactor safety applications-6 (CFD4NRS-6). Workshop proceedings. Paris: OECD; NEA; 2016:(15 pp.).
    DORA PSI
  • Hursin M, Siefman D, Perret G, Grimm P, Pautz A
    Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:674-683.
    DORA PSI
  • Jacquemain D, Albiol T, Dickinson S, Herranz L-E, Funke F, Glowa G, et al.
    Conclusion of the international OECD/NEA-NUGENIA iodine workshop
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11PA0625 (20 pp.).
    DORA PSI
  • Kalilainen J, Prasser H-M, Lind T, Krepel J, Schenler W
    Recent research activities on high temperature pebble bed reactors at PSI
    In: 2016 international topical meeting on high temperature reactor technology (HTR 2016). Illinois: American Nuclear Society; 2016:135-140.
    DORA PSI
  • Krepel J, Mikityuk K, Pautz A
    The EQL0D procedure for fuel cycle studies in molten salt reactor
    In: 2016 International Congress on Advances in Nuclear Power Plants, ICAPP 2016. ; 2016.
    DORA PSI
  • Lamirand V, Hursin M, Frajtag P, Pautz A, Perret G, Pakari O
    Future experimental programmes in the CROCUS reactor
    In: Conference proceedings. Berlin, Germany. 13-17 March 2016. European research reactor conference 2016. Bruessels, Belgium: European Nuclear Society; 2016:284-291.
    DORA PSI
  • Leray O, Fiorito L, Rochman D, Ferroukhi H, Pautz A, Stankovskiy A, et al.
    Comparison of fission yield perturbation methodologies on nuclide composition for a PWR UO2 fuel assembly
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. LaGrange Park, IL, USA: American Nuclear Society; 2016:1669-1680.
    DORA PSI
  • Li J, Rochman D, Herrero J, Ferrouki H, Vasiliev A, Pautz A
    Towards analysis of the bowing effect on burnt nuclear fuel compositions using SERPENT
    Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
    DORA PSI
  • Lind T, Beghi I, Opilik L, Suckow D
    The effect of thermal-hydraulic conditions on iodine retention in a wet scrubber of the FCVS
    In: Proceedings of the 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11). La Grange Park: American Nuclear Society; 2016:N11P1234 (12 pp.).
    DORA PSI
  • Mignot G, Dupont J, Paladino D, Prasser H-M
    Containment thermal-hydraulic experiment and potential for severe accident studies in the LINX facility
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Mukin R, Zerkak O, Pautz A
    Modeling and analysis of selected OECD PKL3 Station-Blackout experiments using TRACE
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Mukin R, Dehbi A
    Simulation of flow on the secondary side of a steam generator bundle
    In: Computational fluid dynamics for nuclear reactor safety-5. (CFD4NRS-5). Workshop proceedings. Paris, France: OECD; 2016. https://www.oecd-nea.org/nsd/csni/cfd/.
    DORA PSI
  • Mullyadzhanov R, Palkin E, Nićeno B, Vervisch L, Hanjalić K
    Verification of a low Mach variable-density Navier-Stokes solver for turbulent combustion
    In: All-Russian conference with the school for young scientists thermophysics and physical hydrodynamics, 2016. Vol. 754. Journal of physics: conference series. IOP Publishing; 2016:062005 (11 pp.). https://doi.org/10.1088/1742-6596/754/6/062005
    DORA PSI
  • Paranjape S, Kapulla R, Mignot G, Paladino D
    Erosion of a helium layer due to the flow resulting from the interaction of a steam jet with a flow obstruction in a large vessel
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Perret G
    Delayed neutron fraction and prompt decay constant measurement in the Minerve reactor using the PSI instrumentation
    In: 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). 2015 4th international conference on advancements in nuclear instrumentation measurement methods and their applications (ANIMMA). Danvers: IEEE; 2016:8 pp. https://doi.org/10.1109/ANIMMA.2015.7465533
    DORA PSI
  • Perret G, Vlassopoulos E, Hursin M, Pautz A
    Toward reanalysis of the tight-pitch HCLWR-PROTEUS Phase II experiments
    In: Serot O, ed. Wonder-2015 – 4th international workshop on nuclear data evaluation for reactor applications. Vol. 111. EPJ web of conferences. Les Ulis Cedex A, France: EDP Sciences; 2016:11006 (9 pp.). https://doi.org/10.1051/epjconf/201611111006
    DORA PSI
  • Puragliesi R, Zerkak O, Pautz A
    Influence of URANS turbulence models on in-vessel flow mixing during cold leg accumulator injection
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Qian G, Niffenegger M, Sharabi M, Lafferty N
    Deterministic and probabilistic PTS study for a reactor pressure vessel considering plume cooling effects
    In: Materials and fabrication. Vol. 6A-2016. Conference proceedings. Pressure vessels and piping conference. sine loco: ASME; 2016:PVP2016-63869 (12 pp.). https://doi.org/10.1115/PVP2016-63869
    DORA PSI
  • Rahman S, Karanki DR, Wicaksono D, Zerkak O, Dang VN
    Evaluation of deterministic sampling for uncertainty quantification in a probabilistic accident analysis model
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Rais A, Hursin M, Perret G, Pautz A
    Experimental validation of control rod reactivity worth and fission rate distributions for the CROCUS Reactor
    In: Physics of reactors 2016 (PHYSOR 2016). Unifying theory and experiments in the 21st century. Vol. 6. LaGrange Park, IL, USA: American Nuclear Society; 2016:3874-3883.
    DORA PSI
  • Rýdl A, Fernandez-Moguel L, Lind T
    Impact of containment venting on source term for Fukushima-like BWR scenarios
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI
  • Sato Y, Niceno B
    Pool boiling simulation of water up to critical heat flux using an interface tracking method
    In: NUTHOS-11: proceedings of the 11th international topical meeting on nuclear reactor thermal-hydraulics, operations and safety. La Grange Park, IL, USA: American Nuclear Society; 2016.
    DORA PSI
  • Savelli R, Vasiliev A, Ferroukhi H, Pautz A
    Extention of PSI FNF modeling methodology validation using BWR dosimetry data
    Presented at: American Nuclear Society 2016 student conference; March 31 - April 3, 2016; University of Wisconsin, Madison, USA.
    DORA PSI
  • Sublet JC, Koning AJ, Rochman D, Fleming M, Gilbert M
    TENDL-2015: Delivering both completeness and robustness
    In: Advances in nuclear nonproliferation technology and policy conference (ANTPC 2016). Advances in nuclear nonproliferation technology and policy conference: bridging the gaps in nuclear nonproliferation, ANTPC 2016. American Nuclear Society; 2016:(4 pp.).
    DORA PSI
  • Wicaksono D, Zerkak O, Pautz A
    Bayesian calibration of thermal-hydraulics model with time-dependent output
    Presented at: 11th international topical meeting on nuclear reactor thermal hydraulics, operation and safety (NUTHOS-11); October 9-13, 2016; Gyeongju, Korea.
    DORA PSI


Erosion Of A Helium Layer Due To The Flow Resulting From The Interaction Of A Steam Jet With A Flow Obstruction In A Large Vessel
Sidharth Paranjape, Ralf Kapulla, Guillaume Mignot, Domenico Paladino
Nuthos-11: Proceedings Of The 11th International Topical Meeting On Nuclear Reactor Thermal-Hydraulics, Operation And Safety (Oct 9-13, 2016, Gyeongju, Korea) N11a0514, 1 (2016).


Scaling And Cfd Modelling Of The Pool Experiments With Spargers Performed In The Panda Facility
Ignacio Gallego-Marcos, Walter Villanueva, Pavel Kudinov, Ralf Kapulla, Sidharth Paranjape, Domenico Paladino
Nuthos-11: Proceedings Of The 11th International Topical Meeting On Nuclear Reactor Thermal-Hydraulics, Operation And Safety (Oct 9-13, 2016, Gyeongju, Korea) Nuthos-11, 1 (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

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)

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

The effect of thermal-hydraulic conditions on iodine retention in a wet scrubber of the FCVS
T.M. Lind, I. Beghi, L. Opilik, D.J. Suckow
11th NUTHOS, Gyeongju, Korea


Thermal-hydraulic evaluation of the system code TRACE/PARCS using different sets of cross-sections
P. Papadopoulos, A. Sehkri, P. Hidalga, G. Verdu
11th NUTHOS, Gyeongju, Korea

Preliminary insights from the PASSAM project: investigation on enhancement of source term mitigation
T. Albiol, L.-E. Herranz, E. Riera, C. Dalibart, T.M. Lind, A. del Corno, T. Kärkelä, N. Losch, B. Azambre
11th NUTHOS, Gyeongju, Korea


Conclusion of the International OECD/NEA-NUGENIA Iodine workshop
D. Jacquemain, T. Albiol, S. Dickinson, L.-E. Herranz, F. Funke, G. Glowa, S. Gupta, H. Hoshi, T. Kärkelä, M. Kissane, T.M. Lind, M. Salay, J.-H. Song, J.-P. van Dorsselaere
11th NUTHOS, Gyeongju, Korea

Comparison of Hydrogen Flame Acceleration Predictions using the Eddy-Dissipation and the Turbulent Flame Closure
Y. Halouane, A. Dehbi
6th CFD4NRS, Boston, USA

Large Eddy Simulation of Free Convection Particle Transport Inside Cavities at Rayleigh Numbers up to 1010
A. Dehbi, J. Kalilainen
6th CFD4NRS, Boston, USA

Determination of the Decontamination Factor in Two-Phase Flows using Wire-Mesh Sensors
P. Papadopoulos, K. Baur, T.M. Lind, H.-M. Prasser
SWINTH, Livorno, Italy