Journal Publications

Development And Characterization Of A D–D Fast Neutron Generator For Imaging Applications
R Adams, L Bort, R Zboray, HM Prasser
Applied Radiation And Isotopes 96, 114 (2015).
http://dx.doi.org/10.1016/j.apradiso.2014.11.017

Erosion And Break-Up Of Light-Gas Layers By A Horizontal Jet In A Multi-Vessel, Large-Scale Containment Test System
R Zboray, G Mignot, R Kapulla, D Paladino
Nuclear Engineering And Design 291, 10 (2015).
http://dx.doi.org/10.1016/j.nucengdes.2015.05.006

Potential And Status In Imaging With Fast Neutrons
V Dangendorf, R Zboray
Neutron News 26, 27-30 (2015).
http://dx.doi.org/10.1080/10448632.2015.1028276

Simulations And Measurements Of Adiabatic Annular Flows In Triangular, Tight Lattice Nuclear Fuel Bundle Model
A Saxena, R Zboray, H Prasser
Nuclear Engineering And Design , (2015).
http://dx.doi.org/10.1016/j.nucengdes.2015.07.063

Time-Resolved Fast Neutron Radiography Of Air-Water Two-Phase Flows
R Zboray, V Dangendorf, I Mor, B Bromberger, K Tittelmeier, H-M Prasser
Physics Procedia 69, 551 (2015).
http://dx.doi.org/10.1016/j.phpro.2015.07.078

Time-Resolved Fast-Neutron Radiography Of Air-Water Two-Phase Flows In A Rectangular Channel By An Improved Detection System
R Zboray, V Dangendorf, I Mor, B Bromberger, K Tittelmeier
Review Of Scientific Instruments 86, 075103 (2015).
http://dx.doi.org/10.1063/1.4926999

Two-Dimensional Mapping Of Falling Water Film Thickness With Near-Infrared Attenuation
J Dupont, G Mignot, HM Prasser
Experiments In Fluids 56, 90 (2015).
http://dx.doi.org/10.1007/s00348-015-1955-1

A Dynamic Event Tree Informed Approach To Probabilistic Accident Sequence Modeling: Dynamics And Variabilities In Medium Loca
D.R. Karanki, T-W. Kim, V.N. Dang
Reliability Engineering And System Safety, Vol. 142, Pp. 78 91 (2015)
http://dx.doi.org/10.1016/j.ress.2015.04.011

Improving Neutronics Simulations And Uncertainties Via A Selection Of Nuclear Data
D. Rochman, A.J. Koning, S.C. Van Der Marck
European Physical Journal A, Vol. 51 (2015)


On The Use Of Integral Experiments For Uncertainty Reduction Of Reactor Macroscopic Parameters Within The Tmc Methodology
E. Alhassan, H. Sjoestrand, P. Helgesson, M. Oesterlund, S. Pomp, A.J. Koning, D. Rochman
Progress in Nuclear Energy Vol.88, Pp. 43-52 (2016)


Application Of Mcnp For Predicting Power Excursion During Loca In Atucha-2 Phwr
M. Pecchia, C.Parisi, F. D’Auria, O. Mazzantini
Annals of Nuclear Energy, Vol. 85, Pp. 271 278 (2015)


Effects Of Stoichiometry On The Defect Clustering In Uranium Dioxide
R. Ngayam-Happy, M. Krack, A. Pautz
Journal of Physics: Condensed Matter, Vol. 27, 455401(2015)


Gen-Foam: A Novel Openfoam Based Multi-Physics Solver For2d/3d Transient Analysis Of Nuclear Reactors
C. Fiorina, I. Clifford, M. Aufiero, K. Mikityuk
Nuclear Engineering And Design, Vol. 294, Pp. 24-37, (2015)


Review Calculations For The Oecd/Nea Burn-Up Credit Criticality Safety Benchmark
J.J. Herrero, A.Vasiliev, M. Pecchia, H.Ferroukhi, S. Caruso
Annals of Nuclear Energy, Vol. 87, Pp. 48-57, (2016)


Towards Modeling And Validation Enhancements Of The Psi Mcnpx Fast Neutron Fluence Computational Scheme Based On Recent Pwr Experimental Data
A. Dupré, A. Vasiliev, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 85, Pp. 820 829, (2015)


Multi-Scale Approach To Advanced Fuel Modelling For Enhanced Safety
F. Ribeiro,G.Khvostov
Progress in Nuclear Energy, Vol. 84, Pp. 24-35, (2015)


On The Ground State Electronic Structure Of Uranium Dioxide
M. Krack
Physica Scripta, Vol. 90, 094014 (2015)


Linking Atomic And Mesoscopic Scales For The Modelling Of The Transport Properties Of Uranium Dioxide Under Irradiation
M. Bertolus, M. Freyss, B. Dorado, G. Martin, K. Hoang, S. Maillard, R.Skorek, P. Garcia, C. Valot, A. Chartier,L. Van Brutzel, P. Fossati, R. W. Grimes, D. C. Parfitt, C. L. Bishop, S. T. Murphy, M. J.D. Rushton, D. Staicu, E. Yakub, S. Nichenko, M. Krack, F. Devynck, R. Ngayam-Happy, K. Govers, C.S. Deo, R. K. Behera
Journal of Nuclear Materials Vol. 462, Pp. 475-495 (2015)


Boron Dilution Transient Simulation Analyses In A Pwr With Neutronics/Thermal-Hydraulics Coupled Codes In The Nurisp Project
G. Jimenez, J.J. Herrero, A. Gommlich, S. Kliem, D. Cuervo, J. Jimenez
Annals of Nuclear Energy Vol. 84, Pp. 86-97 (2015)


Review Of Multi-Physics Temporal Coupling Methods For Analysis Of Nuclear Reactors
O. Zerkak, T. Kozlowski, I. Gajev
Annals of Nuclear Energy Vol. 84, Pp. 225-233 (2015)


Nuss-Rf: Stochastic Sampling-Based Tool For Nuclear Data Sensitivity And Uncertainty Quantification
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz, S. Tarantola
Journal of Nuclear Science And Technology, Vol. 52:7-8, Pp. 1000-1007, (2015)


Criticality Safety Evaluation Of A Swiss Wet Storage Pool Using A Global Uncertainty Analysis Methodology
M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Annals of Nuclear Energy Vol. 83, Pp. 226-235 (2015)


Advanced Calculation Methodology For Manufacturing And Technological Parameters’ Uncertainties Propagation At Arbitrary Level Of Lattice Elements Grouping
M. Pecchia, A.Vasiliev, O.Leray, H.Ferroukhi, A.Pautz
Journal of Nuclear Science And Technology, Vol. 52:7-8, Pp. 1084-1092, (2015)


Modelling Guidelines For Core Exit Temperature Simulations With System Codes
J. Freixa V. MartíNez-Quiroga, O. Zerkak, F. ReventóS
Nuclear Engineering and Design, Vol. 286, Pp. 116-129 (2015)


Nuss: A Tool For Propagating Multigroup Nuclear Data Covariances In Pointwise Ace-Formatted Nuclear Data Using Stochastic Sampling Method
T. Zhu, A. Vasiliev, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 75, Pp. 713-722 (2015)


RANS modeling for particle transport and deposition in turbulent duct flows: Near wall model uncertainties
S.T. Jayaraju, P. Sathiah, F. Roelofs, A. Dehbi
Nuclear Engineering and Design 289, 60
http://dx.doi.org/10.1016/j.nucengdes.2015.04.011

Analysis of the accident in the Fukushima Daiichi nuclear power station Unit 3 with MELCOR_2.1
L. Fernandez-Moguel, J.C. Birchley
Annals of Nuclear Energy 83, 193
http://dx.doi.org/10.1016/j.anucene.2015.04.021

Comparative assesment of PSI Air oxidation model implementation in SCDAPSim 3.5, MELCOR 1.8.6 and MELCOR 2.1
L. Fernandez-Moguel
Annals of Nuclear Energy 81, 134
http://dx.doi.org/10.1016/j.anucene.2015.03.015

A generalized correlation for steam condensation rates in the presence of air under turbulent free convection
A. Dehbi
International Journal of Heat and Mass Transfer 86, 1
http://dx.doi.org/10.1016/j.ijheatmasstransfer.2015.02.034

Status of the spent fuel in the reactor buildings of Fukushima Daiichi 1-4
B.S. Jäckel
Nuclear Engineering and Design 283, 2
http://dx.doi.org/10.1016/j.nucengdes.2014.07.007