Journal Publications 2015
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)
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)