Journal Publications 2016
Exploring Stochastic Sampling In Nuclear Data Uncertainties Assessment For Reactor Physics Applications And Validation Studies
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Energies 2016, 9, 1039 (2016)
http://dx.doi.org/10.3390/en9121039
Analysis Of Selected Halden Overpressure Tests Using The Falcon Code
G. Khvostov, W. Wiesenack
Nuclear Engineering And Design, Vol. 310, Pp. 395-409,(2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.10.033
Towards A Consolidated Approach For The Assessment Of Evaluation Models Of Nuclear Power Reactors
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Nuclear Technology, Vol.196, Pp. 223-237, (2016)
http://dx.doi.org/10.13182/NT16-47
Validation Of Monte Carlo Based Burnup Codes Against Lwr-Proteus Phase-Ii Experimental Data
M. Pecchia, D. Wicaksono, P. Grimm, A. Vasiliev, G. Perret, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 97, Pp. 153-164, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.07.001
Validation Studies And Interpretation Of The Oskarshamn-2 1999 Stability Event With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 96, Pp. 344-353, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.06.016
Testing The Sampling-Based Nuss-Rf Tool For The Nuclear Data Related Global Sensitivity Analysis With Monte Carlo Neutronics Calculations
T. Zhu, A. Vasiliev, H. Ferroukhi, D. Rochman, A. Pautz
Nuclear Science And Engineering, Vol. 184, (2016)
http://dx.doi.org/10.13182/NSE14-142
Analysis Of Effects Of Pellet-Cladding Bonding On Trapping Of The Released Fission Gases In High Burnup Kkl Bwr Fuels
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Nuclear Engineering And Design, Vol. 305, Pp. 559-568, (2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.06.021
Selecting Benchmarks For Reactor Simulations: An Application To A Lead Fast Reactor
E. Alhassan, H. SjöStrand, P. Helgesson, M. ÖSterlund, S. Pomp, A.J. Koning, D. Rochman
Annals of Nuclear Energy, Vol. 96, Pp. 158-169, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.033
A Bayesian Monte Carlo Method For Fission Yield Covariance Information
D. Rochman, O. Leray, A. Vasiliev, H. Ferroukhi, A.J. Koning, M. Fleming, J.C. Sublet
Annals of Nuclear Energy, Vol. 95, Pp. 125-134, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.005
Re-Evaluation Of The Thermal Neutron Capture Cross Section Of 147nd
D. Rochman, O. Leray, G. Perret, A. Vasiliev, H. Ferroukhi, A.J. Koning
Annals of Nuclear Energy, Vol. 94, Pp. 612-617, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.024
Nuclear Data Uncertainty Propagation On Spent Fuel Nuclide Compositions
O. Leray, D. Rochman, P. Grimm, H. Ferroukhi, A. Vasiliev, M. Hursin, G. Perret, A. Pautz
Annals of Nuclear Energy, Vol. 94, Pp. 603-611, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.023
Sampling Of Systematic Errors To Estimate Likelihood Weights In Nuclear Data Uncertainty Propagation
P. Helgesson, H. SjöStrand, A.J. Koning, J. RydéN, D. Rochman , E. Alhassan, S. Pomp
Nuclear Instruments And Methods in Physics Research A807, Pp. 137 149, (2016)
http://dx.doi.org/10.1016/j.nima.2015.10.024
Characterization Of The Relocated And Dispersed Fuel In The Halden Reactor Project Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, W. Wiesenack
Nuclear Engineering And Design, Vol. 300, Pp. 97 106 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.11.023
210po Poisoning As Possible Cause Of Death: Forensic Investigations And Toxicological Analysis Of The Remains Of Yasser Arafat
P. Froidevaux, F. Bochud, S. Baechler, V. Castella, M. Augsburger, C. Bailat, K. Michaud, M. Straub, M. Pecchia, T-M. Jenk, T. Uldin, P. Mangin
Forensic Science International, Vol. 259 Pp. 1-9 , (2016)
http://dx.doi.org/10.1016/j.forsciint.2015.09.019
Steady-State Cfd Simulations Of An Eprtm Reactor Pressure Vessel: A Validation Study Based On The Juliette Experiments
R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Nuclear Engineering And Design, Vol. 300, Pp. 41 56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025
Localized Neutron Flux Assessment And Verification Studies Using Mcnpx Pwr Full Core Model
A. Vasiliev, H. Ferroukhi, M. Pecchia, A. Pautz
Annals of Nuclear Energy, Vol. 92, Pp. 317-332 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.026
Nuclear Data Uncertainty For Criticality-Safety: Monte Carlo Vs. Linear Perturbation
D. Rochman, A. Vasiliev, H. Ferroukhi, T. Zhu, S.C. Van Der Marck, A.J. Koning
Annals of Nuclear Energy, Vol. 92, Pp. 150-160 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.042
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Energies 2016, 9, 1039 (2016)
http://dx.doi.org/10.3390/en9121039
Analysis Of Selected Halden Overpressure Tests Using The Falcon Code
G. Khvostov, W. Wiesenack
Nuclear Engineering And Design, Vol. 310, Pp. 395-409,(2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.10.033
Towards A Consolidated Approach For The Assessment Of Evaluation Models Of Nuclear Power Reactors
A. Epiney, S. Canepa, O. Zerkak, H. Ferroukhi
Nuclear Technology, Vol.196, Pp. 223-237, (2016)
http://dx.doi.org/10.13182/NT16-47
Validation Of Monte Carlo Based Burnup Codes Against Lwr-Proteus Phase-Ii Experimental Data
M. Pecchia, D. Wicaksono, P. Grimm, A. Vasiliev, G. Perret, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 97, Pp. 153-164, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.07.001
Validation Studies And Interpretation Of The Oskarshamn-2 1999 Stability Event With Simulate-3k
A. Dokhane, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 96, Pp. 344-353, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.06.016
Testing The Sampling-Based Nuss-Rf Tool For The Nuclear Data Related Global Sensitivity Analysis With Monte Carlo Neutronics Calculations
T. Zhu, A. Vasiliev, H. Ferroukhi, D. Rochman, A. Pautz
Nuclear Science And Engineering, Vol. 184, (2016)
http://dx.doi.org/10.13182/NSE14-142
Analysis Of Effects Of Pellet-Cladding Bonding On Trapping Of The Released Fission Gases In High Burnup Kkl Bwr Fuels
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, R. Restani, S. Abolhassani, G. Ledergerber, W. Wiesenack
Nuclear Engineering And Design, Vol. 305, Pp. 559-568, (2016)
http://dx.doi.org/10.1016/j.nucengdes.2016.06.021
Selecting Benchmarks For Reactor Simulations: An Application To A Lead Fast Reactor
E. Alhassan, H. SjöStrand, P. Helgesson, M. ÖSterlund, S. Pomp, A.J. Koning, D. Rochman
Annals of Nuclear Energy, Vol. 96, Pp. 158-169, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.033
A Bayesian Monte Carlo Method For Fission Yield Covariance Information
D. Rochman, O. Leray, A. Vasiliev, H. Ferroukhi, A.J. Koning, M. Fleming, J.C. Sublet
Annals of Nuclear Energy, Vol. 95, Pp. 125-134, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.05.005
Re-Evaluation Of The Thermal Neutron Capture Cross Section Of 147nd
D. Rochman, O. Leray, G. Perret, A. Vasiliev, H. Ferroukhi, A.J. Koning
Annals of Nuclear Energy, Vol. 94, Pp. 612-617, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.024
Nuclear Data Uncertainty Propagation On Spent Fuel Nuclide Compositions
O. Leray, D. Rochman, P. Grimm, H. Ferroukhi, A. Vasiliev, M. Hursin, G. Perret, A. Pautz
Annals of Nuclear Energy, Vol. 94, Pp. 603-611, (2016)
http://dx.doi.org/10.1016/j.anucene.2016.03.023
Sampling Of Systematic Errors To Estimate Likelihood Weights In Nuclear Data Uncertainty Propagation
P. Helgesson, H. SjöStrand, A.J. Koning, J. RydéN, D. Rochman , E. Alhassan, S. Pomp
Nuclear Instruments And Methods in Physics Research A807, Pp. 137 149, (2016)
http://dx.doi.org/10.1016/j.nima.2015.10.024
Characterization Of The Relocated And Dispersed Fuel In The Halden Reactor Project Loca Tests Based On Gamma Scan Data
V. Brankov, G. Khvostov, K. Mikityuk, A. Pautz, W. Wiesenack
Nuclear Engineering And Design, Vol. 300, Pp. 97 106 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.11.023
210po Poisoning As Possible Cause Of Death: Forensic Investigations And Toxicological Analysis Of The Remains Of Yasser Arafat
P. Froidevaux, F. Bochud, S. Baechler, V. Castella, M. Augsburger, C. Bailat, K. Michaud, M. Straub, M. Pecchia, T-M. Jenk, T. Uldin, P. Mangin
Forensic Science International, Vol. 259 Pp. 1-9 , (2016)
http://dx.doi.org/10.1016/j.forsciint.2015.09.019
Steady-State Cfd Simulations Of An Eprtm Reactor Pressure Vessel: A Validation Study Based On The Juliette Experiments
R. Puragliesi, L. Zhou, O. Zerkak, A. Pautz
Nuclear Engineering And Design, Vol. 300, Pp. 41 56 (2016)
http://dx.doi.org/10.1016/j.nucengdes.2015.12.025
Localized Neutron Flux Assessment And Verification Studies Using Mcnpx Pwr Full Core Model
A. Vasiliev, H. Ferroukhi, M. Pecchia, A. Pautz
Annals of Nuclear Energy, Vol. 92, Pp. 317-332 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.026
Nuclear Data Uncertainty For Criticality-Safety: Monte Carlo Vs. Linear Perturbation
D. Rochman, A. Vasiliev, H. Ferroukhi, T. Zhu, S.C. Van Der Marck, A.J. Koning
Annals of Nuclear Energy, Vol. 92, Pp. 150-160 (2016)
http://dx.doi.org/10.1016/j.anucene.2016.01.042