Journal Publications 2018

Monte Carlo nuclear data adjustment via integral information
D. Rochman, E. Bauge, A. Vasiliev, H. Ferroukhi, S. Pelloni, A.J. Koning, J.CH. Sublet
Eur. Phys. J. Plus (2018) 133: 537
https://doi.org/10.1140/epjp/i2018-12361-x

Measurement of the radiative capture cross section of the s-process branching points 204Tl and 171Tm at the n_TOF facility (CERN)
N_TOF Collaboration including D. Rochman
EPJ Web of Conferences 178, 03004 (2018)
https://doi.org/10.1051/epjconf/201817803004

Subchannel modeling of single rod bowing in a bundle geometry
R. Mukin, R. Puragliesi, M. Pecchia, M. Seidl
Nuclear Engineering and Design 340 (2018) 347–369
https://doi.org/10.1016/j.nucengdes.2018.09.032

Performance assessment of adjusted nuclear data along with their covariances on the basis of fast reactor experiments
S. Pelloni, D. Rochman
Annals of Nuclear Energy 115 (2018) 323–342
https://doi.org/10.1016/j.anucene.2018.07.043

Technical note: On modeling central void formation in LWR fuel pellets due to hightemperature restructuring
G. Khvostov
Nuclear Engineering and Design
https://doi.org/10.1016/j.net.2018.07.003

Iron NRT- and arc-displacement cross sections and their covariances
S.P. Simakov, U. Fischer, A.J. Koning, A.Yu. Konobeyev, D. Rochman
Nuclear Materials and Energy 15 (2018) 244-248
https://doi.org/10.1140/epjp/i2018-11926-y

Systematics of Nd cumulative fission yields for neutron-induced fission of 235U, 238U, 238Pu, 239Pu, 240Pu and 241Pu
G. Noguere, J. Tommasi, E. Privas, K.-H. Schmidt, D. Rochman
Eur. Phys. J. Plus (2018) 133: 99
https://doi.org/10.1051/epjn/2018019

Efficient use of Monte Carlo: the fast correlation coefficient
H. Sjöstrand, N. Asquith, P. Helgesson, D. Rochman, St. van der Marck
EPJ Nuclear Sci. Technol. 4, 15 (2018)
https://doi.org/10.1051/epjn/2018019

Consistent criticality and radiation studies of Swiss spent nuclear fuel: The CS2M approach
D. Rochman, A. Vasiliev, H. Ferroukhi, M. Pecchia
Journal of Hazardous Materials 357 (2018) 384-392
https://doi.org/10.1016/j.jhazmat.2018.05.041

Unsteady Single-Phase Natural-Circulation Flow Mixing Prediction Using 3-D Thermal-Hydraulic System and CFD Codes
A. Bousbia Salah, S. C. Ceuca, R. Puragliesi, R. Mukin, A. Grahn, S. Kliem, J. Vlassenbroeck, H. Austregesilo
Nuclear Technology, Volume 203 Issue 3, pp. 293-314 (2018)
https://doi.org/10.1080/00295450.2018.1461517

Nuclear data correlation between different isotopes via integral information
D. Rochman, A. Vasiliev, A.Dokhane, H. Ferroukhi
EPJ Nuclear Sci. Technol. 4, 6 (2018)
https://doi.org/10.1051/epjn/2018005

Uncertainties for Swiss LWR spent nuclear fuels due to nuclear data
D. Rochman, E. Bauge, A. Vasiliev, H. Ferroukhi. G. Perret
EPJ Nuclear Sci. Technol. 4, 6 (2018)
https://doi.org/10.1051/epjn/2018006

Validation Of Psi Best Estimate Plus Uncertainty Methodology Against Spert-Iii Reactivity Initiated Accident Experiments
A. Dokhane, G. Grandi, A. Vasiliev, D. Rochman, H. Ferroukhi
Annals of Nuclear Energy 118 (2018) 178 184
https://doi.org/10.1016/j.anucene.2018.04.022

Monte Carlo Simulation Of A Scintillation Detector For Spent Fuel Characterization In A Hot Cell
M. Papadionysiou, G. Perret, R. Zboray, R. Adams, J.-B. Mosset
Nuclear Engineering And Design 332 (2018) 119 126
https://doi.org/10.1016/j.nucengdes.2018.03.033

SiC Cladding Thermal Conductivity Requirements For Normal Operation And Loca Conditions
C. Cozzo, S. Rahman
Progress in Nuclear Energy 106 (2018) 278 283
https://doi.org/10.1016/j.pnucene.2018.03.016

Endf/B-Viii.0: The 8th Major Release Of The Nuclear Reaction Data Library With Cielo-Project Cross Sections, New Standards And Thermal Scattering Data
D. A. Brown, M. B. Chadwick, R. Capote, A. C. Kahler, A.Trkov, M. W. Herman, A. A. Sonzogni,Y. Danon,A. D. Carlson, M. Dunn, D. L. Smith, G. M. Hale, G. Arbanas, R. Arcilla, C.R. Bates, B. Beck,B. Becker,F. Brown, R. J. Casperson, J. Conlin, D. E. Cullen, M.-A. Descalle, R. Firestone, T. Gaines, K. H. Guber,A. I. Hawari, J. Holmes, T. D. Johnson, T. Kawano, B. C. Kiedrowski, A. J. Koning, S. Kopecky, L. Leal,J.P. Lestone, C. Lubitz, J. I.M´Arquez Dami´An, C. M. Mattoon, E. A. Mccutchan, S. Mughabghab,P. Navratil, D. Neudecker, G.P. A. Nobre, G. Noguere,M.Paris, M. T. Pigni, A. J. Plompen, B. Pritychenko,V. G. Pronyaev, D. Roubtsov, D. Rochman,P. Romano,P. Schillebeeckx, S. Simakov, M. Sin,I. Sirakov,B. Sleaford, V. Sobes, E. S. Soukhovitskii,I. Stetcu, P. Talou,I. Thompson, S. Van Der Marck, L.Welser-Sherrill, D. Wiarda, M. White, J. L.Wormald, R. Q.Wright, M. Zerkle, G.Zerovnik , Y. Zhu
Nuclear Data Sheets 148 (2018) 1 142
https://doi.org/10.1016/j.nds.2018.02.001

Cross-Section Adjustment In The Fast Energy Range On The Basis Of An Asymptotic Progressing Nuclear Data Incremental Adjustment (Apia) Methodology
S. Pelloni, D. Rochman
Annals of Nuclear Energy 115 (2018) 323 342
https://doi.org/10.1016/j.anucene.2018.01.037

Models For Numerical Simulation Of Burst Fgr In Fuel Rods Under The Conditions Of Ria
G. Khvostov
Nuclear Engineering And Design Volume 328, March 2018, Pages 36-57
http://dx.doi.org/10.1016/j.nucengdes.2017.12.028

Sfcompo-2.0: An Oecd Nea Database Of Spent Nuclear Fuel Isotopic Assays, Reactor Design Specifications, And Operating Data
F. Michel-Sendis, I. Gauld, J.S. Martinez, C. Alejano, M. Bossant, D. Boulanger, O. Cabellos, V. Chrapciak, J. Conde, I. Fast, M. Gren, K. Govers, M. Gysemans, V. Hannstein, F. Havlu, M. Hennebach, G. Hordosy, G. Ilas, R. Kilger, R. Mills, D. Mountford, P. Ortego, G. Radulescu, M. Rahimi, A. Ranta-Aho, K. RantamäKi, B. Ruprecht, N. Soppera, M. Stuke, K. Suyama, S. Tittelbach, C. Tore, S. Van Winckel, A. Vasiliev, T. Watanabe, Toru Yamamoto, Toshihisa Yamamoto
Annals of Nuclear Energy 110 (2017) 779 788
http://dx.doi.org/10.1016/j.anucene.2017.07.022

Deterministic Sampling For Propagating Epistemic And Aleatory Uncertainty In Dynamic Event Tree Analysis
S. Rahman, D.R. Karanki, A. Epiney, D. Wicaksono, O. Zerkak, V.N. Dang
Reliability Engineering & System Safety Volume 162, June 2017, Pages 91-102
https://doi.org/10.1016/j.ress.2018.03.009

Epistemic And Aleatory Uncertainties In Integrated Deterministic And Probabilistic Safety Assessment: Tradeoff Between Accuracy And Accident Simulations
D.R. Karanki, S. Rahman, V.N. Dang, O. Zerkak
Reliability Engineering & System Safety Volume 162, June 2017, Pages 91-102
https://doi.org/10.1016/j.ress.2017.01.015

On The Characteristics Of The Flow And Heat Transfer In The Core Bypass Region Of A Pwr
I. Clifford, M. Pecchia, R. Puragliesi, A. Vasiliev, H. Ferroukhi
Nuclear Engineering And Design 330 (2018) 117 128
https://doi.org/10.1016/j.nucengdes.2018.01.039

Modelling And Analysis Of Selected Oecd Pkl3 Station-Blackout Experiments Using Trace
R. Mukin, I. Clifford, O. Zerkak, H. Ferroukhi
Nuclear Engineering and Technology, Net 473. (2017)
https://doi.org/10.1016/j.net.2017.12.005

On The Options For Incorporating Nuclear Data Uncertainties In Criticality Safety Assessments For Lwr Fuel
A. Vasiliev, D. Rochman, M. Pecchia, H. Ferroukhi
Annals of Nuclear Energy, Vol. 116, Pp. 57 68 (2018)
https://doi.org/10.1016/j.anucene.2018.01.046

How Inelastic Scattering Stimulates Nonlinear Reactor Core Parameter Behaviour
D. Rochman, A. Vasiliev, H. Ferroukhi, H. Dokhane, A. Koning
Annals of Nuclear Energy, Vol. 112, Pp. 236 244 (2018)
https://doi.org/10.1016/j.anucene.2017.10.018

Analysis Of Simplified Bwr Full Core With Serpent-2/Simulate-3 Hybrid Stochastic/Deterministic Code
Y. Jo, M. Hursin, D. Lee, H. Ferroukhi, A. Pautz
Annals of Nuclear Energy, Vol. 111, Pp. 141-151 (2018)
http://dx.doi.org/10.1016/j.anucene.2017.08.061