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Andreas Pautz
Andreas Pautz
Professor of Nuclear Engineering, École Polytechnique Fédérale de Lausanne
Verified email at epfl.ch
Title
Cited by
Cited by
Year
A statistical sampling method for uncertainty analysis with SCALE and XSUSA
ML Williams, G Ilas, MA Jessee, BT Rearden, D Wiarda, W Zwermann, ...
Nuclear technology 183 (3), 515-526, 2013
1322013
Fuel cycle advantages and dynamics features of liquid fueled MSR
J Křepel, B Hombourger, C Fiorina, K Mikityuk, U Rohde, S Kliem, A Pautz
Annals of Nuclear Energy 64, 380-397, 2014
632014
DORT-TD: A transient neutron transport code with fully implicit time integration
A Pautz, A Birkhofer
Nuclear science and engineering 145 (3), 299-319, 2003
602003
Development and verification of the neutron diffusion solver for the GeN-Foam multi-physics platform
C Fiorina, N Kerkar, K Mikityuk, P Rubiolo, A Pautz
Annals of Nuclear Energy 96, 212-222, 2016
562016
Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor
C Fiorina, M Hursin, A Pautz
Annals of Nuclear Energy 101, 419-428, 2017
522017
Nuclear data uncertainty propagation on spent fuel nuclide compositions
O Leray, D Rochman, P Grimm, H Ferroukhi, A Vasiliev, M Hursin, ...
Annals of Nuclear Energy 94, 603-611, 2016
492016
The OFFBEAT multi-dimensional fuel behavior solver
A Scolaro, I Clifford, C Fiorina, A Pautz
Nuclear Engineering and Design 358, 110416, 2020
452020
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 75, 713-722, 2015
362015
Influence of nuclear data uncertainties on reactor core calculations
M Klein, L Gallner, B Krzykacz-Hausmann, A Pautz, W Zwermann
Kerntechnik 76 (3), 174-178, 2011
322011
Influence of nuclear data uncertainties on reactor core calculations
M Klein, L Gallner, B Krzykacz-Hausmann, A Pautz, W Zwermann
Kerntechnik 76 (3), 174-178, 2011
322011
Uncertainty analyses with nuclear covariance data in reactor core calculations
W Zwermann, B Krzykacz-Hausmann, L Gallner, A Pautz
Annual meeting on nuclear technology 2010. Documentation, 2010
302010
Quantification of the uncertainty of the physical models in the system thermal-hydraulic codes–PREMIUM benchmark
T Skorek, A de Crécy, A Kovtonyuk, A Petruzzi, R Mendizábal, ...
Nuclear Engineering and Design 354, 110199, 2019
282019
SIMULATE-3K analyses of neutron noise response to fuel assembly vibrations and thermal-hydraulics parameters fluctuations
D Chionis, A Dokhane, L Belblidia, M Pecchia, G Girardin, H Ferroukhi, ...
Int. Conf. Mathematics & Computational Methods Applied to Nuclear Science …, 2017
282017
A two-step approach to uncertainty quantification of core simulators
A Yankov, B Collins, M Klein, MA Jessee, W Zwermann, K Velkov, A Pautz, ...
Science and Technology of Nuclear Installations 2012, 2012
272012
Kilogram‐Scale Crystallogenesis of Halide Perovskites for Gamma‐Rays Dose Rate Measurements
P Andričević, P Frajtag, VP Lamirand, A Pautz, M Kollár, B Náfrádi, ...
Advanced Science 8 (2), 2001882, 2021
262021
Future experimental programmes in the CROCUS reactor
VP Lamirand, M Hursin, G Perret, P Frajtag, O Pakari, A Pautz
Conference proceedings of RRFM/IGORR 2016, 284-292, 2016
262016
Influence of nuclear covariance data on reactor core calculations
W Zwermann, B Krzykacz-Hausmann, L Gallner, A Pautz
Second International Workshop on Nuclear Data Evaluation for Reactor …, 2009
262009
Status of XSUSA for sampling based nuclear data uncertainty and sensitivity analysis
W Zwermann, L Gallner, M Klein, B Krzykacz-Hausmann, I Pasichnyk, ...
EPJ Web of Conferences 42, 03003, 2013
252013
Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
D Siefman, M Hursin, D Rochman, S Pelloni, A Pautz
The European Physical Journal Plus 133 (10), 429, 2018
242018
Full Core modeling techniques for research reactors with irregular geometries using Serpent and PARCS applied to the CROCUS reactor
DJ Siefman, G Girardin, A Rais, A Pautz, M Hursin
Annals of Nuclear Energy 85, 434-443, 2015
242015
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