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Daniel J. Siefman
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Stochastic vs. sensitivity-based integral parameter and nuclear data adjustments
D Siefman
European Physics Journal Plus 130 (10), 429, 2018
30*2018
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, 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, M Hursin, A Pautz
Annals of Nuclear Energy 85, 434-443, 2015
242015
Templating colloidal sieves for tuning nanotube surface interactions and optical sensor responses
AJ Gillen, DJ Siefman, SJ Wu, C Bourmaud, B Lambert, AA Boghossian
Journal of colloid and interface science 565, 55-62, 2020
162020
Neutronics modeling of the CROCUS reactor with SERPENT and PARCS codes
A Rais, D Siefman, M Hursin, A Ward, A Pautz
M&C 2017 - International Conference on Mathematics & Computational Methods …, 2017
162017
Methods and models for the coupled neutronics and thermal-hydraulics analysis of the CROCUS reactor at EFPL
A Rais, D Siefman, G Girardin, M Hursin, A Pautz
Science and Technology of Nuclear Installations 2015, 2015
152015
Data assimilation of post-irradiation examination data for fission yields from GEF
D Siefman, M Hursin, H Sjostrand, G Schnabel, D Rochman, A Pautz
EPJ Nuclear Science and Technology 6 (52), 17, 2020
132020
Design of separated element reflector experiments in CROCUS: PETALE
V Lamirand, G Perret, S Radman, D Siefman, M Hursin, P Frajtag, ...
Sixteenth International Symposium on Reactor Dosimetry, At Santa Fe, New …, 2017
132017
Development and Application of Data Assimilation Methods in Reactor Physics
DJ Siefman
École Polytechnique Fédérale de Lausanne, 2019
112019
Determination of Sobol Sensitivity Indices for Correlated Inputs with SHARK-X
M Hursin, D Siefman, G Perret, D Rochman, A Vasiliev, H Ferroukhi
PHYSOR 2018: Reactor Physics paving the way towards more efficient systems, 2018
112018
Analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II using a CASMO-5 reflected-assembly model
P Grimm, M Hursin, G Perret, D Siefman, H Ferroukhi
Progress in Nuclear Energy 101, 280-287, 2017
102017
Preliminary Design of a New Pulsed-Neutron Die-Away Experimental Testbed for Thermal Scattering Law Benchmarks (PNDA)(IER-501 CED-1)
D Siefman, E Heckmaier, W Zwyiec, D Heinrichs
Lawrence Livermore National Lab.(LLNL), Livermore, CA (United States), 2021
92021
Development and application of marginal likelihood optimization for integral parameter adjustment
D Siefman, M Hursin, G Schnabel, H Sjöstrand
Annals of Nuclear Energy 159, 108255, 2021
82021
Case Study of Data Assimilation Methods with the LWR-Proteus Phase II Experimental Campaign
DJ Siefman, M Hursin, P Grimm, A Pautz
M&C 2017 - International Conference on Mathematics & Computational Methods …, 2017
82017
Constrained Bayesian optimization of criticality experiments
D Siefman, C Percher, J Norris, A Kersting, D Heinrichs
Annals of Nuclear Energy 151, 2021
72021
Verification of the new implementations in SHARK-X for reactivity coefficients and relative reactivity worth UQ
M Hursin, D Siefman, G Perret, P Grimm, A Pautz
Proceedings of the PHYSOR-2016 conference, Sun Valley, Idaho, US, 2016
72016
CASMO-5 analysis of reactivity worths of burnt PWR fuel samples measured in LWR-PROTEUS Phase II
P Grimm, M Hursin, G Perret, D Siefman, H Ferroukhi
PHYSOR 2016, Sun Valley, ID, May 1–5, 2016, 2016
72016
Verification of a reactor physics calculation scheme for the Crocus reactor
M Hursin, D Siefman, A Rais, A Pautz
3rd International Technical Meeting on Small Reactors, 2014
72014
Representativity Analysis of the LWR-Proteus Phase II Experiments using SHARKX Stochastic Sampling Method
M Hursin, D Siefman, G Perret, A Pautz
ANS Best Estimate Plus Uncertainty International Conference (BEPU 2018), 2018
62018
PARCS Few-group Homogenized Parameters Generation using Serpent Monte Carlo code at the CROCUS Reactor
A Rais, D Siefman, G Girardin, M Hursin, A Pautz
IGORR 2014: International Group on Research Reactors, 2014
62014
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