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Adrien Bidaud

Observed names: A. BIDAUD, A. Bidaud, ADRIEN BIDAUD, BIDAUD, A., BIDAUD, Adrien, Bidaud, A., Bidaud, Adrien, Bidaud, Adrien V., Bidaud-Bonod, Adrien
Observed institutions: Université Paris-Sud, Institut polytechnique de Grenoble, Conservatoire National des Arts et Métiers, Argonne National Laboratory, Centre National de la Recherche Scientifique, Université Joseph Fourier, Commissariat à l'Énergie Atomique et aux Énergies Alternatives, Laboratoire d'Economie Appliquée de Grenoble, CEA Cadarache, Laboratoire de Physique des deux infinis Bordeaux, Direction des Energies, CEA Paris-Saclay, Institut National de Physique Nucléaire et de Physique des Particules, Laboratoire de Physique Subatomique et de Cosmologie, Institut de Physique Nucléaire d’Orsay, Communauté Université Grenoble Alpes, Université Bordeaux-I, Université Grenoble Alpes
ORCID: 0000-0002-1749-3759
Observed ORCID: 0000-0002-1749-3759
OpenAlex ID: A5011161966
A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT
2015 · Manuele Aufiero, Adrien Bidaud, et al. · Annals of Nuclear Energy · 125
Neutron-induced fission cross sections of short-lived actinides with the surrogate reaction method
2010 · G. Kessedjian, B. Jurado, et al. · Physics Letters B · 70
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The JEFF-3.1 Nuclear Data Library - JEFF Report 21
2006 · A. J. Koning, R.A. Forrest, et al. · 54
Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors
2011 · A. Nuttin, P. Guillemin, et al. · Annals of Nuclear Energy · 45
A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code CLASS
2015 · Baptiste Leniau, Baptiste Mouginot, et al. · Annals of Nuclear Energy · 43
The JEFF evaluated nuclear data project
2007 · A. J. Koning, M. Avrigeanu, et al. · 41
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A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool
2018 · Nicolas Thiollière, Jean-Baptiste Clavel, et al. · EPJ Nuclear Sciences & Technologies · 25
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The role of biomass gasification and methanisation in the decarbonisation strategies
2019 · Gabin Mantulet, Adrien Bidaud, et al. · Energy · 24
Opportunities and roadblocks in the decarbonisation of the global steel sector: A demand and production modelling approach
2023 · Kimon Keramidas, Silvana Mima, et al. · Energy and Climate Change · 21
Measurements of the Mass and Isotopic Yields of the 233U(nth,f) Reaction by the Lohengrin Spectrometer
2014 · F. Martin, C. Sage, et al. · Nuclear Data Sheets · 19
243 Am neutron-induced fission cross section in the fast neutron energy range
2012 · G. Kessedjian, G. Barreau, et al. · Physical Review C · 19
Recent Results from Lohengrin on Fission Yields and Related Decay Properties
2014 · O. Serot, C. Amouroux, et al. · Nuclear Data Sheets · 18
Advanced plutonium management in PWR, complementarity of thorium and uranium
2014 · M. Ernoult, S. David, et al. · Progress in Nuclear Energy · 17
Economy of uranium resources in a three-component reactor fleet with mixed thorium/uranium fuel cycles
2009 · J.N. Wilson, A. Bidaud, et al. · Annals of Nuclear Energy · 17
Strategies for short-term intermittency in long-term prospective scenarios in the French power system
2022 · Rodica Loisel, Lionel Lemiale, et al. · Energy Policy · 13
Neutronic predictors for PWR fuelled with multi-recycled plutonium and applications with the fuel cycle simulation tool CLASS
2017 · Fanny Courtin, Baptiste Leniau, et al. · Progress in Nuclear Energy · 10
Fundamentals of reactor physics with a view to the (possible) futures of nuclear energy
2017 · Xavier Doligez, Sandra Bouneau, et al. · Comptes Rendus Physique · 9
Americium mono-recycling in PWR: A step towards transmutation
2016 · A.-A. Zakari-Issoufou, Xavier Doligez, et al. · Annals of Nuclear Energy · 9
Fission Cross Sections and Fission-Fragment Mass Yields via the Surrogate Reaction Method
2008 · B. Jurado, G. Kessedjian, et al. · AIP conference proceedings · 9
Global and flexible models for Sodium-cooled Fast Reactors in fuel cycle simulations
2019 · M. Ernoult, X. Doligez, et al. · Annals of Nuclear Energy · 8
MOX fuel enrichment prediction in PWR using polynomial models
2015 · B. Mouginot, B. Leniau, et al. · Annals of Nuclear Energy · 7
Prediction of MgO volume fraction in an ADS fresh fuel for the scenario code CLASS
2015 · N. Thiollière, F. Courtin, et al. · Progress in Nuclear Energy · 5
OECD/NEA expert group on uncertainty analysis for criticality safety assessment: Results of benchmark on sensitivity calculation (phase III)
2012 · Т. А. Иванова, Cedric Laville, et al. · HAL (Le Centre pour la Communication Scientifique Directe) · 5
On data assimilation with Monte-Carlo-calculated and statistically uncertain sensitivity coefficients
2019 · D. Siefman, M. Hursin, et al. · Annals of Nuclear Energy · 4
Propagation of Nuclear Data Uncertainties in Deterministic Calculations: Application of Generalized Perturbation Theory and the Total Monte Carlo Method to a PWR Burnup Pin-Cell
2014 · P. Sabouri, A. Bidaud, et al. · Nuclear Data Sheets · 4
Works count: 138
Citation count: 665
H-index: 14
I10-index: 16
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