The jeff-3.1 nuclear data library-jeff report 21 A Koning, R Forrest, M Kellett, R Mills, H Henriksson, Y Rugama, ...
Organisation for Economic Co-operation and Development, 2006
435 2006 A collision history-based approach to sensitivity/perturbation calculations in the continuous energy Monte Carlo code SERPENT M Aufiero, A Bidaud, M Hursin, J Leppänen, G Palmiotti, S Pelloni, ...
Annals of Nuclear Energy 85, 245-258, 2015
153 2015 Neutron-induced fission cross sections of short-lived actinides with the surrogate reaction method G Kessedjian, B Jurado, M Aiche, G Barreau, A Bidaud, S Czajkowski, ...
Physics Letters B 692 (5), 297-301, 2010
91 2010 The JEFF evaluated nuclear data project AJ Koning, M Avrigeanu, V Avrigeanu, P Batistoni, E Bauge, MM Bé, ...
International Conference on Nuclear Data for Science and Technology, 721-726, 2007
66 2007 Comparative analysis of high conversion achievable in thorium-fueled slightly modified CANDU and PWR reactors A Nuttin, P Guillemin, A Bidaud, N Capellan, R Chambon, S David, ...
Annals of Nuclear Energy 40 (1), 171-189, 2012
65 2012 A neural network approach for burn-up calculation and its application to the dynamic fuel cycle code CLASS B Leniau, B Mouginot, N Thiolliere, X Doligez, A Bidaud, F Courtin, ...
Annals of Nuclear Energy 81, 125-133, 2015
37 2015 Economy of uranium resources in a three-component reactor fleet with mixed thorium/uranium fuel cycles JN Wilson, A Bidaud, N Capellan, R Chambon, S David, P Guillemin, ...
Annals of nuclear energy 36 (3), 404-408, 2009
28 2009 Core library for advanced scenario simulation, CLASS: principle & application B Mouginot, B Leniau, N Thiollière, M Ernoult, S David, X Doligez, ...
International Conference “The Role of Reactor Physics toward a Sustainable …, 2014
26 2014 Measurements of the mass and isotopic yields of the 233 U(nth , f) reaction at the Lohengrin spectrometer F Martin, C Sage, G Kessedjian, CO Bacri, A Bidaud, A Billebaud, ...
2011 2nd International Conference on Advancements in Nuclear Instrumentation …, 2011
25 2011 A methodology for performing sensitivity analysis in dynamic fuel cycle simulation studies applied to a PWR fleet simulated with the CLASS tool N Thiollière, JB Clavel, F Courtin, X Doligez, M Ernoult, Z Issoufou, ...
EPJ N-Nuclear Sciences & Technologies 4, 13, 2018
22 2018 3D coupling of Monte Carlo neutronics and thermal-hydraulics/thermic calculations as a simulation tool for innovative reactor concepts N Capellan, A Bidaud, S David, O Meplan, A Nuttin, J Wilson, J Brizi, ...
International Conference GLOBAL 2009 "The Nuclear Fuel Cycle: Sustainable …, 2009
20 * 2009 Advanced plutonium management in PWR, complementarity of thorium and uranium M Ernoult, S David, X Doligez, O Meplan, B Leniau, A Bidaud, A Nuttin, ...
Progress in Nuclear Energy 78, 330-340, 2015
18 2015 Recent results from Lohengrin on fission yields and related decay properties O Serot, C Amouroux, A Bidaud, N Capellan, S Chabod, A Ebran, H Faust, ...
Nuclear Data Sheets 119, 320-323, 2014
18 2014 OECD/NEA expert group on uncertainty analysis for criticality safety assessment: Results of benchmark on sensitivity calculation (phase III) T Ivanova, C Laville, J Dyrda, D Mennerdahl, Y Golovko, K Raskach, ...
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park …, 2012
17 2012 Am neutron-induced fission cross section in the fast neutron energy rangeG Kessedjian, G Barreau, M Aïche, B Jurado, A Bidaud, S Czajkowski, ...
Physical Review C 85 (4), 044613, 2012
17 2012 The role of biomass gasification and methanisation in the decarbonisation strategies G Mantulet, A Bidaud, S Mima
Energy 193, 116737, 2020
15 2020 Zero-power criticality benchmark evaluation of the Molten Salt Reactor Experiment D Shen, M Fratoni, M Aufiero, A Bidaud, J Powers, G Ilas
Proceedings of the International Conference on Physics of Reactors, PHYSOR 4012, 2018
14 2018 MURE, MCNP Utility for Reactor Evolution-User Guide-Version 1.0 O Meplan, J Wilson, A Bidaud, S David, N Capellan, B Leniau, A Nuttin, ...
IPNO-09-01, IPN Orsay, 2009
13 2009 Plutonium incineration and uranium 233 production in thorium fueled light water reactors F Michel-Sendis, S David, A Bidaud, JN Wilson, O Meplan, A Nuttin, ...
13 2005 Nuclear Data Uncertainty Analysis using the coupling of DRAGON with SUSD3D A Bidaud, G Marleau, E Noblat
2009 Int. Conf. on Mathematics Computational Methods and Reactor Physics …, 2009
11 2009