Pierre SCIORA

Publications

Article dans une revue (12)

CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors Alain Zaetta,Bruno Fontaine,Pierre Sciora,Romain Lavastre,Robert Jacqminet al. EPJ N - Nuclear Sciences & Technologies, 2019, 5, pp.1. ⟨10.1051/epjn/2018049⟩ Article dans une revue cea-02071114v1
Optimization of reactivity control in a small modular sodium-cooled fast reactor H. Guo,L. Buiron,P. Sciora,T. Kooyman Nuclear Engineering and Technology, 2019, ⟨10.1016/j.net.2019.12.015⟩ Article dans une revue cea-02529236v1
Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators H. Guo,L. Buiron,T. Kooyman,P. Sciora Annals of Nuclear Energy, 2019, 132, pp.713-722. ⟨10.1016/j.anucene.2019.07.007⟩ Article dans une revue cea-02534789v1
Flux distribution of the Superphénix start-up core for the validation of neutronic codes E. Garcia,P. Sciora,T. Kooyman,G. Rimpault,H. Guoet al. Annals of Nuclear Energy, 2019, 133, pp.889-899. ⟨10.1016/j.anucene.2019.06.066⟩ Article dans une revue cea-02535326v1
Evaluation of the neutronic Superphenix start-up commissioning tests with TRIPOLI4 E. Garcia,P. Sciora,G. Rimpault Annals of Nuclear Energy, 2019, 129, pp.366-374. ⟨10.1016/j.anucene.2019.02.012⟩ Article dans une revue cea-02340001v1
Design Directions of Optimized Reactivity Control Systems in Sodium Fast Reactors H. Guo,P. Sciora,L. Buiron,T. Kooyman Nuclear Engineering and Design, 2019, 341, ⟨10.1016/j.nucengdes.2018.11.008⟩ Article dans une revue cea-02339949v1
Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core F. Bertrand,X. Manchon,N. Marie,J.B. B. Droin,D. Schmittet al. Nuclear Engineering and Design, 2019, 355, pp.110319. ⟨10.1016/j.nucengdes.2019.110319⟩ Article dans une revue istex hal-02481998v1
A three-dimensional neutronics - thermohydraulics Unprotected Loss Of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices A. Bachrata,L. Trotignon,P. Sciora,M. Saez Nuclear Engineering and Design, 2018, ⟨10.1016/j.nucengdes.2019.02.015⟩ Article dans une revue cea-02339667v1
Advanced method for neutronic simulation of control rods in sodium fast reactors numerical and experimental validation H. Guo,Ey. Garcia-Cervantes,B. Faure,L. Buiron,P. Archieret al. Annals of Nuclear Energy, 2018, ⟨10.1016/j.anucene.2019.01.042⟩ Article dans une revue cea-02339945v1
Application of Minor Actinides as Burnable Poisons in Sodium Fast Reactors H. Guo,T. Kooyman,P. Sciora,L. Buiron Nuclear Technology, 2018, 205 (11), pp.1447-1459. ⟨10.1080/00295450.2019.1611304⟩ Article dans une revue cea-02339877v1
Application of boron carbide as burnable poison in sodium fast reactors H. Guo,P. Sciora,T. Kooyman,L. Buiron,G. Rimpault Nuclear Technology, 2018, 205 (11), pp.1433-1446. ⟨10.1080/00295450.2019.1620054⟩ Article dans une revue cea-02339872v1
Phenomenological investigation of sodium boiling in a SFR core during a postulated ULOF transient with CATHARE 2 system code: a stabilized boiling case Nicolas Alpy,Philippe Marsault,Marine Anderhuber,Antoine Gerschenfeld,Pierre Scioraet al. Journal of Nuclear Science and Technology, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩ Article dans une revue cea-02933360v1

Communication dans un congrès (11)

Multiphysics analysis of power transients based on power system and nuclear dynamics software chaining Charly Boudot,Jean-Baptiste Droin,Pierre Sciora,Yvon Besanger,Bruno Robisson Powertech 2023, Jun 2023, Belgrade, Serbia Communication dans un congrès hal-04157916v1
ESFR-SIMPLE: new HORIZON-EURATOM project on SFR safety Pierre Sciora,Konstantin Mikityuk,Paul-Vincent Bonzom,Emil Fridman,Evaldas Bubeliset al. ICAPP 2023 - International Congress on Advances in Nuclear Power Plants, Apr 2023, Gyeongju, South Korea. pp.1471 Communication dans un congrès cea-04187176v1
Multi-physics calculations of FFTF loss of flow without scram transient: impact of neutronics and thermomechanics on CATHARE3 models Simon Li,Sophie Bajard,Zheng Zhang,Alain Conti,Pierre Scioraet al. 19th international topical meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), Mar 2022, Brussels (virtual), Belgium Communication dans un congrès cea-04374219v1
Evaluation of the Control Rods Withdrawal in a Small Modular Sodium Fast Reactor and Analysis of the Impact on the Core Design H. Guo,P. Sciora,T. Kooyman,L. Buiron ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France Communication dans un congrès cea-02394085v1
Importance of the Doppler Constant and of the fuel temperature evaluation for the design of a 'CADOR' core P. Sciora,J.-B. B Droin,B. Fontaine,Alain Zaetta ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France Communication dans un congrès cea-02394084v2
Some considerations on the design of a small versatile fast reactor T. Kooyman,P. Sciora,C. Coquelet-Pascal ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan Les Pins, France Communication dans un congrès cea-02394072v1
Analysis of the feedback coefficients of the Superphenix start-up core with APOLLO3 E. Garcia,P. Sciora,G. Rimpault ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France Communication dans un congrès cea-02394071v2
Sensitivity studies of sfr unprotected transients with global neutronic feedback coefficients P. Gauthe,P. Sciora International Conference on Fast Reactors and Related Fuel Cycles Next Generation Nuclear Systems for Sustainable Development (FR17), Jun 2017, Yekaterinburg, Russia Communication dans un congrès hal-02419665v1
ASTRID an innovative control rod system to manage reactivity B. Fontaine,P. Sciora,M. Vanier,C. Venard International Congress on Advances in Nuclear Power Plants (ICAPP - 2016), Apr 2016, San Francisco, United States Communication dans un congrès hal-02416292v1
Sodium void map preparation for the safety analysis of sodium-ccoled fast reactors using the Monte carlo code Serpent S. Borot,F. Alvarez-Velarde,E Fridman,I. Garcia Cruzado,N. Garcia Herranzet al. ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France Communication dans un congrès cea-02875256v1
The ASTRID core at the midterm of the conceptual design phase (AVP2) Christophe Venard,Thierry Beck,Bruno Bernardin,Alain Conti,David Gentetet al. ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France Communication dans un congrès cea-02928262v1