Pierre SCIORA

23

Documents

Publications

	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⟩ Journal articles 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. Guo Annals of Nuclear Energy, 2019, 133, pp.889-899. ⟨10.1016/j.anucene.2019.06.066⟩ Journal articles 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⟩ Journal articles cea-02340001v1
	CADOR “Core with Adding DOppleR effect” concept application to sodium fast reactors Alain Zaetta , Bruno Fontaine , Pierre Sciora , Romain Lavastre , Robert Jacqmin EPJ N - Nuclear Sciences & Technologies, 2019, 5, pp.1. ⟨10.1051/epjn/2018049⟩ Journal articles 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⟩ Journal articles cea-02529236v1
	Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core F. Bertrand , X. Manchon , N. Marie , J.B. B. Droin , D. Schmitt Nuclear Engineering and Design, 2019, 355, pp.110319. ⟨10.1016/j.nucengdes.2019.110319⟩ Journal articles hal-02481998v1
	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⟩ Journal articles cea-02339949v1
	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⟩ Journal articles cea-02339872v1
	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. Archier Annals of Nuclear Energy, 2018, ⟨10.1016/j.anucene.2019.01.042⟩ Journal articles 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⟩ Journal articles cea-02339877v1
	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⟩ Journal articles cea-02339667v1
	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 Sciora Journal of Nuclear Science and Technology, 2016, 53 (5), pp.692-697. ⟨10.1080/00223131.2015.1111778⟩ Journal articles cea-02933360v1

	ESFR-SIMPLE: new HORIZON-EURATOM project on SFR safety Pierre Sciora , Konstantin Mikityuk , Paul-Vincent Bonzom , Emil Fridman , Evaldas Bubelis ICAPP 2023 - International Congress on Advances in Nuclear Power Plants, Apr 2023, Gyeongju, South Korea. pp.1471 Conference papers cea-04187176v1
	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 Conference papers hal-04157916v1
	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 Sciora 19th international topical meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), Mar 2022, Brussels (virtual), Belgium Conference papers cea-04374219v1
	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 Conference papers cea-02394071v2
	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 Conference papers cea-02394072v1
	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 Conference papers cea-02394084v2
	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 Conference papers cea-02394085v1
	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 Conference papers 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 Conference papers hal-02416292v1
	European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients S. Borot , F. Alvarez-Velarde , E Fridman , I. Garcia Cruzado , N. Garcia Herranz ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France Conference papers cea-02875256v1
	The ASTRID core at the midterm of the conceptual design phase (AVP2) Christophe Venard , Thierry Beck , Bruno Bernardin , Alain Conti , David Gentet ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France Conference papers cea-02928262v1