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20

Pierre SCIORA


Journal articles12 documents

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

Conference papers8 documents

  • E. Garcia, P. Sciora, G. Rimpault. Analysis of the feedback coefficients of the Superphenix start-up core with APOLLO3. ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France. ⟨cea-02394071v2⟩
  • P. Sciora, J.-B. Droin, B. Fontaine, Alain Zaetta. Importance of the Doppler Constant and of the fuel temperature evaluation for the design of a 'CADOR' core. ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France. ⟨cea-02394084v2⟩
  • H. Guo, P. Sciora, T. Kooyman, L. Buiron. Evaluation of the Control Rods Withdrawal in a Small Modular Sodium Fast Reactor and Analysis of the Impact on the Core Design. ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France. ⟨cea-02394085⟩
  • T. Kooyman, P. Sciora, C. Coquelet-Pascal. Some considerations on the design of a small versatile fast reactor. ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan Les Pins, France. ⟨cea-02394072⟩
  • P. Gauthe, P. Sciora. Sensitivity studies of sfr unprotected transients with global neutronic feedback coefficients. International Conference on Fast Reactors and Related Fuel Cycles Next Generation Nuclear Systems for Sustainable Development (FR17), Jun 2017, Yekaterinburg, Russia. ⟨hal-02419665⟩
  • B. Fontaine, P. Sciora, M. Vanier, C. Venard. ASTRID an innovative control rod system to manage reactivity. International Congress on Advances in Nuclear Power Plants (ICAPP - 2016), Apr 2016, San Francisco, United States. ⟨hal-02416292⟩
  • Christophe Venard, Thierry Beck, Bruno Bernardin, Alain Conti, David Gentet, et al.. The ASTRID core at the midterm of the conceptual design phase (AVP2). ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France. ⟨cea-02928262⟩
  • S. Borot, F. Alvarez-Velarde, E Fridman, I. Garcia Cruzado, N. Garcia Herranz, et al.. European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients. ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France. ⟨cea-02875256⟩