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authFullName_s : P. Sciora

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
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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

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
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Flux distribution of the Superphénix start-up core for the validation of neutronic codes

E. Garcia , P. Sciora , T. Kooyman , G. Rimpault , H. Guo , et al.
Annals of Nuclear Energy, 2019, 133, pp.889-899. ⟨10.1016/j.anucene.2019.06.066⟩
Journal articles cea-02535326v1
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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

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 , et al.
Annals of Nuclear Energy, 2018, ⟨10.1016/j.anucene.2019.01.042⟩
Journal articles cea-02339945v1
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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
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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
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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
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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
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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
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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

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

Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core

F. Bertrand , X. Manchon , N. Marie , J.B. B. Droin , D. Schmitt , et al.
Nuclear Engineering and Design, 2019, 355, pp.110319. ⟨10.1016/j.nucengdes.2019.110319⟩
Journal articles hal-02481998v1
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European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficients

S. Bortot , P. Sciora , F. Alvarez-Velarde , E. Fridman , I. Garcia Cruzado , et al.
ICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France. paper 15361
Conference papers cea-02509072v1
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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