Optimized control rod designs for Generation-IV fast reactors using alternative absorbers and moderators
H. Guo
,
L. Buiron
,
T. Kooyman
,
P. Sciora
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
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Optimization of reactivity control in a small modular sodium-cooled fast reactor
H. Guo
,
L. Buiron
,
P. Sciora
,
T. Kooyman
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.
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
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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.
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
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
Journal articles
cea-02339877v1
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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
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
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Design Directions of Optimized Reactivity Control Systems in Sodium Fast Reactors
H. Guo
,
P. Sciora
,
L. Buiron
,
T. Kooyman
Journal articles
cea-02339949v1
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Coupled thermalhydraulic-neutronic stability extended criterion in a SFR core
F. Bertrand
,
X. Manchon
,
N. Marie
,
J.B. B. Droin
,
D. Schmitt
,
et al.
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
Journal articles
cea-02339872v1
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