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Pierre SCIORA
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ESFR-SIMPLE: new HORIZON-EURATOM project on SFR safetyICAPP 2023 - International Congress on Advances in Nuclear Power Plants, Apr 2023, Gyeongju, South Korea. pp.1471
Communication dans un congrès
cea-04187176v1
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Multiphysics analysis of power transients based on power system and nuclear dynamics software chainingPowertech 2023, Jun 2023, Belgrade, Serbia
Communication dans un congrès
hal-04157916v1
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Multi-physics calculations of FFTF loss of flow without scram transient: impact of neutronics and thermomechanics on CATHARE3 models19th international topical meeting on Nuclear Reactor Thermal Hydraulics (NURETH 19), Mar 2022, Brussels (virtual), Belgium
Communication dans un congrès
cea-04374219v1
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Analysis of the feedback coefficients of the Superphenix start-up core with APOLLO3ICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France
Communication dans un congrès
cea-02394071v2
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Some considerations on the design of a small versatile fast reactorICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan Les Pins, France
Communication dans un congrès
cea-02394072v1
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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 DesignICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France
Communication dans un congrès
cea-02394085v1
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Importance of the Doppler Constant and of the fuel temperature evaluation for the design of a 'CADOR' coreICAPP 2019 - International Congress on Advances in Nuclear Power Plants, May 2019, Juan-Les-Pins, France
Communication dans un congrès
cea-02394084v2
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Sensitivity studies of sfr unprotected transients with global neutronic feedback coefficientsInternational 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
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ASTRID an innovative control rod system to manage reactivityInternational Congress on Advances in Nuclear Power Plants (ICAPP - 2016), Apr 2016, San Francisco, United States
Communication dans un congrès
hal-02416292v1
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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
Communication dans un congrès
cea-02928262v1
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European benchmark on the ASTRID-like low-void-effect core characterization: neutronic parameters and safety coefficientsICAPP 2015 - International Congress on Advances in Nuclear Power Plants, May 2015, Nice, France
Communication dans un congrès
cea-02875256v1
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