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Conference

Degraded core relocation in Sodium-cooled Fast Reactor severe accident $-$ particle-size debris flow

Subjects: SFR; Mitigation; SIMMERSydney; Australia

  • Source: IYNC 2020 - International Youth Nuclear Congress ; https://cea.hal.science/cea-02614131 ; IYNC 2020 - International Youth Nuclear

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Conference

Degraded core relocation in Sodium-cooled Fast Reactor severe accident $-$ particle-size debris flow

Subjects: SFR; Mitigation; SIMMERSydney; Australia

  • Source: IYNC 2020 - International Youth Nuclear Congress ; https://cea.hal.science/cea-02614131 ; IYNC 2020 - International Youth Nuclear

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Conference

Degraded core relocation in Sodium-cooled Fast Reactor severe accident $-$ particle-size debris flow

Subjects: SFR; Mitigation; SIMMERSydney; Australia

  • Source: IYNC 2020 - International Youth Nuclear Congress ; https://cea.hal.science/cea-02614131 ; IYNC 2020 - International Youth Nuclear

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Conference

Degraded core relocation in Sodium-cooled Fast Reactor severe accident $-$ particle-size debris flow

Subjects: SFR; Mitigation; SIMMERSydney; Australia

  • Source: IYNC 2020 - International Youth Nuclear Congress ; https://cea.hal.science/cea-02614131 ; IYNC 2020 - International Youth Nuclear

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French developments for improving In Service Inspection of SFRs

Subjects: Non-Destructive-Examination; ASTRID; InspectionJuan Les Pins; France

  • Source: ICAPP 2019 - International Congress on Advances in Nuclear Power Plants ; https://cea.hal.science/cea-02338464 ; ICAPP 2019 - International Congress on Advances in

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Conference

French developments for improving In Service Inspection of SFRs

Subjects: Non-Destructive-Examination; ASTRID; InspectionJuan Les Pins; France

  • Source: ICAPP 2019 - International Congress on Advances in Nuclear Power Plants ; https://cea.hal.science/cea-02338464 ; ICAPP 2019 - International Congress on Advances in

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Conference

Two-tanks heat storage for variable electricity production in SFR: preliminary architecture and transient results

Subjects: SFR; flexibility; CATHAREJuan Les Pins; France

  • Source: ICAPP 2019 - International Congress on Advances in Nuclear Power Plants ; https://cea.hal.science/cea-02394093 ; ICAPP 2019 - International Congress on Advances in

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Conference

Study of irradiated and non-irradiated MOX fuel reprocessing

Subjects: MOX; SFR; LWRSeattle; United States

  • Source: TOP FUEL 2019 ; https://cea.hal.science/cea-02394092 ; TOP FUEL 2019, Sep 2019, Seattle, United States

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PIRAT - An analytical tool for reliability assessment of reactivity control systems - Progress and applications to Sodium Fast Reactors

Subjects: PIRAT; DEBSE; Reactivity Control SystemJuan-Les-Pins; France

  • Source: ICAPP19 ; https://hal.science/hal-02411057 ; ICAPP19, May 2019, Juan-Les-Pins, France

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Conference

Impact of neutronics parameters in a loss-of-flow transient simulation of a low-void sodium-cooled nuclear reactor

Subjects: Multiphysics; SFR; CFVPortland; United States

  • Source: M&C 2019 ; https://hal.science/hal-02411093 ; M&C 2019, 2019, Portland, United States ; https:/www.mc2019.org

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  • 1-10 of  138 results for ""Nuclear Theory (nucl-th)""