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Poster De Conférence Année : 2023

SAIGA : an in-pile test largely instrumented and devoted to study the degradation of a Sodium Fast Reactor core with mitigation device in Severe Accident Conditions

Résumé

After the end of ASTRID conceptual design studies, CEA has launched a long-term R&D roadmap on generic Sodium Fast Reactor issues including the Severe Accident field based on 3 pillars: - Improving knowledge of the phenomena and equations governing the sequence of events occurring during a severe accident. Developing existing or future calculation codes and numerical platforms focusing specifically on severe accidents in order to sequence and couple these codes; - Extend the experimental database needed to validate the calculation and simulation tools, such as SIMMER-V code, to cover the ranges of the parameters expected in future reactors incorporating advanced design options; - Qualify innovative systems for mitigating the consequences of radioactive emissions in severe accident conditions proposed for future reactors. Transfer Tubes have been installed in recent SFR core designs so that molten core can rapidly relocate out of core region. The objective is to prevent prompt criticality in the core region by removing sufficiently rapidly a significant mass of fissile material. This mitigation device is designed to help return the reactor to a safe state after a severe accident. SAIGA Project will provide experimental results of an integral test to validate SIMMER-V calculations on Corium Transfer Tubes
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Dates et versions

cea-04525921 , version 1 (29-03-2024)

Identifiants

  • HAL Id : cea-04525921 , version 1

Citer

Francois Charollais, Frederic Michel, Grégoire de Izarra, Frederic Payot, Laurent Maurin, et al.. SAIGA : an in-pile test largely instrumented and devoted to study the degradation of a Sodium Fast Reactor core with mitigation device in Severe Accident Conditions. ANIMMA 2023, Jun 2023, lucca, Italy. , 2023. ⟨cea-04525921⟩
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