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THERMAL-HYDRAULICS IN LIQUID METAL FAST REACTORS
Dr. Antoine GerschenfeldCEA, France
29 January 2020
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Meet the Presenter
Dr. Antoine Gerschenfeld earned his PhD from Ecole Normale
Supérieure,
France, in 2012, and has been coordinating R&D on the
thermal-hydraulics of
Sodium Fast Reactors at the Commissariat a l Energie Atomique et
aus Energies
Alternatives (CEA)'s Thermal-Hydraulics and Fluid Mechanics
Section (STMF)
since 2013. In that capacity, he has led the development of a
subchannel
thermal-hydraulics code (TrioMC) as well as the development of a
tool for
coupling coarse and fine models in a single reactor-scale
simulation (MATHYS).
He has also been involved in a number of collaborations:
bilateral exchanges
with DOE, JAEA and IPPE; EURATOM projects on liquid-metal
reactors; and in
international GIF, NEA and IAEA working groups.
Email: [email protected]
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Introduction
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Introduction
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Introduction
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Issues: overall view
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Core / per-subassembly
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Core / overall behavior
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Hot pool / Core outlet
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Hot pool / Core outlet
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Hot pool / Core outlet
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Hot pool
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Free surface
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Intermediate heat exchangers (SFRs)
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Cold pool
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Pumps
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Diagrid
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Vessel cooling system
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Issues / Global
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Issues / Global
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Modelling thermal-hydraulics
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Modelling / Codes
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Modelling / Codes
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Modelling / Codes
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Modelling / Codes
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Modelling / Codes
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Application
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Natural convection
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Natural convection
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Natural convection / Code coupling
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Natural convection / Results
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Natural convection / Results
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Natural convection / Validation
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Natural convection / Validation
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Natural convection / Validation
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Conclusion
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Upcoming Webinars
25 February 2020 (8 pm US EST)
SFR Safety Design Criteria (SDC) and Safety Design
Guidelines(SDGs)
Mr. Shigenobu Kubo, JAEA, Japan
26 March 2020 MicroReactors: A Technology Option for Accelerated
Innovation
Dr. DV Rao, LANL, USA and Dr. Jess Gehin, INL, USA
29 April 2020 GIF VHTR Hydrogen Production ProjectManagement
Board
Dr. Sam Suppiah, CNL, Canada
