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

doi:10.1016/j.nucengdes.2019.02.015

Journal Articles Nuclear Engineering and Design Year : 2018

A three-dimensional neutronics - thermohydraulics Unprotected Loss Of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices

(1) , (1) , (1) , (1)

1

A. Bachrata

Function : Author

CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

L. Trotignon

Function : Author

CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

P. Sciora

Function : Author
PersonId : 182856
IdHAL : pierre-sciora
ORCID : 0000-0002-5882-6003

CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

CV

M. Saez

Function : Author

CEA-Direction des Energies (ex-Direction de l'Energie Nucléaire)

Domains

Nuclear Experiment [nucl-ex] Nuclear Theory [nucl-th]

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https://hal-cea.archives-ouvertes.fr/cea-02339667

Submitted on : Wednesday, October 30, 2019-3:06:08 PM

Last modification on : Wednesday, August 24, 2022-2:45:54 PM

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cea-02339667 , version 1 (30-10-2019)

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HAL Id : cea-02339667 , version 1
DOI : 10.1016/j.nucengdes.2019.02.015

Cite

A. Bachrata, L. Trotignon, P. Sciora, M. Saez. A three-dimensional neutronics - thermohydraulics Unprotected Loss Of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices. Nuclear Engineering and Design, 2018, ⟨10.1016/j.nucengdes.2019.02.015⟩. ⟨cea-02339667⟩

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A three-dimensional neutronics - thermohydraulics Unprotected Loss Of Flow simulation in Sodium-cooled Fast Reactor with mitigation devices

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