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Publikováno v:
OECD/NEA CFD4NRS (Computational Fluid Dynamics for Nuclear Reactor Safety) Workshop, CFD4NRS
OECD/NEA CFD4NRS (Computational Fluid Dynamics for Nuclear Reactor Safety) Workshop CFD4NRS, Nov 2020, SACLAY, France
HAL
OECD/NEA CFD4NRS (Computational Fluid Dynamics for Nuclear Reactor Safety) Workshop CFD4NRS, Nov 2020, SACLAY, France
HAL
International audience; This paper aims at sharing IRSN experiences and perspectives concerning these specific uses of CFD
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::286e47d977453bdd6d8e7ca54bb0112b
https://hal.archives-ouvertes.fr/hal-03098806/document
https://hal.archives-ouvertes.fr/hal-03098806/document
Publikováno v:
Nuclear Engineering and Design 266(2014), 112-128
Nuclear Engineering and Design
Nuclear Engineering and Design, 2014, 266, pp.112-128. ⟨10.1016/j.nucengdes.2013.10.023⟩
Nuclear Engineering and Design
Nuclear Engineering and Design, 2014, 266, pp.112-128. ⟨10.1016/j.nucengdes.2013.10.023⟩
Small Break Loss of Coolant Accident (SB LOCA) is one of the most severe transients which may lead to Pressurized Thermal Shock (PTS) on the Reactor Pressure Vessel (RPV) wall. During postulated SB LOCA Emergency Core Cooling (ECC) water is injected