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Poster communications

Coupling Monte Carlo transport code MCNP and thermohydraulic code TRIO-U for 3D safety analysis. First tests and applications on molten salt reactors

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Poster communications
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http://hal.in2p3.fr/in2p3-00025306
Contributor : Lpsc Bibliotheque <>
Submitted on : Thursday, January 5, 2006 - 5:08:43 PM
Last modification on : Wednesday, September 16, 2020 - 4:08:18 PM

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  • HAL Id : in2p3-00025306, version 1

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LPSC | IPNO | CNRS | IN2P3 | UGA | GEPI

Citation

A. Nuttin, O. Méplan, J. Wilson, F. Perdu. Coupling Monte Carlo transport code MCNP and thermohydraulic code TRIO-U for 3D safety analysis. First tests and applications on molten salt reactors. ENC 2005 - European Nuclear Conference. Nuclear Power for the XXIst Century : From basic research to high-tech industry, Dec 2005, Versailles, France. European Nuclear Society, pp.1, 2005. ⟨in2p3-00025306⟩

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