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Enhancing Nuclear Safety


Research

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Status of the qualification program of the multiphase flow code MC3D

R. MEIGNEN
ICAPP'05, Seoul, Korea, May 15-19, 2005
Rapport IRSN-DSR/64

Document type > *Report/contribution to WG (paper or CD-Rom), *Congrès/colloque

Keywords > MC3D (code), thermohydraulics

Research Unit > IRSN/DSR/SAGR

Authors > MEIGNEN Renaud

Publication Date > 30/05/2005

Summary

MC3D is a thermal-hydraulic multiphase flow code devoted to nuclear safety applications, developed by the IRSN and the CEA. It is mainly applied to the study of Fuel-Coolant-Interactions (FCI), its potentials in nuclear power plants. We provide a general presentation of MC3D, its capabilities and the status of its ongoing program of qualification. Developed since more than ten years, MC3D is now a code with very extended capabilities and functionalities. An important program of qualification has been engaged since two years to evaluate the initial choices for the numerical aspects, for the basic constitutive laws and to check in-depth the code capabilities. This program starts with a new evaluation of the numerical aspects (phase 0), continues with the basic diphasic and triphasic aspects (phase 1, underway) and finishes with the application-specific aspects (phase 2, to be started in 2006). We present the most important results of the program, and also some examples of global validation calculations for FCI and of applications to nuclear safety.
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