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High performance Monte Carlo reactor core analysis (HPMC)
Date du début: 1 oct. 2011, Date de fin: 30 sept. 2014,
"Design and safety analysis of nuclear reactors is based on extensive use of computer codes for the coupled calculation of time-dependend neutron transport, thermal-hydraulics and burnup.State-of-the-art methods use deterministic techniques to solve the neutronics equations, which require various approximations for a full core:a limited number of energy groups, application of diffusion theory inst ...
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