- MELCOR
- код для анализа тяжёлых аварий с расплавлением активной зоны ядерного реактора
Англо-русский словарь технических аббревиатур. 2011.
Англо-русский словарь технических аббревиатур. 2011.
MELCOR — is a nuclear engineering computer code that can model the progression of accidents in nuclear reactors. It is sometimes, though incorrectly, said to be an acronym of Methods for Estimation of Leakages and Consequences of Releases. It can also be… … Wikipedia
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Monte Carlo N-Particle Transport Code — (MCNP) is a software package for simulating nuclear processes. It is developed by Los Alamos National Laboratory and is distributed within the United States by the Radiation Safety Information Computational Center in Oak Ridge, TN and… … Wikipedia
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код для анализа тяжёлых аварий с расплавлением активной зоны ядерного реактора — — [А.С.Гольдберг. Англо русский энергетический словарь. 2006 г.] Тематики энергетика в целом EN MELCOR … Справочник технического переводчика