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COBRA Thermohydraulic Code

COBRA thermohydraulic code for flow and heat transfer analysis in nuclear reactor fuel assemblies. Includes flow channel modeling, temperature and pressure calculations, safety analysis and design optimization for PWR and BWR reactors

About COBRA Thermohydraulic Code Category

COBRA thermohydraulic code for flow and heat transfer analysis in nuclear reactor fuel assemblies. Includes flow channel modeling, temperature and pressure calculations, safety analysis and design optimization for PWR and BWR reactors

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Pertoyar Academy was established in 2010 with the aim of teaching nuclear codes. With the passage of time, by expanding its field of activity to the fields of basic sciences, today it operates on the four axes of education, consulting, project implementation and support.

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