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NUCLEAR SAFETY INSTITUTE OF THE
RUSSIAN ACADEMY OF SCIENCES
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Research » Development of methods and tools for calculated studies of NPP safety » Research in the field of software development for justification of safety of NPP with liquid metal coolant reactor units » New Generation Computer Codes
NEW GENERATION COMPUTER CODES
- HYDRA-IBRAE/LM thermohydravlics computer code for fast neutrons reactors
- DNS code CONV-3D
- CORNER
- BERKUT
- Integrated computer code EVKLID
- SOKRAT-BN code for fast neutrons reactors
- GeRa
- Sibilla
- ROM
- 3D code ROUZ
- ODETTA
- BPS
- DOLCE VITA
- Experimental research
Теги: Gera ГеРа гидрогеологическое моделирование код перенос радионуклидов подземные воды Расчетный код Расчетный код Gera фильтрация
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