Model for integral codes for calculating containment thermohydraulics in severe accidents at nuclear power plants with a water coolant

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The article describes a model for calculating the containment thermal in severe accidents at nuclear power plants with a water coolant. The model is implemented in the SOCRAT integral code in the form of a CONT_TH module, which allows performing self-consistent calculation of parameters in a VVER reactor plant and a containment during a severe accident. In conjunction with other modules of the SOCRAT code, a realistic calculation of the transfer of radioactive substances to the containment is provided, which is necessary to calculate source term into the environment when justifying the safety of nuclear power plants, including probability safety assessment level 2. With a slight adaptation, the model can be used to calculate the parameters of containment in a water-cooled NPP as part of other integral codes.

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Sobre autores

D. Tomashchik

Nuclear Safety Institute of the Russian Academy of Sciences

Autor responsável pela correspondência
Email: tdyu@ibrae.ac.ru
Rússia, Moscow

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2. Fig. 1. Example of a nodalization scheme for the CONT_TH module.

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3. Fig. 2. Movement of a sprinkler drop.

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4. Fig. 3. Calculation step of the CONT_TH module.

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