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NUCLEAR SAFETY INSTITUTE OF THE
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Projects » Ensuring Nuclear and Radiation Safety » Numerical Studies and Software Framework for RW and SNF Management, Decommissioning of Nuclear Hazardous Facilities and Remediation of Territories

NUMERICAL STUDIES AND SOFTWARE FRAMEWORK FOR RW AND SNF MANAGEMENT, DECOMMISSIONING OF NUCLEAR HAZARDOUS FACILITIES AND REMEDIATION OF TERRITORIES


Nuclear Safety institute develops the software framework for numerical safety assessment in the context of radioactive waste disposal and nuclear decommissioning. The goal is to provide an integrated modeling framework taking into account multiple scales, subsystems interactions, and all types of uncertainties. 

Modeling is an essential tool for the safety assessment of radioactive waste disposal facilities. It allows obtaining long-term forecasting results considering the different scenarios of external impacts and the internal evolution of the system. The modeling of the real object always accounts for its specific features. And computational tools for model development are being selected according to a set of requirements on implemented processes, description of parameters, etc.

The software framework consists of:

GeRa code for groundwater flow and transport modeling in the near field and far field;

Radionuclide transport through the engineered barrier system within the RW disposal site boundaries

Development of the groundwater flow and transport model of the geological disposal facility in the GeRa software

 

3D model of the Severny LRW injection site

FENIA code for 3D Thermomechanic modeling;

Simulated temperature field in the radioactive waste repository in 55 years from the beginning of disposal

 

CORIDA code for neutron physics calculations of RW characteristics and dose estimates; 

DESTRUCT methodology modeling the long-term evolution of engineered barrier system;

Structure of the engineering barriers for analysis of the evolution of container materials used for RW disposal

 

"OBOYAN" software and hardware complex

Calculation of the radiological situation at the premises of the nuclear legacy site

Dose rate distribution in the radiation-contaminated building

and MOUSE code for uncertainty quantification, model calibration, and sensitivity analysis.


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