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Kaluga Region, Russian Federation Russian Federation

Department Head. Reactor Development & Design Department.

Education

• Calculates self-shielded multigroup cross sections from different evaluated nuclear data libraries and produce multigroup libraries in traditional MATXS format using the NJOY code. • Calculate shielded multigroup cross sections using TRANSX code. • Also we can produce MCNP libraries in ACE-format using the NJOY code, generate input MCNP files and perform calculations. • Besides this we have our own code for isotope kinetics, which uses reaction rates generated by MCNP and very interested in its testing on special benchmarks. • The feature of this code is to obtain assessments of nuclear concentration uncertainties in isotope kinetics calculations by interval calculation method a