Rostechnadzor Expert Council on Validation of Computer Codes certified 6 computer codes

12.09.2013 On September 12, 2013 SEC NRS held a scheduled 61st meeting of the Rostechnadzor Expert Council on Validation of Computer Codes. The Council considered the findings of the review of 8 computer codes and made a positive decision to approve their validation certificates. The following computer codes were validated for a 10-year period:

- Computer code “Danco+Гепард (translated as Cheetah)” intended to solve tasks at multiprocessor computers to determine the stress-strain behavior of elements of the complex space structures with the account of material non-linear behavior and contact interaction under intensive mechanical and thermal loads (the review was carried out in Session No. 4 of the Council “Calculations of the stress-strain behavior and strength analysis for reactor core elements, equipment and pipelines of nuclear facilities”);

- Computer code “SADCO” intended for calculation of neutronic characteristics of RBMK reactors (the review was carried out in Session No. 1 of the Council “Neutronic Calculations”);

- Computer code “TFR VVR-M” intended for calculation of VVR-M reactor cores in a steady-state mode of the reactor (the review was carried out in Session No. 2 of the Council “Calculation of heat transfer and hydrodynamics, correlated neutronic and thermohydraulic computations, modeling of non-steady and emergency processes”);

- Computer code “GAMBIT-06” intended for calculation of thermohydraulic characteristics of unbranched hydraulic systems and heat-exchange equipment, operating in steady-state mode (the review was carried out in Session No. 2 of the Council);

- Computer code “ADAMS” intended for calculation of loads, accelerations, velocities, movings, frequencies in the problems of statics, kinematics, dynamics, as well as modal analysis of the elements of mechanical systems in a plane and dimensional positioning (the review was carried out in Session No. 4 of the Council);

- Computer code “MCU-TR” intended for precise calculations of neutronic characteristics of cores of light-water reactors for transport purposes and extra accuracy design calculations for critical assemblies, cells of fuel assemblies, storages for nuclear fuel or fragments thereof on the basis of the Monte Carlo method with the account of changes in isotopic composition (the review was carried out in Session No. 1 of the Council);

- Computer code “MCNP” applied for calculations of neutronic characteristics of fast neutron reactors and their models, in particular, for computer estimate of a multiplication factor for various configurations of the BN-800 reactor core using plutonium or mixed MOX-fuel (the review was carried out in Session No. 1 of the Council);

- Computer code “ДОЗА (translated as DOSE)” intended for calculation of mean annual dose rates for public in the region of a NPP location, conditioned by continuous gas-aerosol emission and liquid discharges to the surface waters from the NPP, and public exposure due to short-term emergency emissions of radioactive wastes into the atmosphere (the review was carried out in Session No. 3 of the Council “Calculations for radiation protection and radiation safety”).