CAPABILITIES OF TRACT CODE TO RESOLVE THE PROBLEMS OF RADIOACTIVE

The paper presents the calculation capabilities of the nuclide kinetics code TRACT, its verification on the basis of test experiments on the heat release of fission products. For the VVER-440 reactor radiation characteristics of spent fuel and radioactive waste were analyzed for cooling times up to 10000 years.

Keywords: isotope kinetics, code TRACT, verification, decay heat, spent fuel, radioactive waste, gamma-radiation, VVER-440.

Blokhin A. I., Blokhin P. A., Sipachev I. V. Capabilities code TRACT to solve problems of characterization radioactive waste and spent fuel. Radioactive Waste, 2018, no. 2 (3), pp. 95—104. (In Russian).