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Home Archive of journals 2 (3), june 2018 Capabilities code TRACT to solve problems of characterization radioactive waste and spent fuel

CAPABILITIES CODE TRACT TO SOLVE PROBLEMS OF CHARACTERIZATION RADIOACTIVE WASTE AND SPENT FUEL

JOURNAL: 2018, 3, p. 95-104

AUTHOR: A.I. Blokhin, P.A. Blokhin, I.V. Sipachev

ANNOTATION:

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.


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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


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