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

JOURNAL: , , p. 77-85

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. (In Russian).


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