Authors & Affiliations

Tykleeva K.V., Zabrodskaya S.V., Popov E.P., Tsikunov A.G.
A.I. Leypunsky Institute for Physics and Power, Obninsk, Russia


In this work the production of radionuclide tritium in technological environments of fast reactor with MOX and nitrogen fuel during normal operation is studied. In the work the major sources of production tritium are defined in these fuels, as well as in the coolant and steel constructions. The analysis of modern nuclear data used in the calculation of the rate of production of tritium was performed. The method of calculating the production rate of tritium in materials of fast reactors is presented.

Key words
tritium generation, fast reactor, sodium coolant, MOX fuel, MNUP fuel

Article Text (PDF, in Russan)


UDC 621.039.54:519.85

Problems of Atomic Science and Technology. Series: Nuclear Constants, issue 2:3, 2015