EDN: VTXTOO
Authors & Affiliations
Alekseev V.V., Sorokin A.P., Kuzina Yu.A.
A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Alekseev V.V. – Chief Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, 249033. Tel.: +7 (484) 399-42-34; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Sorokin A.P. – Chief Researcher, Dr. Sci. (Tech.).
Kuzina Yu.A. – Head of division Nuclear Power, Cand. Sci. (Tech.).
Abstract
An analysis of the main patterns of tritium transfer in the sodium circuits of fast reactors is presented. Data are presented on the distribution of tritium in the circuits of nuclear power plants, its entry into the third circuit and the environment, and its accumulation in cold traps. The results of calculations for the BN-350, BN-600, BN-1200, MBIR installations are presented. The results of an experimental study of tritium mass transfer in a circulating sodium circuit are presented. Measurements were carried out of the tritium content in sodium and argon of the gas cavity of the sodium circuit and the permeability of tritium through structural materials. In the gas cavity of the sodium circuit, the increased hydrogen content leads to an increase in the supply of tritium from sodium and an increase in its concentration in the protective gas. The temperature dependence of the permeability constant of tritium through an Armco-iron membrane is in good agreement with the data of other authors.
Keywords
sodium coolant, tritium, hydrogen, argon, shielding gas, temperature, cold trap, mass transfer, concentration, permeability of hydrogen isotopes
Article Text (PDF, in Russian)
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UDC 621.039.534
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 1, 1:7
