Abstract
The simulation of the mass transfer of tritium in the technological media of sodium-cooled fast reactors is studied. The computational model of tritium mass transfer for a three-loop nuclear power system is based on an analysis of the balance of hydrogen and tritium in the first and second loops.
The following are calculated for the BN-600 and Phoenix reactors which are currently in operation: the concentration of hydrogen and tritium in the first two loops, the concentration of tritium in the protective gas and the steam-water medium in the third loop, and the tritium fluxes into the cold traps, the third loop, and the surrounding environment. About ∼2.2 TBq/(GW·yr) tritium flow into the atmosphere through the walls of loops with nominal system parameters, and about 3 TBq/(GW·yr) flows into the third loop. The cold traps in the first and second loops catch about 99% of the tritium produced.
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Translated from Atomnaya Energiya, Vol. 98, No. 3, pp. 175–182, March, 2005.
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Kozlov, F.A., Poplavskii, V.M., Alekseev, V.V. et al. Simulation of Tritium Mass Transfer in a Three-Loop Sodium-Cooled Nuclear Power System. At Energy 98, 163–169 (2005). https://doi.org/10.1007/s10512-005-0187-5
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DOI: https://doi.org/10.1007/s10512-005-0187-5