Formation and distribution of tritium in the primary circuit of vver: numerical simulation

Formation and distribution of tritium in VVER-1000 primary circuit has been simulated for the cases when fuel rod cladding was made of structured materials with different tritium permeability due to its diffusion in metal, namely zirconium alloy E110 and chromium-nickel alloy containing 42% of Cr. The simulation results show that in the last case activity of tritium transferred from nuclear fuel into primary circuit coolant during one cycle of the reactor power operating exceeds 700 TBq. Thus, one can expect that the use of chromium-nickel alloys for fabrication of fuel cladding will increase both gas exhaust and liquid discharge of tritium from the VVER nuclear power plants in a few times.

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