Ingecid

Source term Cofrentes NPP

Calculation of the source term of a fuel assembly type for the Cofrentes Nuclear Power Plant

Determination of the most conservative gamma, neutron and activation source term for a 10×10 fuel element

Determination of the most conservative gamma, neutron and activation source term for a 10×10 fuel element. The source terms have been calculated using two different methodologies, both from the SCALE package:

  • ORIGEN-ARP
  • TRITON + ORIGEN-S

Using the ORIGEN-ARP methodology, sensitivity studies have been carried out for the presence or not of a control bar and the presence or not of Gd.

Using the TRITON + ORIGEN-S methodology, sensitivity studies have been carried out for the presence or not of a control rod, axial variation of the moderator and burner density, variation of U-235 enrichment in the fuel rods and presence or not of Gd. The results obtained using both methodologies have been compared.

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