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.
Do you want to know more about INGECID’s capabilities in Radiological Engineering and/or Project Management?Access here
