Potential utilization of SRS uranium with high U-236 content as commercial LWR fuel (Study of neutronic and safety characteristics)

The neutronics and safety characteristics of a PWR core loaded with fuel made from SRS recovered uranium have been analyzed. These results are compared to those of a standard commercial fuel loaded core. For both cases, equilibrium cycle three-dimensional core models have been developed to accurately quantify the fuel cycle penalty factor associated with high U-236 content in SRS derived fuel. A 0.28 wt% over enrichment is required to compensate for each 1.0 wt% of U-236 in SRS derived fuel in order to match the cycle length. Doppler and moderator coefficients have become slightly more negative with the increase in U-236 content along with a slight reduction of control rode worth, boron worth and shutdown margin. These changes will not impact the safety or operation of a commercial nuclear plant. Thus, the feasibility of using SRS recovered uranium in the form of commercial nuclear fuel has been established from the neutronic and safety point of view. The real issue is the radiological problem related to SRS derived fuel and its effect on worker safety