Neutronic Analysis of SMART Reactor Core for (U-Th)O2 and MOX Fuel Hybrid Configurations

The neutronic behavior of nuclear reactors is being investigated by considering different fuel, cladding, and neutron-moderating materials. In the present manuscript, two different assembly types of SMART small modular reactor with different enrichments and different numbers of IFBA rods are considered, and the effects of mixed heavy/light water moderator, with varying fractions of heavy water during the burnup, on the assembly cycle burnup are investigated. It is observed that, to extend the cycle burnup we have to use a higher fraction of D2O at the Beginning of the Cycle (BOC) whereas it reduces toward the End of the Cycle (EOC). A higher fraction of heavy water causes the neutron spectrum to shift to the resonance region, resulting in a higher capture rate of the fertile materials. This, in turn, causes an increase in the conversion ratio. on the contrary, toward the EOC, by increasing the light water fraction, the neutron spectrum becomes softer. This also causes an increase in the fission rate of fissile materials. Finally, a certain improvement in the cycle burnup is observed. Moreover, by implementing the proposed method on an assembly containing (Th+U)O2 fuel, the UO2 mass saving is calculated.

show abstract

scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.

Contact Info

customersupport@researchsolutions.com

10624 S. Eastern Ave., Ste. A-614

Henderson, NV 89052, USA

This site is protected by reCAPTCHA and the Google Privacy Policy and Terms of Service apply.

Blog Terms and Conditions API Terms Privacy Policy Contact Cookie Preferences Do Not Sell or Share My Personal Information

Made with 💙 for researchers

Part of the Research Solutions Family.

Neutronic Analysis of SMART Reactor Core for (U-Th)O2 and MOX Fuel Hybrid Configurations

Cited by 3 publications

References 21 publications

Evaluating Risks of Multi-unit Nuclear Sites: Insights and Considerations

Evaluating Risks of Multi-unit Nuclear Sites: Insights and Considerations

Evaluation of dynamical behavior of Thorium fueled SMART reactor using lumped parameter dynamic model

Neutronic analysis of mixed H2O/D2O moderated SMART reactor fuel assembly with varying fractions of D2O during the fuel burnup

Contact Info

Product

Resources

About