Abstract
In this paper, we present the results of studies of the physics of a high-temperature gas-cooled thorium reactor facility of low power operating in the long-term operation mode. Carried out a comparative neutron-physical calculation of promising fuel compounds ((Th,Pu)O2, (Th,Pu)N, (Th,Pu)C), which can be included (dispersed) into the matrix of the fuel compact of the reactor under investigation. It has been established that the use of (Th, Pu) C-fuel will increase the burn-up of heavy metal by 5%, reduce the accumulation of fission products and CO, increase the service life of fuel.
Sign-in/Register to access full text options 
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
