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)O 2 , (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.
|Journal||Journal of Physics: Conference Series|
|Publication status||Published - 16 Apr 2019|
|Event||7th International Scientific School-Conference of Young Scientists on Modern Problems of Physics and Technologies, MPPT 2018 - Moscow, Russian Federation|
Duration: 16 Apr 2018 → 21 Apr 2018
ASJC Scopus subject areas
- Physics and Astronomy(all)