Low-power lead-cooled fast reactor loaded with MOX-fuel

International Conference for Young Scientists, Specialists, and Postgraduates on Nuclear Reactor Physics 2016

Sitdikov, E.R.^1 ; Terekhova, A.M.^1

Obninsk Institute for Nuclear Power Engineering, NRNU, MEPhI, 1 Studgorodok, Kaluga Region, Obninsk

249030, Russia^1

关键词: Delayed neutrons;    Effective fractions;    Hard neutron spectrum;    Innovative fast reactors;    Lead coolant;    Monte Carlo codes;    Prompt neutrons;    Research center;   

Others  :  https://iopscience.iop.org/article/10.1088/1742-6596/781/1/012007/pdf
DOI  :  10.1088/1742-6596/781/1/012007

来源: IOP

【 摘 要 】

Fast reactor for the purpose of implementation of research, education of undergraduate and doctoral students in handling innovative fast reactors and training specialists for atomic research centers and nuclear power plants (BRUTs) was considered. Hard neutron spectrum achieved in the fast reactor with compact core and lead coolant. Possibility of prompt neutron runaway of the reactor is excluded due to the low reactivity margin which is less than the effective fraction of delayed neutrons. The possibility of using MOX fuel in the BRUTs reactor was examined. The effect of Keffgrowth connected with replacement of natural lead coolant to 208Pb coolant was evaluated. The calculations and reactor core model were performed using the Serpent Monte Carlo code.