The neutronic calculations for safety analysis of high-temperature reactors with pebble bed core on the example of HTR-10

This poster presents the verification of the safety characteristics of the pebble bed HTGR (High Temperature Gas-cooled Reactor), using technical data of the experimental Chinese reactor HTR-10. The neutronic calculations were performed with the SCALE/KENO-VI code system developed at Oak Ridge National Laboratory. HTR-10 fuel is composed of a large number of tiny tri-structural-isotropic (TRISO) fuel particles embedded in a graphite matrix and shaped into spherical or cylindrical fuel elements - pebbles. The inherent double heterogeneity of such a fuel makes it more difficult to model and requires methods different from those used for LWR fuel. The following parameters and quantities have been computed: -) dependence of the effective multiplication factor value (k-eff) on the number of pebbles and their temperature, -) power distribution in the core for operational conditions, -) calculation of the temperature coefficient values, and -)calculation of the control rods worth