Neutronics and Thermal-hydraulics Simulation of Generic Pebble-Bed Fluoride-salt-cooled High-temperature Reactor (gFHR)

  Shai Kinast  
Nuclear Research Center Negev

is demonstrated.steady-state calculations, and good agreement between SAM and AGREEanalysis code SAM is used to couple thermal-hydraulics and neutronics fordemonstrates the applicability of the hybrid method to FHRs. The systembenchmark is achieved. The agreement between Serpent-2 and AGREE
ence neutron diffusion code AGREE. A good consistency with the gFHRsection generator, and the cross sections are applied to the finite differ-
model. Monte Carlo code Serpent-2 is employed as a few-group cross
ing stochastic and deterministic codes is developed to simulate the gFHR(gFHR) benchmark. Based on this benchmark, a hybrid method combin-
of FHRs, Kairos Power (LLC) has recently published the generic FHR
nology is relatively immature. To facilitate the design and safety analysisbased on innovative design concepts and materials, hence the current tech-
both research institutes and commercial industries in recent years. It isleading advanced reactor concepts, has been attracting great interest fromThe fluoride-salt-cooled high-temperature reactor (FHR), one of the