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Thermal-hydraulics aspect is one of the crucial aspects that must be considered when reactor design and operation analysis were performed, because this aspect involves security, safety, and efficiency factor that must have to be examined. In this study, thermal-hydraulics aspect of the HTR-10MW (which classified into Pebble-Bed Reactor or PBR) were analyzed by reviewing the fast neutron irradiation influence using the modified PEBBLE program (or mPEBBLE), this program using finite-difference numerical method for solving the differential equation of the system. In reviewing fast neutron irradiation, the thermal conductivity value of fuel is induced by fast neutron irradiation dose. The study concludes that fast neutron can influence the fuel thermal conductivity. The value of fuel thermal conductivity can induce the thermal-hydraulics aspect of PBR core which is so important to be understanding more the safety ability of PBR core.