Preliminary reactor safety analyses were performed for the Pu-burner HTGR (High Temperature Gas-cooled Reactor) to investigate plutonium fuel influence on reactor thermal and kinetic behavior for the depressurization accident which is design base accident, and the depressurization accident without scram, which is beyond design base accident. The analytical results of depressurization accident show that the reactor thermal power is restricted lower than the reference reactor with uranium fuel, because the core width is wider for better Pu-burning performance. The analytical results of depressurization accident without scram show that the re-criticality is delayed compare to the reference reactor with uranium-fueled core, due to its temperature reactivity coefficient. The delay of re-criticality brings that operators have more margins for accident management, for example, manual insertion of shutdown devices to the reactor core.

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