Inderscience Publishers

Safety assessment for the deficient operation data in the gas-cooled nuclear power plants for hydrogen production

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The probabilistic safety assessment (PSA) is investigated in the case of the operational data shortage which is characteristic of the passive system in gas-cooled nuclear power plants (NPPs). Therefore, it is difficult to make a quantification of the PSA. One of the solutions is to compare the passive system and the active system. Using this comparison, one can find the priority of the passive system reliability. For the modelling, the anticipated transient without scram (ATWS) in the very high temperature reactor (VHTR) and the pressurised water reactor (PWR) is used. Finally, this study decides the difference in the reliability between passive and active systems. The propagation is done by the dynamically modified algorithm (DMA), which highlights the information feedback. The result is analysed by the time changes.

Keywords: very high temperature reactors; VHTR; passive reliability; anticipated transient without scram; ATWS; dynamically modified algorithms; DMA; feedback; probabilistic safety assessment; nuclear safety; deficient operation data; gas-cooled NPPs; nuclear power plants; hydrogen production; nuclear energy; nuclear power; nuclear safety; modelling; pressurised water reactors; PWR.

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