
doi: 10.1007/bf01137996
Heightened reliabiilty requirements for nuclear power reactors require formulation of new critical heat flux recommendations, whose validity is backed by adequate experimental data with correct physical or mathematical models to guarantee internal dataiconsistency. Data error analysis should cover every parameter region and also consider the amount of original experimental material in neighboring regions. Available reconnnendations [1-3] on critical heat fluxes do not completely satisfy these requirements.
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