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- W3206132912 abstract "Design and operation of nuclear reactor is very difficult issue from the engineering and technical point of view. All facilities must be availably designed separately, but with respect to other facilities working in the same system too. In nuclear power plant the key safety factor is the insurance of nuclear fuel assemblies cooling. The basic requirement from this point of view is an pressure loss coefficient assessment for all possible modes of coolant flow. This article describes an experience with measurement of pressure loss coefficient characteristics in Škoda JS." @default.
- W3206132912 created "2021-10-25" @default.
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- W3206132912 date "2021-01-01" @default.
- W3206132912 modified "2023-09-25" @default.
- W3206132912 title "Measurement of pressure loss coefficient for nuclear fuel assembly" @default.
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- W3206132912 doi "https://doi.org/10.1051/matecconf/202134500023" @default.
- W3206132912 hasPublicationYear "2021" @default.
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