A temperature chart and formulas useful with the USASI B31.7 code for thermal stress in nuclear power piping
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A chart and formulas give values of ΔT1,max, ΔT2, and NFo as functions of NBi for the case of sudden change in temperature of fluid flowing in a thin wall insulated pipe. These results are useful in designing according to the USAS B31.7 Code for Nuclear Power Piping. The procedure outlined is suitable at high values of heat transfer coefficient, as obtained with liquid metal-cooled and pressurized water reactors.
The article of record as published may be found at http://dx.doi.org/10.1016/0029-5493(69)90007-7
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