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Empirical Intensity of PWR (Pressurized Water Reactor) Primary Coolant Pumps Failure and Repair.

机译:压水堆(加压水反应堆)主冷却剂泵故障及修复的经验强度。

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The wealth of operating experience concerning PWR type and nuclear reactors that has been regularly monitored and systematically processes since 1971, enabled an analysis of the PWR primary coolant pumps operation. Failure intensity (alpha) and repair intensity (mu) of the pump during its working life were calculated, as these values are necessary in order to determine the reliability and availability of the pump as the basis for analyzing its effect on the safety and efficiency of the nuclear power plant. The trend of failure intensity (alpha) follows the theoretically expected changes in (alpha) over time, and this is around 10(sup -5) in the majority of life-time. Repair intensity (mu) indicates a slow rise during life-time, i.e. its faster return to operation. (author).7 refs.; 5 figs. (Atomindex citation 20:049351)

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