Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting

Proceedings of the U.S. Nuclear Regulatory Commission ... Water Reactor Safety Research Information Meeting
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Publisher :
Total Pages : 776
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ISBN-10 : UOM:39015036232612
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Rating : 4/5 (12 Downloads)

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Fatigue crack growth data sets, for pressure vessel and piping steels, in reactor-grade water environment have appeared in various reports and publications sinc