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- W2270867397 abstract "The integrity of PWR-I blanket element cladding was tested using a helium leak detector. Its use enabled the detection and rejection of leaking elements prior to insertion into the reactor. This resulted in a considerable reduction in the problems associated with the operation and maintenance of the Pressurized Water Reactor. The low failure rate during service shows that the test methods were satisfactory. (B.O.G.)" @default.
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- W2270867397 title "Helium leak testing fuel rods for the PWR blanket." @default.
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