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- W1543208563 abstract "Abstract : A near approach to absolute fracture safety in boiling water (BW) and pressurized water (PW) nuclear reactor pressure vessels requires a very conservative fracture control plan. Such a plan must assume that any plausible cracklike defect, which has not been proved absent by inspection, may exist in the vessel. Requirements for design, materials, and inspection may then be established in a conservative way relative to estimates of progressive crack extension behavior. These estimates are assisted by elastic and plastic methods of analysis of cracks in tension. Approximate methods of assigning K sub Lc values to measurements of crack toughness in terms of a brittle-ductile transition temperature are valuable in reviewing methods of fracture control which have received trial in the past, such as the NRL fracture analysis diagram and the leak-before-break toughness criterion." @default.
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- W1543208563 date "1967-11-21" @default.
- W1543208563 modified "2023-09-27" @default.
- W1543208563 title "BASIC ASPECTS OF CRACK GROWTH AND FRACTURE" @default.
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