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- W45955847 abstract "This is the final report of EPRI Research Program RP 2180-3 performed for EPRI by Combustion Engineering, Inc. (C-E), Windsor, CT. A compact fracture test specimen was developed, and tests were performed to study crack propagation from an initial fatigue precrack in chilled reactor vessel grade steel, to arrest in warmer material of increasing toughness and rising stress intensity. The conditions necessary for crack arrest in high stress, high toughness conditions were determined by correlation of the test results to computer analyses. A simplified computer code was written which reproduces the test results. The specimens were manufactured from unirradiated nuclear reactor vessel grade steel, and the loads and toughness gradients in the tests simulated pressure and thermal loadings analogous to postulated pressurized thermal shock (PTS) conditions in irradiated vessels. Comparison of detailed dynamic elastic plastic finite element analyses and dynamic strain and displacement measurements of the crack extension, arrest and reinitiation events have led to a new understanding of the crack extension and arrest process. This understanding is shown to be applicable to the extension and arrest of cracks in pressure vessels and structures in general." @default.
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- W45955847 date "1987-04-01" @default.
- W45955847 modified "2023-09-23" @default.
- W45955847 title "Tests and analyses of crack arrest in reactor vessel materials: Final report" @default.
- W45955847 hasPublicationYear "1987" @default.
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