Analytical and numerical crack growth prediction for a leak-before-break assessment of a nuclear pressure vessel

Extending the safety analysis of a nuclear reactor pressure vessel beyond the requirements of the regulations which were first laid down in the ASME-Code, the behavior of two crack sizes (14-t axial, 34-t circumferential, a2c = 16) in the upper shelf region is analyzed to demonstrate the capability of a reactor pressure vessel for Leak-Before-Break. The postulated load is a monotonic increase of pressure, ending when the crack penetrates through...