Fracture probability and leak before break analysis for the cold neutron source moderator vessel

Fracture mechanics calculations are made to ensure the safety of the moderator vessel against failure by fracture. The 6061-T6 aluminum alloy is used for the moderator vessel structure. The fracture analysis of the moderator vessel consists of: (1) the probability of fracture calculations at the locations of the moderator where either the primary stress or the secondary stress assumes the highest value, (2) the vessel wall leak-before-break analysis by applying an edge crack solution, and (3) the crack penetration calculation as a result of radiation embrittlement by applying the flaw assessment diagram (FAD). The probability of fracture for the capsule is calculated by using a direct probability integration method instead of the Monte Carlo simulation method used by the PRAISE Code or the FAVOR Code developed in Oak Ridge. The probability of fracture as a function of radiation embrittlement is obtained. The leak before break analysis indicates that the vessel will fail by leak before fail by catastrophic fracture. A mass spectrometer will be installed to monitor the leak of hydrogen circulating within the moderator