Fracture mechanics evaluation of the Trino reactor vessel

1975 
Results are presented of the fracture toughness testing of the Trino pressure vessel, and the data are discussed in light of current US regulatory rules. This includes generation of heatup and cooldown curves based on the method of Appendix G of the Summer 1972 Addendum to Section III ASME Code. In addition, a fracture mechanics analysis was performed to demonstrate the integrity of the Trino reactor vessel. The analysis included a fatigue analysis utilizing fracture mechanics parameters, and the determination of critical flaw sizes for design (normal, upset, test) transients and a postulated accident (LOCA) condition. (auth)
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