1. Study of the research in the nuclear reactor pressure vessel field,1970
2. Degraded Piping Program — Phase II Semiannual Report;Wilkowski;NUREG/CR-4082 BMI 2120,1986
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4. Ductile fracture behaviour of circumferentially cracked Type 304 stainless steel piping under bending load;Shibata;Nucl. Engrg. Des.,1986
5. Tests on bursting vessels with effects on the crack postulate of primary circuit piping systems for light water reactors;Kussmaul;GRS-45,1982