Engineering estimates of crack opening displacement for non-idealized circumferential through-wall cracks in pipe

Author:

Cho Doo-Ho,Shin An-Dong,Huh Nam-Su,Jeon Hyun-Ik

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference27 articles.

1. USNRC, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition. USNRC, Section 3.6.3; NUREG-0800, 1987.

2. USNRC, Special Meeting on Leak Before Break in Reactor Piping and Vessels, NUREG/CP-0155, 1997.

3. Wilowski G, Schmidt R, Scott P, Olson R, Marschall C, Kramer G, et al. International Piping Integrity Research Group (IPIRG) Program – Final report, NUREG/CR-6233, USNRC, 1997.

4. Hopper A, Wilowski G, Scott P, Olson R, Rudland D, Lilinski T, et al. The Second International Piping Integrity Research Group(IPIRG-2) Program – Final report, NUREG/CR-6452, USNRC, 1997.

5. Ductile fracture handbook;Zahoor;Novetech Corp,1991

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