Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part III: off-center cracks, restraint of bending, thickness transition and weld residual stresses-Reference-Cited by-同舟云学术

Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part III: off-center cracks, restraint of bending, thickness transition and weld residual stresses

Published:1998-04 Issue:5 Volume:75 Page:397-415
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Rahman S.,Ghadiali N.,Wilkowski G.M.,Moberg F.,Brickstad B.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference38 articles.

1. Rahman S, Brust FW, Ghadiali N and Wilkowski G. Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part I: analytical models. International Journal of Pressure Vessels and Piping, 1998;75:357–373.

2. Rahman S, Brust FW, Ghadiali N and Wilkowski G. Crack-opening-area analyses for circumferential through-wall cracks in pipes—Part II: model validations. International Journal of Pressure Vessels and Piping, 1998;75:375–396.

3. Rahman S, Brust F, Ghadiali N, Choi YH, Krishnaswamy P, Moberg F, Brickstad B and Wilkowski G. Refinement and evaluation of crack-opening-area analyses for circumferential through-wall cracks in pipes. NUREG/CR-6300, US Nuclear Regulatory Commission, Washington, D.C., April 1995.

4. Wilkowski GM, Ahmad J, Barnes CR, Brust F, Ghadiali N, Guerrieri D, Jones D, Kramer G, Landow M, Marschall CW, Olson R, Papaspyropoulos V, Pasupathi V, Rosenfeld M, Scott P and Vieth P. Degraded piping program—Phase II: Summary of technical results and their significance to leak-before-break and in-service flaw acceptance criteria. NUREG/CR-4082, vol. 8, US Nuclear Regulatory Commission, Washington, D.C., March 1989.

5. Paul D, Ahmad J, Scott PM, Flanigan LF and Wilkowski G. Evaluation and refinement of leak-rate estimation models. NUREG/CR-5128, Rev. 1, US Nuclear Regulatory Commission, Washington, D.C., June 1994.

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