Prediction of crack coalescence of steam generator tubes in nuclear power plants-Reference-Cited by-同舟云学术

Prediction of crack coalescence of steam generator tubes in nuclear power plants

Published:2004-04 Issue:2-3 Volume:229 Page:175-187
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Abou-Hanna Jeries,McGreevy Timothy E,Majumdar Saurin

Publisher

Elsevier BV

Reference10 articles.

1. Alzheimer, J.M., Clark, R.A., Morris, C.J., Vagins, M., 1979. Steam Generator Tube Integrity Program Phase I Report, NUREG/CR-0718, PNL-2937, Richland, WA.

2. Analysis and testing of rupture of steam generator tubing with flaws, 2001. In: The 10th International Conference on Fracture (ICF-10), December 3–7, 2001, Honolulu, Hawaii.

3. Cochet, B., Flesch, B., 1987. Crack stability criteria in steam generator tubes. In: Proceedings of Ninth International Conference on SMiRT, vol. D, pp. 413–419.

4. Eiber, R.J., Maxey, W.A., Duffy, A.R., Atterbury, T.J., 1971. Investigation of the Initiation and Extent of Ductile Pipe Rupture, BMI-1908, Battelle Memorial Institute.

5. Ductile fracture theories for pressurised pipes and containers

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