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Structural integrity assessments of steam generator tubes using the FAD methodology

  • Published:2015-12 Issue: Volume:295 Page:457-467
  • ISSN:0029-5493
  • Container-title:Nuclear Engineering and Design
  • language:en
  • Short-container-title:Nuclear Engineering and Design

Author:

Bergant Marcos A.ORCID,Yawny Alejandro A.,Perez Ipiña Juan E.ORCID

Funder

Argentinean National Atomic Energy Commission

Publisher

Elsevier BV

Reference28 articles.

1. Prediction of crack coalescence of steam generator tubes in nuclear power plants;Abou-Hanna;Nucl. Eng. Des.,2004

2. Fracture Mechanics, Fundamentals and Applications;Anderson,2005

3. Fitness-For-Service,2007

4. Volume 19, Fatigue and Fracture,1997

5. Estimation procedure of J-resistance curves for through wall cracked steam generator tubes;Bergant;Procedia Mater. Sci.,2012

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3. A comparison of the structural integrity of steam generator tubes based on deterministic and probabilistic crack acceptance criteria;Journal of the Brazilian Society of Mechanical Sciences and Engineering;2022-02-07

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