This book provides a comprehensive exploration of how fracture mechanics is applied to solve problems specific to the nuclear industry. It delves into key principles, such as evaluating load capacity, predicting component lifetime, and establishing inspection intervals for cracked materials. The content covers essential topics, including linear-elastic and elastic-plastic fracture mechanics, material properties, crack initiation, fatigue, and stress corrosion cracking. With a focus on practical applications, the book addresses critical components like reactor vessel, turbine disks, and steam generator tubes, offering valuable insights for professionals in design, material selection, manufacturing, and inspection within nuclear power plants, as well as serving as a useful resource for students in related engineering courses
1. OBJECTIVE AND HISTORY.-
2. FAILURES BY FRACTURE IN THE INDUSTRY.-
3.
LINEAR-ELASTIC FRACTURE MECHANICS.-
4. MATERIAL PROPERTIES FOR FRACTURE.-
5.
CRACK INITIATION AND PROPAGATION.-
6. CRACK GROWTH BY FATIGUE AND STRESS
CORROSION CRACKING.-
7. ELASTIC-PLASTIC FRACTURE MECHANICS.-
8. COMPONENTS
DESIGN AGAINST BRITTLE FRACTURE.-
9. REACTOR VESSEL STRUCTURAL INTEGRITY.-
10. STRESS CORROSION CRACKING IN TURBINE DISKS.-
11. FATIGUE ANALYSIS OF
THE REACTOR VESSEL.-
12. STRESS CORROSION CRACKING IN REACTOR VESSEL HEAD
PENETRATIONS.-
13. LEAK-BEFORE-BREAK APPLICATION TO PIPING.-
14. STEAM
GENERATOR TUBE INTEGRITY.
José Eduardo Maneschy is a mechanical engineer and has a Ph.D. degree from Universidade de São Paulo/IPEN. He worked in Eletronuclear, the Brazilian nuclear energy utility, for almost 35 years. He has over 40 years of experience in stress analyses, fracture mechanics, fatigue, structural integrity, and aging management applied to piping and mechanical components of nuclear power plants. He has been a Westinghouse contractor since 2016, initially as part the team responsible for the Angra 1 life extension of operation project and then, starting in 2024, as a member of the group involved in fatigue and aging management for the U.S. nuclear plants.
Carlos Alexandre de J. Miranda is a civil engineer and has a Ph.D. degree from Universidade de São Paulo/IPEN. He has been on the Brazilian nuclear safety board for over 40 years, mainly at the Institute of Energy and Nuclear Research (IPEN-CNEN/SP). He has experience in stress analysis, finite elements, fracture mechanics, and structural integrity of piping and mechanical components of nuclear power plants. He also is a professor for undergraduate and graduate courses at Universidade de São Paulo/IPEN.
