FATIGUE LIFE ASSESSMENT OF REACTOR COOLANT SYSTEM COMPONENTS BY USING TRANSFER FUNCTIONS OF INTEGRATED FE MODEL
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference5 articles.
1. Inspection performance with a view to pressure vessel life management
2. On line fatiguemeter: a large experiment in French nuclear plants
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2. Study on stress-based fatigue monitoring methodology for Class 1 nuclear pipe based on the RCC-M code;Nuclear Engineering and Design;2022-12
3. Safety assessment of the small welded pipe system by the test and FEA;International Journal of Pressure Vessels and Piping;2021-12
4. On-line safety monitoring of pressure-retaining equipment in power plants: a review;Health Monitoring of Structural and Biological Systems XII;2018-03-27
5. Numerical study on fluid flow by hydrodynamic loads in reactor internals;Structural Engineering and Mechanics;2014-09-25
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