In this paper, fatigue assessment of Class 1 nuclear power piping according to ASME Boiler and Pressure Vessel Code, Section III, NB-3600, is discussed. Key parameters involved in the fatigue assessment, i.e. the alternating stress intensity Salt, the penalty factor Ke and the cumulative damage factor U, are addressed. In particular, a so-called simplified elastic-plastic discontinuity analysis for alternative verification when basic fatigue requirements found unsatisfactory, and the procedures for evaluating the alternating stress intensity Salt, is reviewed. Factors that can significantly affect the reliability and accuracy of the fatigue assessment are examined. It is illustrated that there is a great need of other alternatives to this simplified elastic-plastic analysis procedure. An alternative based on non-linear finite element analysis is suggested. This paper is a continuation of our work presented in ICONE16-21, which attempted to categorize design rules in the code into linear and non-linear rules and to clarify corresponding requirements that can be used in combination with non-linear finite element analysis.
Skip Nav Destination
2014 22nd International Conference on Nuclear Engineering
July 7–11, 2014
Prague, Czech Republic
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4589-9
PROCEEDINGS PAPER
Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives? Available to Purchase
Lennart G. Jansson
Lennart G. Jansson
ÅF-Industry AB, Göteborg, Sweden
Search for other works by this author on:
Lingfu Zeng
ÅF-Industry AB, Göteborg, Sweden
Lennart G. Jansson
ÅF-Industry AB, Göteborg, Sweden
Paper No:
ICONE22-31074, V001T07A016; 11 pages
Published Online:
November 17, 2014
Citation
Zeng, L, & Jansson, LG. "Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues. Prague, Czech Republic. July 7–11, 2014. V001T07A016. ASME. https://doi.org/10.1115/ICONE22-31074
Download citation file:
26
Views
Related Proceedings Papers
Related Articles
A Methodology for Fatigue Prediction of Electronic Components Under Random Vibration Load
J. Electron. Packag (December,2001)
A Reliability-Based Expression of ASME B&PV Code Equation (11) for Class 2 and 3 Nuclear Pipes
J. Pressure Vessel Technol (October,2010)
A Reliability-Based Approach for Low-Cycle Fatigue Design of Class 2 and 3 Nuclear Piping
J. Pressure Vessel Technol (October,2010)
Related Chapters
Subsection NB—Class 1 Components
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 1, Second Edition
Subsection NB—Class 1 Components
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition
Part 2, Section II—Materials and Specifications
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 1, Third Edition