Abstract
This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the overconservatism of the stress-based acceptance criteria, which often occurs for level D service loads.
Original language | English |
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Pages (from-to) | 340-350 |
Number of pages | 11 |
Journal | Nuclear Engineering and Technology |
Volume | 47 |
Issue number | 3 |
DOIs | |
Publication status | Published - 2015 |
Bibliographical note
Funding Information:This work has been supported by NRF (2011-0018948) and NRF (2013M2A8A 1040924), which are funded by MEST (Ministry of Education, Science, and Technology) and MSICTFP (Ministry of Science, ICT and Future Planning) .
Publisher Copyright:
© 2015, Published by Elsevier Korea LLC on behalf of Korean Nuclear Society.
Keywords
- Components
- Damage initiation model
- Finite element analysis
- Level D service loads
- Plastic instability
- Safety class 1 nuclear
- Strain-based acceptance criteria
ASJC Scopus subject areas
- Nuclear Energy and Engineering