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 |
|---|---|
| Pages (from-to) | 340-350 |
| Number of pages | 11 |
| Journal | Nuclear Engineering and Technology |
| Volume | 47 |
| Issue number | 3 |
| DOIs | |
| Publication status | Published - 2015 |
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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
Cite this
Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads. / Kim, Ji Su; Lee, Han Sang; Kim, Jong Sung; Kim, Yun-Jae; Kim, Jin Won.
In: Nuclear Engineering and Technology, Vol. 47, No. 3, 2015, p. 340-350.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads
AU - Kim, Ji Su
AU - Lee, Han Sang
AU - Kim, Jong Sung
AU - Kim, Yun-Jae
AU - Kim, Jin Won
PY - 2015
Y1 - 2015
N2 - 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.
AB - 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.
KW - Components
KW - Damage initiation model
KW - Finite element analysis
KW - Level D service loads
KW - Plastic instability
KW - Safety class 1 nuclear
KW - Strain-based acceptance criteria
UR - http://www.scopus.com/inward/record.url?scp=84928613355&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=84928613355&partnerID=8YFLogxK
U2 - 10.1016/j.net.2014.12.016
DO - 10.1016/j.net.2014.12.016
M3 - Article
AN - SCOPUS:84928613355
VL - 47
SP - 340
EP - 350
JO - Nuclear Engineering and Technology
JF - Nuclear Engineering and Technology
SN - 1738-5733
IS - 3
ER -