Abstract
In this paper, a chloride-induced stress-corrosion-cracking (CISCC) test method for spent nuclear-fuel-storage canisters is presented. The developed tester is easy to use with a standard compact-tension (C(T)) specimen and the load is applied by a constant displacement. The experiment is not only accelerated since the specimen is immersed, but the signal stability also increases, because the load cell is separated from the chloride environment. The experiment was performed for 28 days with two specimens manufactured using austenitic stainless steel 304. As results, relaxed loads were 4,382.2 and 3,980.8 N and crack-growth lengths were 1.41E-4 and 1.77E-4 m respectively. From this data, stress-intensity factors were calculated as 40.0 and 41.8 MPa m using the relaxed loads. Therefore, a new test method for evaluating defects by CISCC using the developed tester is suggested based on the experimental results.
| Original language | English |
|---|---|
| Pages (from-to) | 401-408 |
| Number of pages | 8 |
| Journal | Transactions of the Korean Society of Mechanical Engineers, A |
| Volume | 43 |
| Issue number | 6 |
| DOIs | |
| Publication status | Published - 2019 Jan 1 |
| Externally published | Yes |
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Keywords
- Austenitic Stainless Steel
- Chloride Induced Stress Corrosion Cracking
- Spent Nuclear Fuel Canister
- Stress Intensity Factor
ASJC Scopus subject areas
- Mechanical Engineering
Cite this
Development of chloride induced stress corrosion cracking test method for austenitic stainless steel using C(T) specimen. / Jeong, Jae Yoon; Lee, Myeong Woo; Kim, Yun Jae.
In: Transactions of the Korean Society of Mechanical Engineers, A, Vol. 43, No. 6, 01.01.2019, p. 401-408.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Development of chloride induced stress corrosion cracking test method for austenitic stainless steel using C(T) specimen
AU - Jeong, Jae Yoon
AU - Lee, Myeong Woo
AU - Kim, Yun Jae
PY - 2019/1/1
Y1 - 2019/1/1
N2 - In this paper, a chloride-induced stress-corrosion-cracking (CISCC) test method for spent nuclear-fuel-storage canisters is presented. The developed tester is easy to use with a standard compact-tension (C(T)) specimen and the load is applied by a constant displacement. The experiment is not only accelerated since the specimen is immersed, but the signal stability also increases, because the load cell is separated from the chloride environment. The experiment was performed for 28 days with two specimens manufactured using austenitic stainless steel 304. As results, relaxed loads were 4,382.2 and 3,980.8 N and crack-growth lengths were 1.41E-4 and 1.77E-4 m respectively. From this data, stress-intensity factors were calculated as 40.0 and 41.8 MPa m using the relaxed loads. Therefore, a new test method for evaluating defects by CISCC using the developed tester is suggested based on the experimental results.
AB - In this paper, a chloride-induced stress-corrosion-cracking (CISCC) test method for spent nuclear-fuel-storage canisters is presented. The developed tester is easy to use with a standard compact-tension (C(T)) specimen and the load is applied by a constant displacement. The experiment is not only accelerated since the specimen is immersed, but the signal stability also increases, because the load cell is separated from the chloride environment. The experiment was performed for 28 days with two specimens manufactured using austenitic stainless steel 304. As results, relaxed loads were 4,382.2 and 3,980.8 N and crack-growth lengths were 1.41E-4 and 1.77E-4 m respectively. From this data, stress-intensity factors were calculated as 40.0 and 41.8 MPa m using the relaxed loads. Therefore, a new test method for evaluating defects by CISCC using the developed tester is suggested based on the experimental results.
KW - Austenitic Stainless Steel
KW - Chloride Induced Stress Corrosion Cracking
KW - Spent Nuclear Fuel Canister
KW - Stress Intensity Factor
UR - http://www.scopus.com/inward/record.url?scp=85069737887&partnerID=8YFLogxK
UR - http://www.scopus.com/inward/citedby.url?scp=85069737887&partnerID=8YFLogxK
U2 - 10.3795/KSME-A.2019.43.6.401
DO - 10.3795/KSME-A.2019.43.6.401
M3 - Article
AN - SCOPUS:85069737887
VL - 43
SP - 401
EP - 408
JO - Transactions of the Korean Society of Mechanical Engineers, A
JF - Transactions of the Korean Society of Mechanical Engineers, A
SN - 1226-4873
IS - 6
ER -