High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure. Issue 3 (4th March 2023)
- Record Type:
- Journal Article
- Title:
- High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure. Issue 3 (4th March 2023)
- Main Title:
- High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure
- Authors:
- Ohtsuka, Satoshi
Shizukawa, Yuta
Tanno, Takashi
Imagawa, Yuya
Hashidate, Ryuta
Yano, Yasuhide
Onizawa, Takashi
Kaito, Takeji
Ohnuma, Masato
Mitsuhara, Masatoshi
Nakashima, Hideharu - Abstract:
- ABSTRACT: The Japan Atomic Energy Agency (JAEA) has been developing 9Cr-oxide dispersion strengthened (ODS) tempered martensitic steel (TMS) as a candidate material for use in the fuel cladding tubes of sodium-cooled fast reactors (SFRs). The creep property is essential for the fuel cladding tube of SFR; the reliable prediction of in-reactor creep-rupture strength is critical for implementing the 9Cr-ODS TMS cladding tube in the SFR. This study investigated the quantitative correlation between the creep properties of 9Cr-ODS TMS at 700°C and the dispersions of nanosized oxides by analyzing the creep data and the material's nanostructure. The possibility of deriving a formula for estimating the in-reactor creep properties of 9Cr-ODS TMSs based on an analysis of the nanostructure of neutron-irradiated 9Cr-ODS TMSs was also discussed. The creep properties of 9Cr-ODS TMS at 700°C closely correlated with the dispersion of nanosized oxide particles. The correlation between creep-rupture lives and nanosized oxide particle dispersion in 9Cr-ODS TMS was determined using existing creep models. The elucidation of correlation between the stress exponent of secondary creep rate and the nanostructure is essential to enhance future modeling reliability and formulation. Graphical Abstract: uf0001
- Is Part Of:
- Journal of nuclear science and technology. Volume 60:Issue 3(2023)
- Journal:
- Journal of nuclear science and technology
- Issue:
- Volume 60:Issue 3(2023)
- Issue Display:
- Volume 60, Issue 3 (2023)
- Year:
- 2023
- Volume:
- 60
- Issue:
- 3
- Issue Sort Value:
- 2023-0060-0003-0000
- Page Start:
- 288
- Page End:
- 298
- Publication Date:
- 2023-03-04
- Subjects:
- Oxide dispersion strengthened steel -- fuel cladding tube -- creep property -- nanostructure -- accident tolerant fuel
Nuclear engineering -- Periodicals
Nuclear physics -- Periodicals
Nuclear energy -- Periodicals
621.4805 - Journal URLs:
- http://www.tandfonline.com/loi/tnst20 ↗
http://www.tandfonline.com/ ↗
http://www.jstage.jst.go.jp/browse/jnst/%5Fvols ↗ - DOI:
- 10.1080/00223131.2022.2096147 ↗
- Languages:
- English
- ISSNs:
- 0022-3131
- Deposit Type:
- Legaldeposit
- View Content:
- Available online (eLD content is only available in our Reading Rooms) ↗
- Physical Locations:
- British Library DSC - 5023.500000
British Library DSC - BLDSS-3PM
British Library HMNTS - ELD Digital store - Ingest File:
- 26148.xml