TY - JOUR
T1 - High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure
AU - Ohtsuka, Satoshi
AU - Shizukawa, Yuta
AU - Tanno, Takashi
AU - Imagawa, Yuya
AU - Hashidate, Ryuta
AU - Yano, Yasuhide
AU - Onizawa, Takashi
AU - Kaito, Takeji
AU - Ohnuma, Masato
AU - Mitsuhara, Masatoshi
AU - Nakashima, Hideharu
N1 - Funding Information:
This work was supported by MEXT Innovative Nuclear Research and Development Program Grant Number JPMXD0219214482; Ministry of Education Culture, Sports, Science and Technology.
Funding Information:
To complete the formulation based on modeling, the authors started an innovative nuclear research and development program sponsored by the Ministry of Education, Culture, Sports, Science, and Technology titled, “Development of irradiation properties evaluation technique of accident tolerant fuel cladding tube for advanced nuclear system.’ Under that program, the creep data of 9Cr-ODS TMSs has been obtained at temperatures from 700°C (equivalent to the hot-spot temperature under normal operation) to 1,000°C (equivalent to an accident temperature). Creep data has been obtained, and research into the creep deformation mechanism has been conducted to upgrade the equation correlating the nanostructure with creep properties. This upgrade allowed its application to a wide temperature range.
Publisher Copyright:
© 2022 Atomic Energy Society of Japan. All rights reserved.
PY - 2023
Y1 - 2023
N2 - 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.
AB - 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.
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U2 - 10.1080/00223131.2022.2096147
DO - 10.1080/00223131.2022.2096147
M3 - Article
AN - SCOPUS:85134412295
SN - 0022-3131
VL - 60
SP - 288
EP - 298
JO - journal of nuclear science and technology
JF - journal of nuclear science and technology
IS - 3
ER -