TY - JOUR
T1 - Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C
AU - Imagawa, Yuya
AU - Hashidate, Ryuta
AU - Miyazawa, Takeshi
AU - Onizawa, Takashi
AU - Ohtsuka, Satoshi
AU - Yano, Yasuhide
AU - Tanno, Takashi
AU - Kaito, Takeji
AU - Ohnuma, Masato
AU - Mitsuhara, Masatoshi
AU - Toyama, Takeshi
N1 - Publisher Copyright:
© 2023 The Author(s). Published by Informa UK Limited, trading as Taylor & Francis Group.
PY - 2024
Y1 - 2024
N2 - The Japan Atomic Energy Agency has been developing 9Cr-oxide dispersion strengthened (ODS) steel as a fuel cladding material for sodium-cooled fast reactors (SFRs). Previous studies have formulated the creep rupture equation for 650°C–850°C. However, little data have been obtained above 850°C, and no equation has been formulated. This study conducted creep tests to evaluate creep strength at 700°C–1000°C. Two creep test methods, the internal pressure and ring creep tests under development, were used, and the validation of the ring creep test method was conducted. The results showed that 9Cr-ODS steel undergoes almost no strength change due to the matrix’s phase transformation, and a single equation can express a creep rupture strength from 700°C to 1000°C. In validating the ring creep test method, analysis clarified the effect of stress concentration on the specimen. Plastic deformation occurs at high initial stress and may lead to early rupture. The results will be essential for future creep testing and evaluation of neutron-irradiated 9Cr-ODS steel.
AB - The Japan Atomic Energy Agency has been developing 9Cr-oxide dispersion strengthened (ODS) steel as a fuel cladding material for sodium-cooled fast reactors (SFRs). Previous studies have formulated the creep rupture equation for 650°C–850°C. However, little data have been obtained above 850°C, and no equation has been formulated. This study conducted creep tests to evaluate creep strength at 700°C–1000°C. Two creep test methods, the internal pressure and ring creep tests under development, were used, and the validation of the ring creep test method was conducted. The results showed that 9Cr-ODS steel undergoes almost no strength change due to the matrix’s phase transformation, and a single equation can express a creep rupture strength from 700°C to 1000°C. In validating the ring creep test method, analysis clarified the effect of stress concentration on the specimen. Plastic deformation occurs at high initial stress and may lead to early rupture. The results will be essential for future creep testing and evaluation of neutron-irradiated 9Cr-ODS steel.
KW - Oxide dispersion strengthened steel
KW - creep strain
KW - creep strength
KW - fuel cladding tube
KW - internal creep test
KW - ring creep test
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U2 - 10.1080/00223131.2023.2269178
DO - 10.1080/00223131.2023.2269178
M3 - Article
AN - SCOPUS:85174600994
SN - 0022-3131
VL - 61
SP - 762
EP - 777
JO - journal of nuclear science and technology
JF - journal of nuclear science and technology
IS - 6
ER -