Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C

Imagawa, Yuya; Hashidate, Ryuta; Miyazawa, Takeshi; Onizawa, Takashi; Ohtsuka, Satoshi; Yano, Yasuhide; Tanno, Takashi; Kaito, Takeji; Ohnuma, Masato; Mitsuhara, Masatoshi; Toyama, Takeshi

doi:10.1080/00223131.2023.2269178

Title: Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C

Journal Article · 23 October 2023 · Journal of Nuclear Science and Technology (Tokyo)

DOI: https://doi.org/10.1080/00223131.2023.2269178 · OSTI ID:2203483

Imagawa, Yuya ^[1]; Hashidate, Ryuta ^[1]; Miyazawa, Takeshi ^[1]; Onizawa, Takashi ^[1];

^[1]; Yano, Yasuhide ^[1]; Tanno, Takashi ^[1]; Kaito, Takeji ^[1]; Ohnuma, Masato ^[2]; Mitsuhara, Masatoshi ^[3]; Toyama, Takeshi ^[4]

Oarai Research Institute, Sector of Fast Reactor and Advanced Reactor Research and Development, Japan Atomic Energy Agency, Ibaraki, Japan
Division of Quantum Science and Engineering, Hokkaido University, Sapporo, Hokkaido, Japan
Department of molecular and material Sciences, Kyushu University, Kasuga, Fukuoka, Japan
Institute for Materials Research, Tohoku University, Oarai, Ibaraki, Japan

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Sponsoring Organization:: USDOE Office of Electricity (OE), Advanced Grid Research & Development. Power Systems Engineering Research

Grant/Contract Number:: JPMXD0219214482

OSTI ID:: 2203483

Journal Information:: Journal of Nuclear Science and Technology (Tokyo), Journal Name: Journal of Nuclear Science and Technology (Tokyo) Vol. 61 Journal Issue: 6; ISSN 0022-3131

Publisher:: Informa UK LimitedCopyright Statement

Country of Publication:: Japan

Language:: English

References (34)

Creep and damage anisotropies of 9%Cr and 14%Cr ODS steel cladding Jaumier, T.; Vincent, S.; Vincent, L. Journal of Nuclear Materials, Vol. 518 https://doi.org/10.1016/j.jnucmat.2019.02.041	journal	May 2019
Creep constitutive equation of dual phase 9Cr-ODS steel Sakasegawa, Hideo; Ukai, Shigeharu; Tamura, Manabu Journal of Nuclear Materials, Vol. 373, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2007.05.031	journal	February 2008
ODS Ferritic/martensitic alloys for Sodium Fast Reactor fuel pin cladding Dubuisson, Philippe; Carlan, Yann de; Garat, Véronique Journal of Nuclear Materials, Vol. 428, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.10.037	journal	September 2012
Cooperative grain boundary sliding in creep deformation of FeCrAl-ODS steels at high temperature and low strain rate Kamikawa, R.; Ukai, S.; Kasai, S. Journal of Nuclear Materials, Vol. 511 https://doi.org/10.1016/j.jnucmat.2018.04.050	journal	December 2018
High-temperature strength characterization of advanced 9Cr-ODS ferritic steels Ukai, S.; Ohtsuka, S.; Kaito, T. Materials Science and Engineering: A, Vol. 510-511 https://doi.org/10.1016/j.msea.2008.04.126	journal	June 2009
Creep-rupture tests on chromium-containing conventional and ODS steels in oxygen-controlled Pb and air at 650 °C Yurechko, Mariya; Schroer, Carsten; Wedemeyer, Olaf Nuclear Engineering and Design, Vol. 280 https://doi.org/10.1016/j.nucengdes.2014.06.003	journal	December 2014
In-reactor creep rupture properties of 20% CW modified 316 stainless steel Ukai, S.; Mizuta, S.; Kaito, T. Journal of Nuclear Materials, Vol. 278, Issue 2-3 https://doi.org/10.1016/S0022-3115(99)00233-0	journal	April 2000
ODS cladding fuel pins irradiation tests using the BOR-60 reactor Kaito, Takeji; Yano, Yasuhide; Ohtsuka, Satoshi Journal of Nuclear Science and Technology, Vol. 50, Issue 4 https://doi.org/10.1080/00223131.2013.773165	journal	April 2013
The properties of the ring and burst creep of ZIRLO cladding Seok, Chang-Sung; Bae, Bong-Kook; Koo, Jae-Mean Engineering Failure Analysis, Vol. 13, Issue 3 https://doi.org/10.1016/j.engfailanal.2005.02.009	journal	April 2006
High-temperature creep deformation in FeCrAl-oxide dispersion strengthened alloy cladding Ukai, S.; Kato, S.; Furukawa, T. Materials Science and Engineering: A, Vol. 794 https://doi.org/10.1016/j.msea.2020.139863	journal	September 2020
Burst properties of irradiated oxide dispersion strengthened ferritic steel claddings Yoshitake, T.; Ohmori, T.; Miyakawa, S. Journal of Nuclear Materials, Vol. 307-311 https://doi.org/10.1016/S0022-3115(02)00947-9	journal	December 2002
Creep Behavior, Deformation Mechanisms, and Creep Life of Mod.9Cr-1Mo Steel Abe, Fujio Metallurgical and Materials Transactions A, Vol. 46, Issue 12 https://doi.org/10.1007/s11661-015-3144-5	journal	September 2015
Microstructural stability of ODS steel after very long-term creep test Oka, Hiroshi; Tanno, Takashi; Yano, Yasuhide Journal of Nuclear Materials, Vol. 547 https://doi.org/10.1016/j.jnucmat.2021.152833	journal	April 2021
Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor Yamano, H.; Kubo, S.; Shimakawa, Y. Science and Technology of Nuclear Installations, Vol. 2012 https://doi.org/10.1155/2012/614973	journal	January 2012
High temperature deformation characteristics of Zirlo™ tubing via ring-creep and burst tests Seok, C. S.; Marple, B.; Song, Y. J. Nuclear Engineering and Design, Vol. 241, Issue 3 https://doi.org/10.1016/j.nucengdes.2010.04.017	journal	March 2011
Creep and rupture in Type 316 stainless steel at temperatures between 525 and 900°C Part I: Creep rate Morris, D. G.; Harries, D. R. Metal Science, Vol. 12, Issue 11 https://doi.org/10.1179/msc.1978.12.11.525	journal	November 1978
Development of Pressurized Resistance Welding Technology for ODS Ferritic Steel Cladding Tube Seki, Masayuki; Kono, Shusaku Transactions of the Atomic Energy Society of Japan, Vol. 3, Issue 1 https://doi.org/10.3327/taesj2002.3.95	journal	January 2004
Assessment of a new fabrication route for Fe–9Cr–1W ODS cladding tubes Toualbi, L.; Cayron, C.; Olier, P. Journal of Nuclear Materials, Vol. 428, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.12.013	journal	September 2012
Irradiation response of ODS Eurofer97 steel Luzginova, N. V.; Nolles, H. S.; ten Pierick, P. Journal of Nuclear Materials, Vol. 428, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.08.030	journal	September 2012
High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure Ohtsuka, Satoshi; Shizukawa, Yuta; Tanno, Takashi Journal of Nuclear Science and Technology, Vol. 60, Issue 3 https://doi.org/10.1080/00223131.2022.2096147	journal	July 2022
Elemente der Technologischen Mechanik Ludwik, P. https://doi.org/10.1007/978-3-662-40293-1	book	January 1909
HRTEM Study of yttrium oxide particles in ODS steels for fusion reactor application Klimiankou, M.; Lindau, R.; Möslang, A. Journal of Crystal Growth, Vol. 249, Issue 1-2 https://doi.org/10.1016/S0022-0248(02)02134-6	journal	February 2003
In-pile creep rupture properties of ODS ferritic steel claddings Kaito, T.; Ohtsuka, S.; Inoue, M. Journal of Nuclear Materials, Vol. 386-388 https://doi.org/10.1016/j.jnucmat.2008.12.117	journal	April 2009
Reliable Evaluation of Long-term Creep Properties at Elevated Temperature Maruyama, Kouichi Tetsu-to-Hagane, Vol. 105, Issue 8 https://doi.org/10.2355/tetsutohagane.TETSU-2019-006	journal	January 2019
Creep response and deformation processes in nanocluster-strengthened ferritic steels Hayashi, T.; Sarosi, P. M.; Schneibel, J. H. Acta Materialia, Vol. 56, Issue 7 https://doi.org/10.1016/j.actamat.2007.11.038	journal	April 2008
Creep behavior of ODS materials: A study of dislocations/precipitates interactions Malaplate, J.; Mompiou, F.; Béchade, J. -L. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.059	journal	October 2011
High-temperature mechanical properties and microstructure of 9Cr oxide dispersion strengthened steel compared with RAFMs Li, Yanfen; Nagasaka, Takuya; Muroga, Takeo Fusion Engineering and Design, Vol. 86, Issue 9-11 https://doi.org/10.1016/j.fusengdes.2011.03.004	journal	October 2011
The Monkman-Grant relationship Sundararajan, G. Materials Science and Engineering: A, Vol. 112 https://doi.org/10.1016/0921-5093(89)90360-2	journal	June 1989
Irradiation behavior evaluation of oxide dispersion strengthened ferritic steel cladding tubes irradiated in JOYO Yamashita, Shinichiro; Yano, Yasuhide; Ohtsuka, Satoshi Journal of Nuclear Materials, Vol. 442, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.04.051	journal	November 2013
Superior Charpy impact properties of ODS ferritic steel irradiated in JOYO Kuwabara, T.; Kurishita, H.; Ukai, S. Journal of Nuclear Materials, Vol. 258-263 https://doi.org/10.1016/S0022-3115(98)00192-5	journal	October 1998
Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings Yano, Y.; Sekio, Y.; Tanno, T. Journal of Nuclear Materials, Vol. 516 https://doi.org/10.1016/j.jnucmat.2019.01.052	journal	April 2019
Deformation and damage processes during creep of Incoloy MA957 Wilshire, B.; Lieu, T. Materials Science and Engineering A, Vol. 386, Issue 1-2 https://doi.org/10.1016/S0921-5093(04)00969-4	journal	November 2004
Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I): Improvement of Mechanical Properties by Recrystallization Processing Ukai, Shigeharu; Nishida, Toshio; Okada, Hirokazu Journal of Nuclear Science and Technology, Vol. 34, Issue 3 https://doi.org/10.1080/18811248.1997.9733658	journal	March 1997
A next Generation Sodium-Cooled fast Reactor Concept and its r&d Program Ichimiya, Masakazu; Mizuno, Tomoyasu; Kotake, Shoji Nuclear Engineering and Technology, Vol. 39, Issue 3 https://doi.org/10.5516/NET.2007.39.3.171	journal	June 2007

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