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Journal of Nuclear Science and Technology Volume 50, 2013 - Issue 4
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ARTICLE

ODS cladding fuel pins irradiation tests using the BOR-60 reactor

Takeji Kaito Japan Atomic Energy Agency, 4002, Narita-cho, Oarai-machi, Ibaraki, Japan
,
Yasuhide Yano Japan Atomic Energy Agency, 4002, Narita-cho, Oarai-machi, Ibaraki, Japan
,
Satoshi Ohtsuka Japan Atomic Energy Agency, 4002, Narita-cho, Oarai-machi, Ibaraki, Japan
,
Masaki Inoue Japan Atomic Energy Agency, 4002, Narita-cho, Oarai-machi, Ibaraki, Japan
,
Kenya Tanaka Japan Atomic Energy Agency, 4002, Narita-cho, Oarai-machi, Ibaraki, Japan
,
Alexander E. Fedoseev Research Institute of Atomic Reactors, Joint Stock Company, 10, Dimitrovgrad, Ulyanovsk region, Russia
,
Alexander V. Povstyanko Research Institute of Atomic Reactors, Joint Stock Company, 10, Dimitrovgrad, Ulyanovsk region, Russia
&
Andrey Novoselov Research Institute of Atomic Reactors, Joint Stock Company, 10, Dimitrovgrad, Ulyanovsk region, Russia
 show all
Pages 387-399 | Received 22 Aug 2012, Accepted 10 Dec 2012, Published online: 28 Mar 2013

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Yuya Imagawa, Ryuta Hashidate, Takeshi Miyazawa, Takashi Onizawa, Satoshi Ohtsuka, Yasuhide Yano, Takashi Tanno, Takeji Kaito, Masato Ohnuma, Masatoshi Mitsuhara & Takeshi Toyama. (2023) Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C. Journal of Nuclear Science and Technology 0:0, pages 1-16.
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Bing Bai, Xu Han, Han Cao, Xinfu He, Changyi Zhang & Wen Yang. (2022) Composition optimization of radiation resistance ODS alloy with high strength and ductility for advanced reactor based on machine learning. Journal of Nuclear Science and Technology 59:6, pages 725-734.
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Satoshi Ohtsuka, Takeji Kaito, Yasuhide Yano, Shinichiro Yamashita, Ryuichiro Ogawa, Tomoyuki Uwaba, Shinichi Koyama & Kenya Tanaka. (2013) Investigation of the cause of peculiar irradiation behavior of 9Cr-ODS steel in BOR-60 irradiation tests. Journal of Nuclear Science and Technology 50:5, pages 470-480.
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Articles from other publishers (13)

Y. Liu, H.E. Ge, Q.S. Ren, H.W. Deng, Z. Li, B. Du & T. Zhang. (2023) Improved corrosion resistance of TiAlCrNbMo alloy to lead-bismuth eutectic by pre-oxidation. Journal of Materials Research and Technology.
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M. Romedenne, R. Pillai, B. Harris & B.A. Pint. (2022) Compatibility of Fe-Cr-Al and Fe-Cr-Al-Mo oxide dispersion strengthened steels with static liquid sodium at 700  C . Journal of Nuclear Materials 569, pages 153919.
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G. V. Prasad ReddyV. KarthikS. Latha, C. N. Venkiteswaran, Divakar Ramachandran & Shaju K. Albert. (2022) Core Materials for Sodium-Cooled Fast Reactors: Past to Present and Future Prospects. Materials Performance and Characterization 11:2, pages 20200208.
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Kosuke Aizawa, Masanori Ando, Yoshitaka Chikazawa, Norihiro Doda, Yasuhiro Enuma, Toshiki Ezure, Yoshitaka Fukano, Erina Hamase, Shun Hirooka, Tomoyuki Hiyama, Katsunori Ishii, Takeji Kaito, Kenji Kamiyama, Norihiro Kikuchi, Jun Kobayashi, Shigenobu Kubo, Akikazu Kurihara, Shuhei Maruyama, Kentaro Matsushita, Takero Mori, Koji Morita, Hiroaki Ohira, Shigeo Ohki, Satoshi Okajima, Yasushi Okano, Takashi Onizawa, Ayako Ono, Takayuki Ozawa, Hiroshi Seino, Takashi Takata, Shigeru Takaya, Masayuki Takeuchi, Masaaki Tanaka, Hiroshi Taninaka, Takashi Tanno, Kodai Toyota, Akihiro Uchibori, Tomoyuki Uwaba, Takashi Wakai, Tomoyoshi Watakabe, Hiroki Yada, Tomohiko Yamamoto, Hidemasa Yamano, Kenji Yokoyama, Ryuji Yoshikawa, Kazuo Yoshimura, Ryuta Hashidate, Yuichi Sano & Akiyuki Seki. 2022. Sodium-cooled Fast Reactors. Sodium-cooled Fast Reactors 409 626 .
D. Sornin, U. Ehrnstén, N. Mozzani, J. Rantala, M. Walter, A. Hobt, J. Aktaa, E. Oñorbe, M. Hernandez-Mayoral, A. Ulbricht, S. Gicquel, L. Frank & Y. de Carlan. (2021) Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure. Metallurgical and Materials Transactions A 52:8, pages 3541-3552.
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Shigeharu Ukai, Naoko Oono-Hori & Satoshi Ohtsuka. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 255 292 .
Y. Yano, Y. Sekio, T. Tanno, S. Kato, T. Inoue, H. Oka, S. Ohtsuka, T. Furukawa, T. Uwaba, T. Kaito & S. Ukai. (2019) Ultra-high temperature creep rupture and transient burst strength of ODS steel claddings. Journal of Nuclear Materials 516, pages 347-353.
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Hiroshi Oka, Takashi Tanno, Satoshi Ohtsuka, Yasuhide Yano & Takeji Kaito. (2018) Effect of nitrogen concentration on nano-structure and high-temperature strength of 9Cr-ODS steel. Nuclear Materials and Energy 16, pages 230-237.
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Satoshi Ohtsuka, Takashi Tanno, Hiroshi Oka, Yasuhide Yano, Shoichi Kato, Tomohiro Furukawa & Takeji Kaito. (2018) Model calculation of Cr dissolution behavior of ODS ferritic steel in high-temperature flowing sodium environment. Journal of Nuclear Materials 505, pages 44-53.
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Y. Yano, T. Tanno, H. Oka, S. Ohtsuka, T. Inoue, S. Kato, T. Furukawa, T. Uwaba, T. Kaito, S. Ukai, N. Oono, A. Kimura, S. Hayashi & T. Torimaru. (2017) Ultra-high temperature tensile properties of ODS steel claddings under severe accident conditions. Journal of Nuclear Materials 487, pages 229-237.
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S. Ukai, S. Ohtsuka, T. Kaito, Y. de Carlan, J. Ribis & J. Malaplate. 2017. Structural Materials for Generation IV Nuclear Reactors. Structural Materials for Generation IV Nuclear Reactors 357 414 .
Hiroshi Oka, Takashi Tanno, Satoshi Ohtsuka, Yasuhide Yano, Tomoyuki Uwaba, Takeji Kaito & Masato Ohnuma. (2016) Effect of thermo-mechanical treatments on nano-structure of 9Cr-ODS steel. Nuclear Materials and Energy 9, pages 346-352.
Crossref
Satoshi Ohtsuka, Yasuhide Yano, Takashi Tanno, Takeji Kaito & Kenya Tanaka. (2013) Microstructure Characterization of Oxide Dispersion Strengthened Steels Containing Metallic Chromium Inclusions after High-Temperature Thermal Aging. MATERIALS TRANSACTIONS 54:10, pages 2018-2026.
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