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ORIGINAL PAPER

Development of Oxide Dispersion Strengthened Ferritic Steels for FBR Core Application, (I)

Improvement of Mechanical Properties by Recrystallization Processing

, , , , &
Pages 256-263 | Received 02 Jul 1996, Published online: 15 Mar 2012

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Read on this site (13)

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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Hideo Sakasegawa, Hiroyasu Tanigawa & Masami Ando. (2014) Corrosion-resistant coating technique for oxide-dispersion-strengthened ferritic/martensitic steel. Journal of Nuclear Science and Technology 51:6, pages 737-743.
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Takeshi Narita, Shigeharu Ukai, Bin Leng, Satoshi Ohtsuka & Takeji Kaito. (2013) Characterization of recrystallization of 12Cr and 15Cr ODS ferritic steels. Journal of Nuclear Science and Technology 50:3, pages 314-320.
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Takeshi NARITA, Shigeharu UKAI, Takeji KAITO, Satoshi OHTSUKA & Yasuji MATSUDA. (2008) Water Corrosion Resistance of ODS Ferritic-Martensitic Steel Tubes. Journal of Nuclear Science and Technology 45:2, pages 99-102.
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Akihiko KIMURA, Han-Sik CHO, Naoki TODA, Ryuta KASADA, Kentaro YUTANI, Hirotatsu KISHIMOTO, Noriyuki IWATA, Shigeharu UKAI & Masayuki FUJIWARA. (2007) High Burnup Fuel Cladding Materials R&D for Advanced Nuclear Systems. Journal of Nuclear Science and Technology 44:3, pages 323-328.
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Takeshi NARITA, Shigeharu UKAI, Takeji KAITO, Satoshi OHTSUKA & Toshimi KOBAYASHI. (2004) Development of Two-Step Softening Heat Treatment for Manufacturing 12Cr-ODS Ferritic Steel Tubes. Journal of Nuclear Science and Technology 41:10, pages 1008-1012.
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Shigeharu UKAI, Takanari OKUDA, Masayuki FUJIWARA, Toshimi KOBAYASHI, Syunji MIZUTA & Hideharu NAKASHIMA. (2002) Characterization of High Temperature Creep Properties in Recrystallized 12Cr-ODS Ferritic Steel Claddings. Journal of Nuclear Science and Technology 39:8, pages 872-879.
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Shigeharu UKAI, Shunji MIZUTA, Masayuki FUJIWARA, Takanari OKUDA & Toshimi KOBAYASHI. (2002) Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation. Journal of Nuclear Science and Technology 39:7, pages 778-788.
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Takeshi YOKOO, Takanari OGATA & Hirokazu OHTA. (2000) A Design Study on the FBR Metal Fuel and Core for Commercial Applications. Journal of Nuclear Science and Technology 37:8, pages 636-645.
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Shigeharu UKAI, Tsunemitsu YOSHITAKE, Syunji MIZUTA, Yukihiko MATSUDAIRA, Shigeki HAGI & Toshimi KOBAYASHI. (1999) Preliminary Tube Manufacturing of Oxide Dispersion Strengthened Ferritic Steels with Recrystallized Structure. Journal of Nuclear Science and Technology 36:8, pages 710-712.
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I. Shibahara. (1998) Development of in-core materials for fast breeder reactors. Radiation Effects and Defects in Solids 144:1-4, pages 233-250.
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Shigeharu UKAI, Toshio NISHIDA, Takanari OKUDA & Tunemitsu YOSHITAKE. (1998) Development of Oxide Dispersion Strengthened Steels for FBR Core Application, (II). Journal of Nuclear Science and Technology 35:4, pages 294-300.
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