著者

伊藤 裕道

出版者

日本英語教育史学会

雑誌

日本英語教育史研究 (ISSN:0916006X)

巻号頁・発行日

vol.17, pp.41-75, 2002-05-10 (Released:2012-10-29)

参考文献数

116

著者

伊藤 裕道

出版者

日本英語教育史学会

雑誌

日本英語教育史研究 (ISSN:0916006X)

巻号頁・発行日

vol.14, pp.67-104, 1999-05-10 (Released:2012-10-29)

著者

高松 操 川原 啓孝 伊藤 裕道 宇敷 洋 鈴木 信弘 佐々木 純 大田 克 奥田 英二 小林 哲彦 長井 秋則 坂尾 龍太 村田 長太郎 田中 淳也 松坂 康智 立野 高寛 原 正秀 岡﨑 弘祥

出版者

一般社団法人 日本原子力学会

雑誌

日本原子力学会和文論文誌 (ISSN:13472879)

巻号頁・発行日

vol.15, no.1, pp.32-42, 2016 (Released:2016-02-15)

参考文献数

10

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In the experimental fast reactor “Joyo”, it was confirmed that the top of the irradiation test subassembly of the material testing rig named “MARICO-2” was broken and bent onto the in-vessel storage rack as an obstacle, damaging the upper core structure (UCS). In this paper, we describe the in-vessel repair techniques for UCS replacement, which are developed in Joyo. The UCS replacement was conducted in the following four stages: (1) jack-up of the existing damaged UCS, (2) retrieval of the existing damaged UCS, (3) installation of the O-ring, and (4) insertion of the new UCS. Since the UCS replacement was not anticipated in the original design, the work conditions at Joyo were carefully investigated, and the obtained results were applied to the design of special handling equipment. The UCS replacement was successfully completed in 2014. In-vessel repair techniques for sodium-cooled fast reactors (SFRs) are important in confirming the safety and integrity of SFRs. However, the techniques demonstrated in the actual reactor environment with high temperature, high radiation dose, and remaining sodium are insufficient to secure the reliability of these techniques. The experience and knowledge accumulated in the UCS replacement provide valuable insights into further improvements of in-vessel repair techniques for SFRs.

著者

伊藤 裕道

出版者

日本英語教育史学会

雑誌

日本英語教育史研究 (ISSN:0916006X)

巻号頁・発行日

vol.12, pp.163-191, 1997-05-10 (Released:2012-10-29)

参考文献数

74

著者

吉岡 洋明 伊藤 裕道 田中 泰彦 池田 保 美

出版者

社団法人日本鉄鋼協会

雑誌

鐵と鋼 : 日本鐡鋼協會々誌 (ISSN:00211575)

巻号頁・発行日

vol.89, no.6, pp.705-710, 2003-06

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To meet the requirements for optimum utilization of power station sites and economic realization of coal fired thermal units, tandem compound 60 Hz 1000 MW large thermal units were developed. One of the most critical items was development of a large-size high strength generator rotor forging with comparable toughness to the conventional rotor forging. Based on the investigation results of existing rotor forging, chemistry optimization was conducted within the specification of conventional turbine generator and low pressure rotor forging by using lab oratory heat materials and 0.28%C-0.25%Mn-4%Ni-1.75%Cr-0.4%Mo-0.12%V high purity steel was selected for the candidate material. Double tempering heat treatment of 550℃ and 580℃ was also developed for increasing the yielding ratio of 0.02% yielding stress to tensile strength to meet the requirements of mechanical properties. According to those laboratory studies, one trial rotor forging with the same diameter as production ones was successfully produced.