検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Development of PRW welding technology for 9Cr-ODS cladding tube

9CrODS鋼製被覆管の抵抗溶接技術開発

関 正之; 木原 義之; 皆藤 威二; 塚田 竜也*; 本木 和彦*; 平子 一仁*

Seki, Masayuki; Kihara, Yoshiyuki; Kaito, Takeji; Tsukada, Tatsuya*; Motoki, Kazuhiko*; Hirako, Kazuhito*

原子力機構では、高速炉における集合体平均150GWd/tの燃焼度を達成するために、耐スエリング性と高温強度に優れた酸化物分散強化型被覆材(ODS鋼)の開発を進めている。ODS鋼の端栓溶接に際しては、従来のTIG溶接のような融接法では溶融部にポロシティーが生じて必要な溶接強度が得られないことから、固相溶接法の一つである加圧抵抗溶接法の開発を行っている。また、溶接部における残留応力の緩和のために溶接部熱処理装置及び溶接部の健全性確認のために超音波探傷装置の開発も合わせて実施している。本報告は、これら装置の特徴と溶接強度及び原子炉を用いた照射試験結果についてまとめて報告するものである。

Oxide Dispersion Strengthened (ODS) steel has been developed as an advanced fuel cladding tube for sodium cooled fast reactors in Japan Atomic Energy Agency (JAEA) to attain the target burn up of 150 GWd/t in the bundle average because of its excellent swelling resistance and high mechanical strength in high temperature. If conventional TIG welding is applied to the ODS welding, it is difficult to obtain necessary mechanical strength at the weld zone because of the formation of porosity. It is formed by the argon bubbles which initially dissolve in the matrix and grow up under the high temperature during welding. Therefore JAEA has been conducted the development of pressurized resistance welding (PRW) technology for ODS cladding tube, which is one of the solid state welding methods. This paper describes in the development of PRW technology, an ultrasonic test method for detecting weld defects, the result of machine strength measurement examination in weld part and the result of fuel pin irradiation examination using nuclear reactor.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.