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川崎製鉄技報
KAWASAKI STEEL GIHO
Vol.6 (1974) No.2
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原子炉圧力容器用ASME SA533 Gr.B Cl.1極厚鋼板について
On Heavy Gauge ASME SA 533 Gr.B Cl.1 Steel Plate for Nuclear Reactor Pressure Vessels

楠原 祐司(Yuji Kusuhara) 吉村 茂彦(Shigehiko Yoshimura) 荻野 泰司(Yasuji Ogino) 榎並 禎一(Teiichi Knami) 船越 督己(Tokushi Funakoshi) 林  忠男(Tadao Hayashi)
要旨 :
溶解精錬工程にLD転炉とASEA-SKF取鍋精錬炉(LRF)の組合せを使用し,原子炉圧力容器用ASME SA533 Cr.B Cl.1鋼板の試作を行なった。試作は適正な強度,高靱性および鋼板の内部健全性の確保ならびにこれらの再現性を確認するため,60〜80tの鋼塊を用い5回行なった。結果はきわめて良好であり,LRF精錬鋼の特色である非金属介在物の少ない内部健全性のすぐれた鋼板が製造できることが確認され,240mm厚さの鋼板でも適正な強度と高靱性が得られた。さらに鋼板内の諸特性のバラツキ,大型脆性破壊試験,低サイクル疲労試験,加工性試験などを実施し,原子炉圧力容器用鋼板としてきわめてすぐれた特性を有することを確認した。
Synopsis :
ASME SA 533 Gr.B Class 1 steel plates for nuclear reactor pressure vessels have been made for test purpose by means of combined use of LD converter and ASEA-SKF ladle refining furnace (LRF) in the melting and refining process. In order to secure proper strength, high fracture toughness and excellent internal soundness of the steel, as well as to confirm their reproducibility, tests were conducted five times, using a 60 to 80 t ingot for each heat. The results are found satisfactory, and steel plates obtained have a superior internal soundness with lesser non-metallic inclusions, well confirming what is usually known of LRF refined steels. The steel, even in 240 mm thickness, showed proper strength and high fracture toughness. These results and other tests conducted on uniformity of mechanical properties and fracture toughness across total dimensions of the plates, fracture toughness based on large specimens, low cycle fatigue, and workability, confirmed that the subject steel has such properties to permit good nuclear reactor pressure vessel fabrication.
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