銅合金/ステンレス鋼接合材の中性子照射試験

• Material Type: 文書・図像類
• Title: 銅合金/ステンレス鋼接合材の中性子照射試験
• Author/Editor: 山田 弘一; 河村 弘
• Author Heading: 山田 弘一; 河村 弘
• Publication Date: 2006-01
• Publication Date (W3CDTF): 2006-01
• Alternative Title: Neutron irradiation test of copper alloy/stainless steel joint materials
• Periodical title: JAEA-Technology 2005-001
• Text Language Code: eng
• Target Audience: 一般
• Note (General): As a study about the joint technology of copper alloy and stainless steel for utilization as cooling piping in International Thermonuclear Experimental Reactor (ITER), Al$_{2}$O$_{3}$-dispersed strengthened copper or CuCrZr was joined to stainless steel by three kinds of joint methods (casting joint, brazing joint and friction welding method) for the evaluation of the neutron irradiation effect on joints. A neutron irradiation test was performed to three types of joints and each copper alloy. The average value of fast neutron fluence in this irradiation test was about 2$\times$10$^{24}$n/m$^{2}$(E$>$1MeV), and the irradiation temperature was about 130$^{\circ}$C. As post-irradiation examinations, tensile tests, hardness tests and observation of fracture surface after the tensile tests were performed. All type joints changed to be brittle by the neutron irradiation effect like each copper alloy material, and no particular neutron irradiation effect due to the effect of joint process was observed. On the casting and friction welding, hardness of copper alloy near the joint boundary changed to be lower than that of each copper alloy by the effect of joint procedure. However, tensile strength of joints was almost the same as that of each copper alloy before/after neutron irradiation. On the other hand, tensile strength of joints by brazing changed to be much lower than CuAl-25 base material by the effect of joint process before/after neutron irradiation. Results in this study showed that the friction welding method and the casting would be able to apply to the joint method of piping in ITER.; 国際熱核融合実験炉(ITER)における冷却配管のための銅合金とステンレス鋼の接合方法に関する研究として、銅合金にアルミナ分散強化銅(Al$_{2}$O$_{3}$含有率:0.5wt\%(CuAl-25))及びCuCrZrを選定し、ステンレス鋼(SUS316LN-IG)との各種接合方法による接合材を製作し、中性子照射効果の評価を行った。照射試験として、高速中性子照射量約2$\times$10$^{24}$n/m$^{2}$(E$>$1MeV)及び照射温度約130$^{\circ}$Cにて中性子照射を行った後、照射後試験として、引張試験,硬さ試験及び破面観察を行った。その結果、中性子照射により、いずれの接合材も脆化したが、接合による影響に起因する中性子照射効果は認められなかった。接合による影響としては、硬さ試験の結果から、鋳込み接合法及び摩擦圧接法では、接合による影響で接合界面近傍の銅合金の硬さの低下が確認された。しかしながら、中性子照射前後とも、引張強度は接合材,銅合金ともに同等の特性であった。一方、ロウ付け接合材は照射材,未照射材とも、接合により著しい引張強度の低下が見られた。以上のことから、鋳込み接合材及び摩擦圧接接合材については、本研究で用いた接合要領が、核融合炉における異種接合方法として適用できることを明らかにした。
• Source: /JAEA-Technology-2005-001.pdf （fulltext）; https://jopss.jaea.go.jp/pdfdata/JAEA-Technology-2005-001.pdf
• Access Restrictions: 限定公開
• Data Provider (Database): 国立情報学研究所 : 学術機関リポジトリデータベース（IRDB）（機関リポジトリ）; https://irdb.nii.ac.jp
• Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System

• Summary, etc.: As a study about the joint technology of copper alloy and stainless steel for utilization as cooling piping in International Thermonuclear Experimenta...