研究了用于核反应堆低放射性结构材料Fe-Cr-Mn(W,V) 奥氏体钢.通过(C+N)复合强化有效地提高Fe-12 %Cr-15 %Mn(W,V)钢高温强度和蠕变断裂寿命,并改善高温塑性.在温度673 K以下,该合金比SUS316钢和JPCAS钢强度和塑性优良.合金强度和塑性与形变温度的相互关系是和合金形变组织变化密切相关.对673 K以上塑性降低的原因进行断口和显微组织分析,控制晶界碳化物粗化是进一步提高高温塑性的主要途径.
参考文献
[1] | Brager M R;Garner F A;Gelles D S et al.Developme nt o f Reduced Activation Alloys for Fusion Service[J].Journal of Nuclear Materials,1985,133&134:907. |
[2] | Fenici P;Boerman D;Coen V.Propertie s of Cr-Mn A ustenitic Stainless Steel for Fusion Reactor Applications[J].Nuclear Engineering and Design,1984(01):167. |
[3] | Defilippi J D;Brickner K G;Gilbert E M .Ductile-brittle Transitio n in Austenitic Chromium-Manganese-Nitro-gen Stainless Steels[J].Transactions of the Metallurgical Society of AIME,1969,245(10):214. |
[4] | Ohnishi K;Ishizaka J .The Effect of Temperature and Strain Rate on the Tensile Deformation Behaviour of Austenitic Steel[J].Journal of the Iron & Steel Institute of Japan,1977,63(14):2362. |
[5] | Miyahara K;Bae D S;Staka H.High Temperature Strength of High Mn -Cr Austenitic Steels[A].Nagoya Japan,1993:230. |
上一张
下一张
上一张
下一张
计量
- 下载量()
- 访问量()
文章评分
- 您的评分:
-
10%
-
20%
-
30%
-
40%
-
50%