欢迎登录材料期刊网

材料期刊网

高级检索

中子辐照引起的核反应堆压力容器钢中磷的晶间偏析是导致核反应堆压力容器脆性断裂的主要因素之一.本文提出了预测核反应堆压力容器钢中杂质元素(主要是磷)晶间非平衡偏析的溶质拖拽模型,并且与速率理论模型进行了对比.该模型的预测结果与最近发表的压力容器钢(包括C-Mn和MnMoNi钢)的一些实验数据一致.

参考文献

[1] Faulkner R G, Song S H, Flewitt P E J, Victoria M,Marmy P. J Nucl Mater, 1998, 255:189
[2] Druce S G, English C A, Foreman A J E, McElroy R J,Vatter I A, Bolton C J, Buswell J T, Jones R B. ASTM STP 1270, 1996:119
[3] McLean D. Grain Boundaries in Metals. Oxford: Oxford University Press, 1957:131
[4] Perez F J, Smith, R. Nucl Instr Meth, 1999, 136B: 153
[5] Bischler P J E, Wild R K. ASTM STP 1270, 1996:260
[6] Williams T J, Ellis D. ASTM STP 1405, 2001:8
[7] Meade D. PhD Thesis, Loughborough: Loughborough University, 1999
[8] English C A, Ortner S R, Gage G, Server W L, Rosinski S T. ASTM STP 1405, 2001:151
[9] Williams T J. Rolls Royce Naval Marine. Private communication, 2001
[10] Faulkner R G, Song S, Goodwin C C, Flewitt P E J. Defect Diffus Forum, 1999, 29:165
[11] Jones R B. Proceedings of EPRI Discussion Meeting,USA: Squaw Valley, 2001:66
[12] Little E A. J Nucl Mater, 1979, 11:87
[13] Takeyama T, Takahashi H, Ohnuki S. Bull Fac EngHokkaido Univ, 1984, 85:121
[14] Honeycombe R W K. Steels, Microstructure and Properties. London: Edward Arnold Ltd, 1981:5
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:
  • 1
    0%
  • 2
    0%
  • 3
    0%
  • 4
    0%
  • 5
    0%