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简述了金属材料中氦聚集行为的研究概况,特别是本课题组近年来对奥氏体不锈钢中氦扩散及氦泡形核生长机制的研究结果,并提出了这个领域有待解决的问题.

Studies of diffusion and aggregation behaviour of helium inmetallic materials are very important to solve the problem of helium embrittlement in structural materials used in the environment of nuclear power. Experimental studies on helium diffusion and aggregation in austenitic stainless steels in a wide temperature range have been performed in our research group and the main results obtained are briefly summarized. The mechanism of nucleation-growth of helium-bubbles has been discussed and some problems to be solved are also given.

参考文献

[1] Ullmaier H. Introductory Remarks-Helium in Metals [J]. Rad Eff, 1983, 78: 1-10.
[2] Singh B N, Trinkaus H. An Analysis of the Bubble Formation Behaviour under Different Experimental Conditions [J]. J Nucl Mater, 1992, 186: 153-165.
[3] Chen K Q, Yang S H, Wang Z G, et al. The Analysis of Microstructure of Helium Bubbles in 316L SS Induced by 3.02 MeV He Ion Irradiation [J]. J Nucl Mater, 1992, 191-194: 737-741.
[4] Chen K Q, Wang Y S, Quan J M, et al. The Formation of Helium Bubbles in 316L SS Irradiated with Helium Ions at Different Temperatures [J]. J Nucl Mater, 1994, 212-215: 345-351.
[5] 王引书,陈克勤,张崇宏,等. 高温下He+离子辐照316 L不锈钢中氦泡的形成研究 [J]. 核技术, 1996, 19(1): 5-8.
[6] Wang Y S, Chen K Q, Zhang C H, et al. The Formation of Helium Bubbles in 316L SS Irradiated with Helium Ions at 873 K [J]. J Nucl Mater, 1996, 240: 70-74.
[7] Zhang C H, Chen K Q, Wang Y S, et al. Formation of Bubbles in Helium Implanted 316L SS at Temperatures between 25 ℃ and 550 ℃ [J]. J Nucl Mater , 1997, 245: 210-216.
[8] 张崇宏, 陈克勤, 王引书,等. 2.5 MeV 的He+ 辐照316L不锈钢中氦泡的形核生长研究 [J].物理学报, 1997, 46(9): 1 774-1 781.
[9] Zhang C H, Chen K Q, Wang Y S, et al. Thermal Stability of He-vacancy Clusters in He-ion Irradiated 316L SS at 550 ℃ [J]. Nucl Instr and Meth, 1998, B135: 256-259.
[10] Zhang C H, Chen K Q, Wang Y S, et al. Temperature Dependence of Bubble Structures in Stainless Steels Irradiated with 2.5 MeV He+ ions [J]. J Nucl Mater , 1998, 258-263: 1 623-1 627.
[11] Sagara A, Muroga T, Motojima, et al. Materials Design and Related R & D Issues for the Force-free Helical Reactor (FFHR) [J]. J Nucl Mater, 1998, 258-263: 2 079-2 082.
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