不锈钢辐射损伤随温度和剂量的变化(英文)

郑永男; 普拉提.艾合买提; 徐勇军; 周冬梅; 王志强; 阮玉珍; 杜恩鹏; 袁大庆; 朱升云

doi:10.11804/NuclPhysRev.22.01.110

不锈钢辐射损伤随温度和剂量的变化(英文)

1 中国原子能科学研究院, 北京 102413; 2 新疆大学物理系, 新疆乌鲁木齐 830046

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出版历程
- 收稿日期: 1899-12-31
- 修回日期: 1899-12-31
- 刊出日期: 2005-03-19

Variation of Radiation Damage in Stainless Steel with Temperature and Dose

1 China Institute of Atomic Energy, Beijing 102413, China; 2 Department of Physics, Xinjian University, Wulumuqi 830046, China

摘要

摘要: 用重离子辐照模拟和正电子湮没寿命技术研究了改进型316L不锈钢在21 和33 dpa辐照剂量下的辐照损伤在室温到802 °C温度范围随辐照温度变化和室温下0—100 dpa剂量范围随辐照剂量变化. 在580 °C左右实验观察到辐照肿胀峰，在21 和33 dpa辐照剂量下相应的空位团分别由14和19个空位组成，尺度分别为0.68 和0.82 nm. 空位团尺寸随辐照剂量增加，在100 dpa时空位团由8个空位组成，尺度为0.55 nm. 实验结果表明，在改进型316L不锈钢中辐照损伤随辐照温度变化更灵敏.
- 改进型316L不锈钢 /
- 辐照损伤 /
- 正电子湮没寿命技术 /
- 重离子辐照模拟
Abstract: Dependence of radiation damage in the modified 316L stainless steel has been investigated on irradiation temperature from room temperature to 802 ℃ at 21 and 33 dpa and on irradiation dose up to 100 displacemets/atom(dpa) at room temperature by the heavy ion irradiation simulation and positron annihilation lifetime techniques. A radiation swelling peak was observed at ~580 ℃ where the vacancy cluster contains 14 and 19 vacancies and has an average diameter of 0.68 and 0.82 nm, respectively for the 21 and 33 dpa irradiations. The size of the vacancy clusters increases with the increasing of irradiation dose, and the vacancy cluster produced at 100 dpa consists of 8 vacancies and reaches a size of 0.55 nm in diameter. The experimental results show that the radiation damage in this modified 316L stainless steel is more sensitive to irradiation temperature.
- modified 316L stainless steel /
- radiation damage /
- positron annihilation lifetime techniques /
- heavy ion irradiation simulation

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不锈钢辐射损伤随温度和剂量的变化(英文)

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出版历程

Variation of Radiation Damage in Stainless Steel with Temperature and Dose

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出版历程

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