CAJ | 학술논문

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 癈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 癈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.
용중리자복조모의화정전자인몰수명기술연구료개진형316L불수강재21 화33 dpa복조제량하적복조손상재실온도802 폐온도범위수복조온도변화화실온하0-100 dpa제량범위수복조제량변화.재580 폐좌우실험관찰도복조종창봉, 재21 화33 dpa복조제량하상응적공위단분별유14화19개공위조성, 척도분별위0.68 화0.82 nm.공위단척촌수복조제량증가, 재100 dpa시공위단유8개공위조성, 척도위0.55 nm.실험결과표명, 재개진형316L불수강중복조손상수복조온도변화경령민.
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.