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核能结构材料高剂量辐照损伤的重离子辐照模拟研究
High dose Radiation damage in nuclear energy structural materials investigated by heavy ion irradiation simulation
【作者】 郑永男; 徐勇军; 袁大庆; 朱佳政; 李安利; 左(走翼); 周冬梅; 范平; 王志强; 马小强; 张乔丽;
【Author】 ZHENG Yong-nan;XU Yong-jun;YUAN Da-qing;ZHU Jia-zheng;LI An-li;ZUO Yi;ZHOU Dong-mei;FAN Ping;WANG Zhi-qiang;MA Xiao-qiang;ZHANG Qiao-li;China Institute of Atomic Energy;
【机构】 中国原子能科学研究院;
【摘要】 在聚变堆、ADS、快堆等新一代核能装置中,结构材料受到的辐照位移损伤高达几十到上百dpa/年。高剂量辐照引起的材料辐照损伤的研究是核能发展中一个十分关注的问题。然而,缺少高注量质子和中子辐照源装置,严重阻碍了相关领域的研究。重离子辐照产生的位移损伤率比中子和质子高几个数量级,能在短时间内产生很高的辐照位移损伤,用重离子辐照模拟中子辐照开启了一个研究高剂量位移损伤的有效方法。在中国原子能科学研究院HI-13串列加速器上建立了重离子辐照装置,本文采用重离子辐照模拟方法研究了改进型316不锈钢室温到800℃温度范围内的辐照损伤效应随温度变化和改进型316不锈钢、钨和钽的高达100 dpa高剂量下的辐照效应。实验结果表明国产改进型316奥氏体不锈钢辐照肿胀峰出现在辐照温度580℃处,辐照损伤对温度更灵敏;三种材料的辐照损伤产生的空位团尺寸随辐照剂量增加而增大,国产改进型316奥氏体不锈钢在这三种材料中辐照效应最小,钨最大。
【Abstract】 Structural materials in ITER,ADS and fast reactor suffer high dose irradiations of neutrons and/or protons,that leads to severe displacement damage up to 100 dpa per year.Investigation of radiation damage induced by such a high dose irradiation has attracted great attention along with the development of nuclear energy facilities of new generation.However,it is deeply hampered for the lacking of high dose neutron and proton sources.Irradiation simulation of heavy ions produced by accelerators opens up an effective way for laboratory investigation of high dose irradiation induced radiation damage encountered in the ITER,ADS,etc.Radiation damage is caused mainly by atomic displacement in materials.The displacement rate of heavy ions is about 10~3~10~7 orders higher than those of neutrons and protons.High displacement rate of heavy ions significantly reduces the irradiation time.The heavy ion irradiation simulation technique(HIIS) technique has been developed at China Institute of Atomic Energy and a series of the HIIS experiments have been performed to investigate radiation damage in stainless steels,tungsten and tantalum at irradiation temperatures from room temperature to 800 °C and in the irradiation dose region up to 100 dpa.The experimental results show that he radiation swelling peak for the modified stainless steel appears in the temperature region around 580 °C and the radiation damage is more sensitive to the temperature,the size of the radiation induced vacancy cluster or void increase with the increasing of the irradiation dose,and among the three materials the home-made modified stainless steel has the best radiation resistant property.
【Key words】 heavy ion irradiation simulation; radiation damage; nuclear energy structural materials; positron annihilation;
- 【会议录名称】 中国核科学技术进展报告(第三卷)——中国核学会2013年学术年会论文集第6册(核物理分卷、计算物理分卷、粒子加速器分卷)
- 【会议名称】中国核学会2013年学术年会
- 【会议时间】2013-09-11
- 【会议地点】中国黑龙江哈尔滨
- 【分类号】TL341
- 【主办单位】中国核学会