Study of Radiation Damage of Materials Candidate to Advanced Nuclear Energy Systems by Utilizing High-Energy Heavy Ions at HIRFL
-
摘要: 载能重离子与高能中子在材料中能够产生相似的级联碰撞损伤，加之重离子具有大的离位损伤截面和在材料样品中低的感生放射性，载能重离子束成为模拟先进核能装置内部结构材料辐照损伤的重要手段。HIRFL能区的重离子在结构材料中的射程一般远大于晶粒尺寸，因此能够产生材料体损伤，借助小样品技术可以获得材料力学性能变化（尤其辐照脆化）的有用信息，为探讨材料辐照损伤微结构和宏观力学性能变化的关联提供了重要条件。本文简要介绍了近年来我们基于HIRFL高能离子束开展的聚变堆候选材料辐照损伤的研究，包括低活化钢的辐照脆化行为、氧化物弥散强化（ODS）铁素体钢的结构优化对于抗辐照性能的影响、不同载能粒子辐照条件下铁素体/马氏体钢的辐照肿胀数据的关联，以及高能重离子辐照的钨材料中氢同位素的滞留行为。研究表明，结合特殊的测试技术及数据分析方法，高能重离子可作为核能结构材料辐照损伤研究及评估的有效手段。
Because of the similarity in cascade damage structure in materials produced by energetic heavy ions and by fast neutrons, and the high displacement rate and low induced radioactivity of samples by heavy ions, heavy ion beam becomes an important tool to simulate radiation damage by energetic neutrons in materials in advanced nuclear energy systems. The ranges of heavy ions provided by HIRFL (Heavy Ion Research Facility in Lanzhou) are generally much larger than the mean dimensions of grains in alloys candidate to advanced nuclear reactors, and is capable of producing radiation damage in bulk scale. It therefore makes possible the evaluation of change of mechanical properties including the radiation induced embrittlement from the irradiated specimens by using miniaturized specimen techniques. In the present paper, we provide an introduction of our recent studies of radiation damage of materials candidate to future fusion reactors by utilizing heavy ion beams in HIRFL.The studies include issues as follows:ductility loss of RAFM steels causes by high-energy Ne ions, impact of oxide dispersoids on the radiation resistance of ODS ferritic steels, correlation of void swelling of ferritic/martensitic steels under different particle irradiation, and behavior of deuterium retention in tungsten under irradiation with high-energy heavy ions. The results show that high-energy heavy ions can be used as a tool to efficiently investigate or evaluate radiation damage in structure materials if combined with some special test techniques and data analysis.Abstract: Because of the similarity in cascade damage structure in materials produced by energetic heavy ions and by fast neutrons, and the high displacement rate and low induced radioactivity of samples by heavy ions, heavy ion beam becomes an important tool to simulate radiation damage by energetic neutrons in materials in advanced nuclear energy systems. The ranges of heavy ions provided by HIRFL (Heavy Ion Research Facility in Lanzhou) are generally much larger than the mean dimensions of grains in alloys candidate to advanced nuclear reactors, and is capable of producing radiation damage in bulk scale. It therefore makes possible the evaluation of change of mechanical properties including the radiation induced embrittlement from the irradiated specimens by using miniaturized specimen techniques. In the present paper, we provide an introduction of our recent studies of radiation damage of materials candidate to future fusion reactors by utilizing heavy ion beams in HIRFL.The studies include issues as follows:ductility loss of RAFM steels causes by high-energy Ne ions, impact of oxide dispersoids on the radiation resistance of ODS ferritic steels, correlation of void swelling of ferritic/martensitic steels under different particle irradiation, and behavior of deuterium retention in tungsten under irradiation with high-energy heavy ions. The results show that high-energy heavy ions can be used as a tool to efficiently investigate or evaluate radiation damage in structure materials if combined with some special test techniques and data analysis.-
Key words:
- heavy ion /
- nuclear reactor material /
- radiation damage
-
[1] ZINKLE S J, WAS G S. Acta Materialia, 2013, 61:735. [2] ZINKLE S J. Materials Today, 2009, 12:12. [3] MANSUR L K, ROWCLIFFE A F, NANSTAD R K, et al. Journal of Nuclear Materials, 2004, 329:166. [4] MAZEY D J. Journal of Nuclear Materials, 1990, 174:196. [5] WAS G S. Journal of Materials Research, 2015, 30(9):1158. [6] SCHROEDER H, KESTERNICH W, ULLMAIER H. Nuclear Engineering and Design Fusion, 1985, 2:65. [7] CHEN J, JUNG P, HOFFELNER W. Journal of Nuclear Materials, 2013, 441:688. [8] YAMAMOTO N, MURASE Y, NAGAKAWA J, et al. Journal of Nuclear Materials, 2002, 307:217. [9] HASEGAWA A, EJIRI M, NOGAMI S, et al. Journal of Nuclear Materials, 2009, 386-388:241. [10] ZHANG C H, YANG Y T, SONG Y, et al. Journal of Nuclear Materials, 2014, 455:61. [11] JUNG P, HISHINUMA A, LUCAS G E, et al. Journal of Nuclear Materials,1996, 232:186. [12] LUCAS G E, ODETTE G R, SOKOLOV M, et al. Journal of Nuclear Materials, 2002, 307-311:1600. [13] ZHANG H Q, ZHANG C H, YANG Y T, et al. Journal of Nuclear Materials, 2014, 455:349. [14] YANG Yitao, ZHANG Chonghong, DING Zhaonan, et al. Journal of Nuclear Materials, 2018, 498:129. doi: 10.1016/j.jnucmat.2017.10.025. [15] ODETTE G R, ALINGER M J, WIRTH B D. Annual Review of Materials Research, 2008, 38:471. [16] ZHANG C H, KIMURA A, KASADA R, et al. Journal of Nuclear Materials,2011, 417:221. [17] DING Z N, ZHANG C H, YANG Y T, et al. Journal of Nuclear Materials, 2017, 493:53. [18] XIAN Y Q, LIU Juan, ZHANG C H, et al. Journal of Nuclear Materials, 2015, 461:171. [19] ZHANG C H, CHEN K Q, WANG Y S, et al. Journal of Nuclear Materials, 2000, 283-287:259. [20] ZHANG C H, JANG J, CHO H D, et al. Journal of Nuclear Materials, 2008, 375:185. [21] ZHANG C H, JANG J, CHO H D, et al. Journal of Nuclear Materials, 2009, 386-388:457. [22] LIU Feng, XU Yuping, ZHOU Haishan, et al. Nucl Instr Meth B, 2015, 351:23. -
点击查看大图
计量
- 文章访问数: 1499
- HTML全文浏览量: 231
- PDF下载量: 121
- 被引次数: 0
下载:
甘公网安备 62010202000723号