高温反应堆用镍基合金辐照性能的研究进展及改性方向研究

doi:10.11896/cldb.24110035

材料导报

2026, Vol. 40

Issue (6): 24110035-8 https://doi.org/10.11896/cldb.24110035

金属与金属基复合材料

高温反应堆用镍基合金辐照性能的研究进展及改性方向研究

王优, 林基伟, 王晨, 卢俊强^*

上海核工程研究设计院股份有限公司燃料材料所,上海 200233

Research and Modification Direction of Irradiation Resistance of Nickel-based Alloy in High Temperature Nuclear Reactor

WANG You, LIN Jiwei, WANG Chen, LU Junqiang^*

Department of Fuel and Materials, Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai 200233, China

摘要
参考文献
相关文章
推荐阅读
Metrics

下载:

全文 ( PDF ) ( 18693KB )
输出: BibTeX | EndNote (RIS)

摘要本文深入分析了镍基合金在高温反应堆环境下的耐辐照损伤机制,包括辐照肿胀、辐照脆化和辐照硬化等问题。通过综合分析合金成分、制造工艺以及辐照环境因素,提出了一系列改性策略,旨在提高镍基合金的抗辐照性能。这些策略包括精确调控合金成分以减少氦原子的生成、优化制造工艺以抑制氦泡的聚集与长大、以及避免溶质元素和缺陷的晶界偏析。研究还探讨了引入第二相颗粒,如碳化物和氧化物,以有效捕获和钉扎氦泡,减少氦脆风险。此外,通过高温退火处理降低材料内部应力和缺陷,进一步增强了材料的抗辐照性能。这些研究成果为开发适用于高温反应堆的高性能核用镍基合金提供了重要的理论依据和技术支持,对于确保核反应堆的安全、稳定和长期运行具有重要意义。

	服务
	把本文推荐给朋友
	加入引用管理器
	E-mail Alert
	RSS
	作者相关文章
	王优
	林基伟
	王晨
	卢俊强

关键词: 高温反应堆镍基合金辐照脆化改性方向

Abstract: In this paper, the irradiation resistance mechanisms of nickel-based alloys under high-temperature reactor conditions were comprehensively investigated, particularly focused on addressing irradiation-induced swelling, embrittlement, and hardening. Through systematic analysis of alloy composition, manufacturing processes, and irradiation parameters, a series of modification strategies have been developed to enhance irradiation tolerance. It includes precise compositional tuning to suppress helium generation, optimized processing techniques to impede helium bubble coalescence and coarsening, and strategic grain boundary engineering to mitigate solute segregation and defect accumulation. Innovatively, the research explores incorporating secondary-phase particles(carbides/oxides) to effectively trap and pin helium bubbles, thereby reducing helium embrittlement susceptibility. High-temperature annealing treatments further enhance radiation resistance by relieving internal stresses and reducing crystalline defects. These findings establish critical theoretical foundations and provide advanced technical pathways for developing next-generation nuclear-grade nickel-based alloys suitable for high-temperature reactors. The proposed methodologies offer substantial engineering significance for ensuring safe, stable, and extended operation of nuclear reactor systems.

Key words: high-temperature nuclear reactors nickel-based alloy irradiation-induced embrittlement modification

出版日期: 2026-03-25 发布日期: 2026-04-03

ZTFLH:

TL341

基金资助: 国家科技重大专项(2024ZD0600200);上海市科技创新行动启明星项目(24YF2718700);中国科协青年人才托举项目(YESS20240818)

通讯作者: ^*卢俊强,博士,上海核工程研究设计院股份有限公司燃料材料所正高级工程师。目前主要从事新型核燃料与材料研究工作,承担压水堆重大专项课题和重点新材料研发及应用项目课题等。lujunqiang@snerdi.com.cn

作者简介: 王优,博士,上海核工程研究设计院股份有限公司燃料材料所工程师,目前主要从事先进核能系统用核燃料材料设计与使役性能研究。

引用本文:

王优, 林基伟, 王晨, 卢俊强. 高温反应堆用镍基合金辐照性能的研究进展及改性方向研究[J]. 材料导报, 2026, 40(6): 24110035-8.
WANG You, LIN Jiwei, WANG Chen, LU Junqiang. Research and Modification Direction of Irradiation Resistance of Nickel-based Alloy in High Temperature Nuclear Reactor. Materials Reports, 2026, 40(6): 24110035-8.

链接本文:

https://www.mater-rep.com/CN/10.11896/cldb.24110035 或 https://www.mater-rep.com/CN/Y2026/V40/I6/24110035

1 Lu Y L, Chen L J, Liaw P K, et al. Materials Science & Engineering A, 2006, 429(1), 1.
2 Zhang T, Wei Z G, Tian L N, et al. Inner Mognolia Electric Technology, 2015(5), 20(in Chinese)
张涛, 卫志刚, 田力男, 等. 内蒙古电力技术, 2015(5), 20.
3 Mo K, Lv W, Tung H M, et al. Journal of Engineering Materials and Technology-Transactions of the ASME, 2016, 138(3), 031015.
4 Muralidharan G, Keiser J, Raiman S, et al. Oak Ridge National Laboratory, US, 2021, pp.1.
5 Jnucmat J. Journal of Nuclear Materials, 2007, 366, 23.
6 Zhou X T, Luo F F. Jiangxi Science, 2020, 38(2), 135(in Chinese).
周兴泰, 罗凤凤. 江西科学, 2020, 38(2), 135.
7 Jiang Z, Xu Z F, Li Z J, et al. In: 8 Pacific Rim International Congress on Advanced Materials and Processing, Hawaii, 2013, pp.125.
8 Xu Z, Xu F, Jiang L, et al. Journal of Alloys & Compounds, 2015, 620, 197.
9 Xu Z F, Dong J S, Jiang L, et al. Acta Metallurgica Sinica(English Letters), 2015, 8, 951.
10 Murty K L, Charit I. Germany:Wiley-VCH Verlag, 2013, pp. 398.
11 Zinkle S J, Steven J. Elsevier, Germany, 2012, pp.65.
12 Zinkle S J, Was G S. Acta Materialia, 2013, 61, 735.
13 Zinkle S J, Matsukawa Y. Journal of Nuclear Materials, 2004, 329, 88.
14 Budylkina N I, Mironovaa E G, Chernov V M, et al. Journal of Nuclear Materials, 2008, 375, 359.
15 Johnston W G, Rosolowski J H, Turalo A M, et al. Journal of Nuclear Materials, 1972, 54(1), 24.
16 Ying H, Wen A L, Zhou M R, et al, Nuclear Technology, 2023, 46(12), 120301(in Chinese).
应红, 温阿利, 周岁茹, 等. 核技术, 2023, 46(12), 120301.
17 Zhao P F, Zhu H Y, Hou K L, et al. Journal of Materials Research and Technology, 2023, 27, 1214.
18 Nanstad R K, McClintock D A, Hoelzer D T, et al. Journal of Nuclear Materials, 2009, 392, 331.
19 Barnaby J, Barton P J, Boothby R M, et al. Radiation Effects in Breeder Reactor Structural Materials, 1977, pp. 159.
20 Griffiths M, Boothby R M. Comprehensive Nuclear Materials, 2020, 3, 334.
21 Zhu Z B, Ji W C, Huang H F. Journal of Nuclear Materials, 2022, 560, 153506.
22 He Z Y, Jiang Y, Chang L T, et al. Journal of Nuclear Materials, 2023, 589, 154871.
23 Trinkaus H, Singh B N. Journal of Nuclear Materials, 2003, 323(2-3), 229.
24 Boothby R M. Journal of Nuclear Material, 1996, 230(2), 148.
25 Martínez E, Uberuaga B P, Wirth B D. Nuclear Fusion, 2017, 57(8), 086044.
26 Kramer D, Garr K, Rhodes C, et al. Journal of Nuclear Materials, 1968, 25(2), 121.
27 Trinkaus H. Radiation Effects, 1987, 101, 91.
28 Nichols F A. Journal of Nuclear Materials, 1969, 30, 143.
29 Greenwood G W, Boltax A. Journal of Nuclear Materials, 1962, 5, 234.
30 Lei G H. The effect of molten salt environment on the high-temperature helium behaviors of GH3535 alloy. Ph. D. Thesis, University of Chinese Academy of Sciences, China, 2019(in Chinese).
雷冠虹. 熔盐环境对GH3535合金高温He行为影响的研究. 博士学位论文. 中国科学院大学, 2019.
31 Liu C P, Ye X X, Huang H F. Scripta Materialia, 2025, 256, 116431.
32 Njifon I C, Gabriel J J, Torres E. Journal of Nuclear Material, 2025, 614, 155882.
33 McCoy H E. Oak Ridge National Laboratory, US, 1997, pp.1.
34 Xu S, Zhou Z J, Long F, et al. Advanced Engineering Materials, 2019, 22(4), 1900879.
35 Hou P Y, Stringer J. Materials Science and Engineering:A, 1995, 202, 1.
36 Bruemmer S M, Simonen E P, Scott P M, et al. Journal of Nuclear Materials, 1999, 274, 299.
37 Schroeder H, Batfalsky P. Journal of Nuclear Material, 1983, 117, 287.
38 Habiyaremyea F, Roulanda S, Radiguet B, et al. Journal of Nuclear Material, 2025, 607, 155710.
39 Yi Y J. Theoretical studies on stabilities and high-temperature elastic properties of carbides in Ni-based superalloys. Master's Thesis, Xiamen University, China, 2017(in Chinese).
易毅杰. 镍基合金中碳化物稳定性及高温弹性性能的理论研究. 硕士学位论文, 厦门大学, 2017.
40 Gao J. Evolution mechanisms of helium bubbles in nickel and nickel-based alloy. Ph.D.Thesis, University of Chinese Academy of Sciences, China, 2019(in Chinese).
高杰. 镍及镍基合金内氦泡演化行为研究. 博士学位论文, 中国科学院大学, 2019.
41 Bajaj R, Shogan R P, DeFlitch C, et al. In:Proceedings of the 10th International Symposium on Effect of Radiation on Material. Bleiberg, 1981, pp. 326.
42 Zhu Z B. Study on irradiation optimization and screening of structural materials for molten salt reactor. Ph.D.Thesis, University of Chinese Academy of Sciences, China, 2022(in Chinese).
朱振博. 熔盐堆用合金结构材料辐照优化筛选研究. 博士学位论文, 中国科学院大学, 2022.
43 Trinkaus H. Journal of Nuclear Materials, 1985, 133-134, 105.
44 Yang T N, Lu C Y, Velisa G, et al. Acta Materialia, 2018, 151, 159.
45 Zhang Y, Zhao S, Weber W J, et al. Current Opinion in Solid State and Materials Science, 2017, 21, 221.
46 Tucker J D, Najafabadi R, Allen T R, et al. Journal of Nuclear Materials, 2010, 405, 216.
47 Trinkaus H. Scripta Metallurgica, 1989, 23(10), 1773.
48 Tang R Z, Tian R Z. Binary alloy phase diagrams and crystal structure of intermediate phase. Central South University Press, China, 2009, pp. 1576(in Chinese).
唐仁政, 田荣璋. 二元合金相图及中间相晶体结构. 中南大学出版社, 2009, pp. 1576.
49 Oono N, Ukai S, Kondo S, et al. Journal of Nuclear Materials, 2015, 465, 835.

[1]	赵永福, 唐敏, 姜峨, 银朝晖, 陈子瑞, 张根, 吴宗佩, 李杨. 氨型碱性水化学对690TT腐蚀特性的影响[J]. 材料导报, 2024, 38(7): 23030048-6.
[2]	朱凯涛, 董多, 杨晓红, 朱冬冬, 王晓红, 马腾飞. GH4169/BNi-7钎焊接头的显微组织、力学性能和腐蚀行为[J]. 材料导报, 2024, 38(24): 23100078-8.
[3]	李孝晨, 丁文艺, 朱霄汉, 郑明杰. 基于机器学习的RAFM钢中子辐照脆化预测模型研究[J]. 材料导报, 2023, 37(1): 22010142-7.
[4]	徐秀清, 王玮, 陈之腾, 李云, 胡海军. 加氢换热器用321不锈钢、镍基合金825氢脆敏感性研究[J]. 材料导报, 2022, 36(14): 21030183-6.
[5]	唐紫苑, 张淑婷, 杜开平, 宣鹏举, 司丽娜. 包埋渗技术在镍基高温合金中的应用[J]. 材料导报, 2021, 35(Z1): 389-394.
[6]	曾小川, 李学军, 邓小云, 胡侨丹, 尤磊. SA508 Gr.4N钢的辐照脆化性能研究进展[J]. 材料导报, 2021, 35(Z1): 438-442.
[7]	初铭强, 丁仁根, 张书彦, 郑江鹏, 张楠. 航空零部件加工表面完整性[J]. 材料导报, 2021, 35(7): 7183-7189.
[8]	马文彬, 郭京京, 骆红云, 唐君, 杨晓光. 低塑性加工对定向凝固镍基合金DZ125高温氧化性能的影响[J]. 材料导报, 2020, 34(10): 10093-10097.
[9]	范舟, 黄泰愚, 刘建仪. 硫对镍基合金825(100)电子结构影响的密度泛函研究[J]. 材料导报, 2019, 33(z1): 332-336.
[10]	平学龙, 符寒光, 孙淑婷. 激光熔覆制备硬质颗粒增强镍基合金复合涂层的研究进展[J]. 材料导报, 2019, 33(9): 1535-1540.
[11]	朱红梅, 李柏春, 朱锦云, 邱长军, 唐忠锋. 熔盐堆用镍基合金在熔融氟盐中的腐蚀研究进展[J]. 材料导报, 2019, 33(11): 1813-1820.
[12]	苏义祥, 张志坚, 邱晓来, 刘解放, 申楠, 刘世铎. Cr₃C₂对45钢表面超音速火焰喷涂制备的Ni基合金涂层热态抗磨损性能的影响[J]. 材料导报, 2018, 32(6): 899-904.

[1]	Yanzhen WANG, Mingming CHEN, Chengyang WANG. Preparation and Electrochemical Properties Characterization of High-rate SiO₂/C Composite Materials[J]. Materials Reports, 2018, 32(3): 357 -361 .
[2]	Yimeng XIA, Shuai WU, Feng TAN, Wei LI, Qingmao WEI, Chungang MIN, Xikun YANG. Effect of Anionic Groups of Cobalt Salt on the Electrocatalytic Activity of Co-N-C Catalysts[J]. Materials Reports, 2018, 32(3): 362 -367 .
[3]	Qingshun GUAN,Jian LI,Ruyuan SONG,Zhaoyang XU,Weibing WU,Yi JING,Hongqi DAI,Guigan FANG. A Survey on Preparation and Application of Aerogels Based on Nanomaterials[J]. Materials Reports, 2018, 32(3): 384 -390 .
[4]	Wen XI,Zheng CHEN,Shi HU. Research Progress of Deformation Induced Localized Solid-state Amorphization in Nanocrystalline Materials[J]. Materials Reports, 2018, 32(1): 116 -121 .
[5]	Laima LUO, Mengyao XU, Xiang ZAN, Xiaoyong ZHU, Ping LI, Jigui CHENG, Yucheng WU. Progress in Irradiation Damage of Tungsten and Tungsten AlloysUnder Different Irradiation Particles[J]. Materials Reports, 2018, 32(1): 41 -46 .
[6]	Fengsen MA,Yan YU,Jie ZHANG,Haibo CHEN. A State-of-the-art Review of Cytotoxicity Evaluation of Biomaterials[J]. Materials Reports, 2018, 32(1): 76 -85 .
[7]	Huimin PAN,Jun FU,Qingxin ZHAO. Sulfate Attack Resistance of Concrete Subjected to Disturbance in Hardening Stage[J]. Materials Reports, 2018, 32(2): 282 -287 .
[8]	Acidifier at High Temperature SiO2Bearing, , , , . Research on Stabilization of Free CaO in Basic Oxygen Furnace Slag with[J]. Materials Reports, 2018, 32(2): 301 -306 .
[9]	Ziming LIU,Huaxin CHEN,Rui XIONG,Yongdan WANG,Xiaowen WANG. Experimental Investigation on Properties of Steel Wool Fiber/Brucite Fiber Reinforced Asphalt Mortar[J]. Materials Reports, 2018, 32(2): 295 -300 .
[10]	ZHANG Hehe, LI Fangfang, WANG Haiyan, PENG Zhiguang, TANG Yougen. Iron Electrode Derived from Fe/Co-MOF and Its Electrochemical Performance for Nickel-Iron Batteries[J]. Materials Reports, 2018, 32(5): 719 -724 .

Viewed

Full text

Abstract

Cited

Shared

Discussed