综述

核聚变堆偏滤器热沉材料研究现状及展望

  • 彭吴擎亮 ,
  • 李强 ,
  • 常永勤 ,
  • 王万景 ,
  • 陈镇 ,
  • 谢春意 ,
  • 王纪超 ,
  • 耿祥 ,
  • 黄伶明 ,
  • 周海山 ,
  • 罗广南
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  • 1.中国科学院合肥物质科学研究院 等离子体物理研究所 合肥 230031
    2.中国科学技术大学 合肥 230026
    3.北京科技大学 材料科学与工程学院 北京 100083
彭吴擎亮,男,1996年生,博士生

收稿日期: 2020-09-21

  修回日期: 2020-11-23

  网络出版日期: 2021-05-06

基金资助

国家自然科学基金项目(11875288)

A Review on the Development of the Heat Sink of the Fusion Reactor Divertor

  • Wuqingliang PENG ,
  • Qiang LI ,
  • Yongqin CHANG ,
  • Wanjing WANG ,
  • Zhen CHEN ,
  • Chunyi XIE ,
  • Jichao WANG ,
  • Xiang GENG ,
  • Lingming HUANG ,
  • Haishan ZHOU ,
  • Guangnan LUO
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  • 1.Institute of Plasma Physics, Hefei Institutes of Physical Science (HFIPS), Chinese Academy of Sciences, Hefei 230031, China
    2.University of Science and Technology of China, Hefei 230026, China
    3.School of Materials Science and Engineering, University of Science and Technology Beijing, Beijing 100083, China
LI Qiang, associate professor, Tel: (0551)65591507, E-mail: liqiang577@ipp.ac.cn

Received date: 2020-09-21

  Revised date: 2020-11-23

  Online published: 2021-05-06

Supported by

National Natural Science Foundation of China(11875288)

摘要

偏滤器是磁约束核聚变装置最为关键的系统之一,直接承受强粒子流和高热流的冲击,服役环境十分苛刻,而满足偏滤器运行环境的热沉材料是聚变堆正常运行的关键之一。受控核聚变领域近30年的研究和工程经验表明,铜合金以高热导率、较高的强度、较好的热稳定性和抗中子辐照性能被认为是聚变堆偏滤器用热沉材料的首要候选材料,也可能是水冷偏滤器热沉材料的唯一候选材料。但是,根据现有商用铜合金在下一代聚变堆(中国聚变工程试验堆(CFETR)和示范性聚变核电厂(DEMO))偏滤器模拟工况下的表现,发现其无法满足CFETR偏滤器的运行要求。目前,CFETR装置的设计和预研工作已经开展并按计划稳步推进,此时适用于高热负荷部件的热沉材料研制工作就显得十分重要。本文依据中国聚变能发展路线图,介绍了下一代聚变堆偏滤器热沉材料的服役工况及其对热沉材料的要求,对现有的铜合金在下一代聚变堆偏滤器运行环境下可能存在的问题进行综合评述,最后针对我国CFETR偏滤器热沉材料的相关问题提出了应对策略。

本文引用格式

彭吴擎亮 , 李强 , 常永勤 , 王万景 , 陈镇 , 谢春意 , 王纪超 , 耿祥 , 黄伶明 , 周海山 , 罗广南 . 核聚变堆偏滤器热沉材料研究现状及展望[J]. 金属学报, 2021 , 57(7) : 831 -844 . DOI: 10.11900/0412.1961.2020.00376

Abstract

Divertor is one of the most important components of the magnetic confinement fusion device, which directly sustains the strong particle flow and high heat load during a harsh service circumstance. The heat sink material that accommodates the operation circumstance of the divertor is one of the crucial prerequisites to perform the normal operation of a fusion reactor. The research and engineering experiences over the past three decades indicate that copper alloys are the best and probably the only material group for the heat sink of the water-cooled target of a divertor owing to its high thermal conductivity, strength, thermal stability, and radiation resistance. However, on account of its performance under the typical irradiation scenario of a divertor in the next step fusion reactor, none of the existing commercial copper alloys can satisfy both the harsh working environment and engineering building requirements in the Chinese Fusion Engineering Test Reactor (CFETR). At present, the design and research of CFETR devices have been conducted and is progressing steadily according to the proposal. Therefore, the development of high-performance copper alloys or copper matrix composites for high heat flux components is essential. In this study, the working condition of the heat sink in the next step fusion reactor divertor was first introduced according to the Roadmap of Fusion Energy of China. Thus, the performance requirements for the heat sink and its potential application limitations in the future fusion reactor divertor were reviewed. Finally, certain countermeasures regarding the heat sink materials were proposed for the CFETR divertor.

参考文献

1 Barbarino M. A brief history of nuclear fusion [J]. Nat. Phys., 2020, 16: 890
2 Knaster J, Moeslang A, Muroga T. Materials research for fusion [J]. Nat. Phys., 2016, 12: 424
3
4 Wan Y X, Li J G, Liu Y, et al. Overview of the present progress and activities on the CFETR [J]. Nucl. Fusion, 2017, 57: 102009
5 Li J G, Wan Y X. Present state of Chinese magnetic fusion development and future plans [J]. J. Fusion Energy, 2019, 38: 113
6 Wang L. Experimental Physics of Magnetic Confinement Plasmas [M]. Beijing: Science Press, 2018: 488
6 王 龙. 磁约束等离子体实验物理 [M]. 北京: 科学出版社, 2018: 488
7 Qiu L J. Fusion Energy Applications [M]. Beijing: Science Press, 2008: 204
7 邱励俭. 聚变能及其应用 [M]. 北京: 科学出版社, 2008: 204
8 Federici G, Skinner C H, Brooks J N, et al. Plasma-material interactions in current tokamaks and their implications for next step fusion reactors [J]. Nucl. Fusion, 2001, 41: 1967
9 Bolt H, Barabash V, Krauss W, et al. Materials for the plasma-facing components of fusion reactors [J]. J. Nucl. Mater., 2004, 329-333: 66
10 Raffray A R, Nygren R, Whyte D G, et al. High heat flux components—Readiness to proceed from near term fusion systems to power plants [J]. Fusion Eng. Des., 2010, 85: 93
11 Hirai T, Barabash V, Escourbiac F, et al. ITER divertor materials and manufacturing challenges [J]. Fusion Eng. Des., 2017, 125: 250
12 You J H. A review on two previous divertor target concepts for DEMO: Mutual impact between structural design requirements and materials performance [J]. Nucl. Fusion, 2015, 55: 113026
13 Federici G, Kemp R, Ward D, et al. Overview of EU DEMO design and R&D activities [J]. Fusion Eng. Des., 2014, 89: 882
14 Gilbert M R, Dudarev S L, Zheng S, et al. An integrated model for materials in a fusion power plant: Transmutation, gas production, and helium embrittlement under neutron irradiation [J]. Nucl. Fusion, 2012, 52: 083019
15 You J H, Mazzone G, Visca E, et al. Conceptual design studies for the European DEMO divertor: Rationale and first results [J]. Fusion Eng. Des., 2016, 109-111: 1598
16 You J H, Mazzone G, Bachmann C, et al. Progress in the initial design activities for the European DEMO divertor: Subproject “Cassette” [J]. Fusion Eng. Des., 2017, 124: 364
17 Fabritsiev S A, Pokrovsky A S. Effect of high doses of neutron irradiation on physico-mechanical properties of copper alloys for ITER applications [J]. Fusion Eng. Des., 2005, 73: 19
18 Singheiser L, Hirai T, Linke J, et al. Plasma-facing materials for thermo-nuclear fusion devices [J]. Trans. Indian Inst. Met., 2009, 62: 123
19 Li M Y, Werner E, You J H. Low cycle fatigue behavior of ITER-like divertor target under DEMO-relevant operation conditions [J]. Fusion Eng. Des., 2015, 90: 88
20 You J H. Copper matrix composites as heat sink materials for water-cooled divertor target [J]. Nucl. Mater. Energy, 2015, 5: 7
21 Mergia K, Boukos N. Structural, thermal, electrical and magnetic properties of Eurofer 97 steel [J]. J. Nucl. Mater., 2008, 373: 1
22 Tavassoli A A F, Rensman J W, Schirra M, et al. Materials design data for reduced activation martensitic steel type F82H [J]. Fusion Eng. Des., 2002, 61-62: 617
23 Ren C, Fang Z Z, Koopman M, et al. Methods for improving ductility of tungsten—A review [J]. Int. J. Refract. Met. Hard Mater., 2018, 75: 170
24 Obitz C, ?ijerholm J, Wikman S, et al. Erosion corrosion of CuCrZr specimens exposed for simulated ITER operational conditions [J]. Nucl. Mater. Energy, 2016, 9: 261
25 Maviglia F, Federici G, Strohmayer G, et al. Limitations of transient power loads on DEMO and analysis of mitigation techniques [J]. Fusion Eng. Des., 2016, 109-111: 1067
26 Ueda Y, Schmid K, Balden M, et al. Baseline high heat flux and plasma facing materials for fusion [J]. Nucl. Fusion, 2017, 57: 092006
27 ITER Organization. ITER material assessment report: 1.4. Selection of copper alloys [R]. G 74 MA 10 01-07-11 W0.2, 2001
28 Barabash V. Summary of materials properties for structural analysis of the ITER internal components [R]. ITER_D_23HL7T V 3.2, 2009
29 Xiang Z Q. A study on microstructures and high-temperature mechanical properties of Cu-Al2O3 dispersion strengthened copper [D]. Changsha: Central South University, 2014
29 向紫琪. Cu-Al2O3弥散强化铜合金的组织和高温力学性能研究 [D]. 长沙: 中南大学, 2014
30 Zhang J, Chang Y Q, Guo Z M, et al. Microstructure and nano-hardness of pure copper and ODS copper alloy under Au Ions irradiation at room temperature [J]. Acta. Metall. Sin. (Engl. Lett.), 2016, 29: 1047
31 Butterworth G J, Forty C B A. A survey of the properties of copper alloys for use as fusion reactor materials [J]. J. Nucl. Mater., 1992, 189: 237
32 Groza J R, Gibeling J C. Principles of particle selection for dispersion strengthened copper [J]. Mater. Sci. Eng., 1993, A171: 115
33 Ogbuji L U. The oxidation behavior of an ODS copper alloy Cu-Al2O3 [J]. Oxid. Met., 2004, 62: 141
34 Lee J, Kim Y C, Lee S, et al. Correlation of the microstructure and mechanical properties of oxide-dispersion-strengthened coppers fabricated by internal oxidation [J]. Metall. Mater. Trans., 2004, 35A: 493
35 Morrison A. Powder based processing of novel dispersion strengthened copper alloys for fusion applications [D]. Boston: University of Oxford, 2017
36 Fathy A, El-Kady O. Thermal expansion and thermal conductivity characteristics of Cu-Al2O3 nanocomposites [J]. Mater. Des., 2013, 46: 355
37 Kimmig S, Allen I, You J H. Strength and conductivity of unidirectional copper composites reinforced by continuous SiC fibers [J]. J. Nucl. Mater., 2013, 440: 272
38 Neu R, Riesch J, Müller A V, et al. Tungsten fibre-reinforced composites for advanced plasma facing components [J]. Nucl. Mater. Energy, 2017, 12: 1308
39 Wang P R, Liu F Q, Wang H, et al. A review of third generation SiC fibers and SiCf/SiC composites [J]. J. Mater. Sci. Technol., 2019, 35: 2743
40 You J H, Brendel A, Nawka S, et al. Thermal and mechanical properties of infiltrated W/CuCrZr composite materials for functionally graded heat sink application [J]. J. Nucl. Mater., 2013, 438: 1
41 Coenen J W, Mao Y, Sistla S, et al. Materials development for new high heat-flux component mock-ups for DEMO [J]. Fusion Eng. Des., 2019, 146: 1431
42 Kelly A, Zweben C. Comprehensive Composite Materials [M]. Amsterdam: Elsevier, 2000, 371
43 Zinkle S J, Fabritsiev S A. Copper-alloys for high heat-flux structure applications [J]. Nucl. Fusion, 1994, 5(suppl.): 163
44 T?htinen S, Pyykk?nen M, Roikonen P K, et al. Effect of neutron irradiation on fracture toughness behaviour of copper alloys [J]. J. Nucl. Mater., 1998, 258-263: 1010
45 Fabritsiev S A, Pokrovsky A S. Effect of irradiation temperature on microstructure, radiation hardening and embrittlement of pure copper and copper-based alloy [J]. J. Nucl. Mater., 2007, 367-370: 977
46 Fabritsiev S A, Zinkle S J, Singh B N. Evaluation of copper alloys for fusion reactor divertor and first wall components [J]. J. Nucl. Mater., 1996, 233-237: 127
47 Brager H R. Effects of neutron irradiation to 63 dpa on the properties of various commercial copper alloys [J]. J. Nucl. Mater., 1986, 141-143: 79
48 Brager H R, Heinisch H L, Garner F A. Effects of neutron irradiation at 450℃ and 16 dpa on the properties of various commercial copper alloys [J]. J. Nucl. Mater., 1985, 133-134: 676
49 You J H, Visca E, Barrett T, et al. European divertor target concepts for DEMO: Design rationales and high heat flux performance [J]. Nucl. Mater. Energy, 2018, 16: 1
50 Li M, Zinkle S J. Physical and mechanical properties of copper and copper alloys [J]. Compre. Nucl. Mater., 2012, 4: 667
51 Zinkle S J. Applicability of copper alloys for DEMO high heat flux components [J]. Phys. Scr., 2016, 2016: 014004
52 Li G, Thomas B G, Stubbins J F. Modeling creep and fatigue of copper alloy [J]. Metall. Mater. Trans., 2000, 31A: 2491
53 De Groh III H C, Ellis D L, Loewenthal W S. Comparison of GRCop-84 to other Cu alloys with high thermal conductivities [J]. J. Mater. Eng. Perform., 2008, 17: 594
54 Aitkhozhin E S, Chumakov E V. Radiation-induced creep of copper, aluminium and their alloys [J]. J. Nucl. Mater., 1996, 233-237: 537
55 Pokrovsky A S, Fabritsiev S A, Barabash V R, et al. Irradiation-induced low-temperature creep of DS copper alloy [J]. Plasma Devices Oper., 1999, 7: 313
56 Kalinin G, Matera R. Comparative analysis of copper alloys for the heat sink of plasma facing components in ITER [J]. J. Nucl. Mater., 1998, 258-263: 345
57 Li Q, Zhao S X, Sun Z X, et al. Development and application of W/Cu flat-type plasma facing components at ASIPP [J]. Phys. Scr., 2017, 2017: 014020
58 Wang P Y, Feng Y, Chen H D, et al. Study on high temperature mechanical properties and softening behavior of Al2O3 dispersion strengthened copper alloy rod [J]. Dev. Appl. Mater., 2017, 32(3): 46
58 王鹏云, 冯 岩, 陈会东等. Al2O3弥散强化铜棒材高温力学性能与软化行为研究 [J]. 材料开发与应用, 2017, 32(3): 46
59 Dong S J, Kelkar G P, Zhou Y. Electrode sticking during micro-resistance welding of thin metal sheets [J]. IEEE Trans. Electron. Pack. Manuf., 2002, 25: 355
60 Li M Y, Wang H, Guo Y H, et al. Microstructures and mechanical properties of the novel CuCrZrFeTiY alloy for fusion reactor [J]. J. Nucl. Mater., 2020, 532: 152063
61 Aghamiri S M S, Oono N, Ukai S, et al. Microstructure and mechanical properties of mechanically alloyed ODS copper alloy for fusion material application [J]. Nucl. Mater. Energy, 2018, 15: 17
62 Zhou D S, Geng H W, Zeng W, et al. High temperature stabilization of a nanostructured Cu-Y2O3 composite through microalloying with Ti [J]. Mater. Sci. Eng., 2018, A712: 80
63 Zhuo H O, Tang J C, Ye N, et al. A novel approach for strengthening Cu-Y2O3 composites by in situ reaction at liquidus temperature [J]. Mater. Sci. Eng., 2013, A584: 1
64 Muller A V, Ewert D, Galatanu A, et al. Melt infiltrated tungsten-copper composites as advanced heat sink materials for plasma facing components of future nuclear fusion devices [J]. Fusion Eng. Des., 2017, 124: 455
65 Domptail F, Barrett T R, Fursdon M, et al. The design and optimisation of a monoblock divertor target for DEMO using thermal break interlayer [J]. Fusion Eng. Des., 2020, 154: 111497
66 Li Q, Xie C Y, Wang W J, et al. Optimization of W/Cu monoblock mock-up with FGM interlayer for CFETR devertor targets [J]. Fusion Eng. Des., 2019, 147: 111262
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