核用碳化硅纤维增强碳化硅复合材料研究进展

doi:10.15541/jim20220145

无机材料学报 ›› 2022, Vol. 37 ›› Issue (8): 821-840.DOI: 10.15541/jim20220145

核用碳化硅纤维增强碳化硅复合材料研究进展

欧阳琴¹^,²(), 王艳菲¹^,², 徐剑¹^,², 李寅生¹, 裴学良¹^,², 莫高明¹^,², 李勉¹^,², 李朋¹, 周小兵¹^,², 葛芳芳¹^,², 张崇宏²^,³, 何流¹^,², 杨磊²^,³, 黄政仁¹^,², 柴之芳¹, 詹文龙²^,³, 黄庆¹^,²()

1.中国科学院宁波材料技术与工程研究所, 宁波 315201
2.先进能源科学与技术广东省实验室, 惠州 516000
3.中国科学院近代物理研究所, 兰州 730000

收稿日期:2022-03-16 修回日期:2022-05-11 出版日期:2022-08-20 网络出版日期:2022-05-15
通讯作者: 黄庆, 研究员. E-mail: huangqing@nimte.ac.cn
作者简介:欧阳琴(1981-), 男, 副研究员. E-mail: ouyangqin@nimte.ac.cn
基金资助:
宁波市“3315计划”A类创新团队和顶尖人才项目(2018A-03-A);先进能源科学与技术广东省实验室创新团队(HND20TDTHGC00);中国科学院战略性先导科技专项(A类)(XDA21010205)

Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application

OUYANG Qin¹^,²(), WANG Yanfei¹^,², XU Jian¹^,², LI Yinsheng¹, PEI Xueliang¹^,², MO Gaoming¹^,², LI Mian¹^,², LI Peng¹, ZHOU Xiaobing¹^,², GE Fangfang¹^,², ZHANG Chonghong²^,³, HE Liu¹^,², YANG Lei²^,³, HUANG Zhengren¹^,², CHAI Zhifang¹, ZHAN Wenlong²^,³, HUANG Qing¹^,²()

1. Ningbo Institute of Materials Technology & Engineering, Chinese Academy of Sciences, Ningbo 315201, China
2. Advanced Energy Science and Technology Guangdong Laboratory, Huizhou 516000, China
3. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China

Received:2022-03-16 Revised:2022-05-11 Published:2022-08-20 Online:2022-05-15
Contact: HUANG Qing, professor. E-mail: huangqing@nimte.ac.cn
About author:OUYANG Qin (1981-), male, associate professor. E-mail: ouyangqin@nimte.ac.cn
Supported by:
Ningbo “3315 Plan” Innovation Team Project and Top Talent Project(2018A-03-A);Advanced Energy Science and Technology Guangdong Laboratory(HND20TDTHGC00);CAS Priority Research program(XDA21010205)

摘要/Abstract

摘要：

碳化硅纤维增强碳化硅(SiC_f/SiC)复合材料具有低中子毒性、耐中子辐照和耐高温氧化等特性, 成为先进核能系统重要的候选结构材料。近年来, 国内外学术界和工业界针对核用SiC_f/SiC复合材料开展了大量研究工作, 取得了一系列重要的研究进展。针对SiC_f/SiC复合材料面向核用所关注的重点方向, 如核用SiC纤维、纤维/基体界面相、复合材料制备工艺、数值仿真、腐蚀行为和表面防护、连接技术以及辐照损伤等方面, 本文进行了综述和讨论, 并针对核用要求指出了SiC_f/SiC复合材料存在的主要问题和可能的解决思路, 希望对该材料的进一步研发和最终应用有所裨益。

关键词: 复合材料, 结构材料, 核材料, 碳化硅, 辐照损伤, 综述

Abstract:

Silicon carbide fiber reinforced silicon carbide (SiC_f/SiC) composites have become the preferred candidate for structural applications in advanced nuclear energy systems, because of their low neutron toxicity, neutron irradiation tolerance and high-temperature oxidation resistance. In recent years, both academia and industry either domestic or abroad have carried out a lot of researches on SiC_f/SiC composites for nuclear application, and numerous important achievements have been made. This paper summarized and analysed some critical directions of SiC_f/SiC composites for nuclear applications, including nuclear-grade SiC fibers, fibre/matrix interfaces, composite processing, modeling and simulation, corrosion behavior and surface protection, joining technology, as well as radiation damage. The key issues and potential solutions of SiC_f/SiC composites for nuclear applications have been pointed out in account to the requirements, anticipating to be beneficial to promoting further researches and final applications.

Key words: composite material, structural material, nuclear material, silicon carbide, radiation damage, review

中图分类号:

TQ174

欧阳琴, 王艳菲, 徐剑, 李寅生, 裴学良, 莫高明, 李勉, 李朋, 周小兵, 葛芳芳, 张崇宏, 何流, 杨磊, 黄政仁, 柴之芳, 詹文龙, 黄庆. 核用碳化硅纤维增强碳化硅复合材料研究进展[J]. 无机材料学报, 2022, 37(8): 821-840.

OUYANG Qin, WANG Yanfei, XU Jian, LI Yinsheng, PEI Xueliang, MO Gaoming, LI Mian, LI Peng, ZHOU Xiaobing, GE Fangfang, ZHANG Chonghong, HE Liu, YANG Lei, HUANG Zhengren, CHAI Zhifang, ZHAN Wenlong, HUANG Qing. Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application[J]. Journal of Inorganic Materials, 2022, 37(8): 821-840.

图/表 15

表1 核用第三代SiC纤维的主要性能[21-23]

Table 1 Key properties of the third-generation SiC fibers for nuclear application[21-23]

	Hi-Nicalon Type S	Tyranno SA
Fiber diameter/μm	12	10
Tow number	800	800
Linear density/(g·km^-1)	195	170
Bulk density/(g·cm^-3)	2.85	3.10
Tensile strength/GPa	3.1	2.4
Tensile modulus/GPa	380	380
Si content/(%, in mass)	69	67
C content/(%, in mass)	31	31
O content/(%, in mass)	0.8	<1
C/Si	1.05	1.08
Thermal conductivity/(W·m^-1·K^-1)	24	65

图1 采用不同SiC纤维增强CVI SiC复合材料经中子辐照后的SEM照片[9]

Fig. 1 SEM images of CVI SiC composites reinforced with different SiC fibers after neutron irradiation[9] (a) Hi-Nicalon Type S fiber; (b) Tyranno SA3 fiber

图2 以PyC为界面相的SiCf/SiC复合材料中子辐照前(a)和辐照后(b)的界面微观结构[35]

Fig. 2 Interfacial microstructures of SiCf/SiC composites with PyC as a interphase before (a) and after (b) neutron irradiation[35]

图3 开发用于高剂量辐照环境的SiCf/SiC复合材料对于界面相的性能和工艺要求[9]

Fig. 3 Performance and processing requirements for development of the interphase between fiber and matrix in SiCf/SiC composites for use in high-dose radiation environments[9]

图4 两种类型的包壳管致密化过程示意图(a~d), 纳米线增强SiC包壳管的微观结构((e)低倍率SEM照片, (f)纤维束间的SEM照片)[66]

Fig. 4 Schematic illustration of densification process of two types of cladding tubes (a-d) and microstructures of as- obtained three-layer-NWs SiC cladding tube (at low magnification (e) and intrabundle area (f) of the SiCf/SiC composite layer)[66] (a) Preform structure of the three-layer SiC cladding tube before CVI process; (b) Structure of the three-layer SiC cladding tube after CVI process; (c) Preform structure of the three-layer-NWs SiC cladding tube before CVI process; (d) Structure of the three-layer SiCNWs cladding tube after CVI process

图5 NITE工艺制备管状SiCf/SiC复合材料的新模具结构示意图(a)和模具及管状样品实物图片(b)[72]

Fig. 5 Schematic diagram of new graphite mold for preparing tubular SiCf/SiC composites via NITE process (a), and photograph of new graphite mold and tubular specimen (b)[72]

图6 包壳管成型工艺

Fig. 6 Cladding tube forming technology (a) Winding technology[88]; (b) Braiding technique[89]; (c) Winding mesostructure[88]; (d) Braided mesostructure[89]

图7 编织管与层合管在轴向的面内损伤系数(a)[88]和缠绕管与层合管在轴向的剪切安全系数(b)[89]

Fig. 7 In-plane damage factors of the braided tube yarn, braided tube matrix, and laminated tube on the hoop direction (a)[88] and safety factor of shear stress of the winding tube and laminated tube (b)[89]

图8 SiC在573 K和15 MPa水中的Pourbaix图[96]

Fig. 8 Pourbaix diagram of SiC in water at 573 K and 15 MPa and are water dissociation lines[96]

图9 不同类型SiC在热水腐蚀环境中的重量变化(a)和模拟PWR冷却环境的重量变化(b)[97]

Fig. 9 Weight changes of monolithic SiC ceramics in the hydrothermal corrosion environments (a) and corrosion rate of SiC ceramics in simulated PWR coolant environment without irradiation (b)[97]

图10 西屋双层SiC包壳管[103]

Fig. 10 Westinghouse duplex SiC cladding tube[103]

图11 多层SiC复合管腐蚀60 d后的宏观照片[97]

Fig. 11 Macrophotographies of the multi-layered SiC composite tubes after corrosion for 60 d[97]

图12 SiCf/SiC复合棒上(左)和CVD试样(右)沉积的CrN、Cr和TiN涂层的光学照片[116]

Fig. 12 Optical images of the as-deposited CrN, Cr and TiN coatings on SiC/SiC composite rods (left) and CVD samples (right)[116]

表2 几种典型的MAX相及其性能对比[158-162]

Table 2 Comparison of related properties of several typical MAX phases[158-162]

Material	Vickers hardness/ GPa	Flexural strength/ MPa	Fracture toughness/ (MPa·m^1/2)	Thermal conductivity/ (W·m^-1·K^-1)	Electrical conductivity/ (×10⁶, S·m^-1)
Ti₃SiC₂	10.4	881(//c-axis)	14.1(//c-axis)	32.4	0.49(//c-axis)
Ti₃AlC₂	9.1	1261(//c-axis)	13.1(//c-axis)	14.6(//c-axis)	1.01(//c-axis)
Ti₂AlC	7.9	735(//c-axis)	8.5(//c-axis)	27	2.5
Nb₄AlC₃	7.0	789(⊥c-axis)	9.3(⊥c-axis)	21.1	0.81

图13 不同温度下连接的SiC/Yb/SiC的低倍和高倍背散射(BSE)图[157]

Fig. 13 Low and high magnification back-scattered electron (BSE) images of the SiC/Yb/SiC joints joined at different temperatures[157] (a, f) 1200 ℃; (b, g) 1400 ℃; (c, h) 1500 ℃, (d, i) 1700 ℃; (e, j) 1500 ℃ (dwell time of 15 min)

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核用碳化硅纤维增强碳化硅复合材料研究进展

Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application

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