Research Progress and Technological Development Trend of Accident Tolerant Fuel
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摘要: 耐事故燃料（ATF）研发已成为后福岛时代国际燃料界一个新的研究方向，其内容涉及先进包壳材料、新型燃料的研发。经过十余年的全面系统研究，以美国、法国为代表的国际核燃料界在近期解决技术方案上取得了重要进展，对中远期的技术方向也更加聚焦。本文主要综述了国内外在ATF包壳材料（包括Cr涂层、FeCrAl合金与SiC复合材料）、燃料方面[包括增强型UO2、高铀密度燃料和陶瓷基包覆颗粒弥散（CDM）燃料]研究取得的重要进展、面临的挑战及后续技术发展趋势。
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关键词:
- 耐事故燃料（ATF） /
- Cr涂层锆合金 /
- 增强型UO2芯块 /
- 陶瓷基包覆颗粒弥散（CDM）燃料
Abstract: The research and development of accident tolerant fuel (ATF) has become a new research direction in the international fuel industry in the post-Fukushima era, which involves the research and development of advanced cladding materials and new nuclear fuels. After more than ten years of comprehensive and systematic research, the international nuclear fuel industry represented by the U.S. and France have gained important progress, focusing further on medium and long-term technical solutions. In this paper, the important progress, challenges and development trend of subsequent technologies in ATF cladding materials (including Cr coating, FeCrAl alloy and SiC composite) and fuels (including enhanced UO2, high uranium density fuel and ceramic dispersive matrix dispersion (CDM) fuel) at home and abroad are reviewed.-
Key words:
- ATF /
- Cr coated-zirconium alloy /
- Enhanced UO2 pellet /
- CDM fuel
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图 2 法马通公司制备的ATR辐照用SiC小棒与西屋公司制备的双层SiC包壳管
Figure 2. ATR SiC Irradiation Rods Made by Framatome and SiC Double-layered Cladding Tube Made by Westinghouse
表 1 Cr涂层包壳材料堆外性能试验与评价
Table 1. Out-of-pile Performance Test and Evaluation of Cr-coated Cladding
技术指标 NPIC 国外 长度 全尺寸制备能力 全尺寸制备能力 物相结构 涂层为物相单一的Cr金属 涂层为物相单一的Cr金属 结合质量 不同变形量拉伸压扁下涂层目视无裂纹剥落 不同变形量拉伸压扁下涂层目视无裂纹剥落 厚度 10~20 μm 5~80 μm 耐高温氧化性能 比锆合金低1个数量级 比锆合金低1个数量级 耐腐蚀性能 比锆合金低约2个数量级 比锆合金低约2个数量级 抗热冲击性能 1200℃涂层完好 暂无报道 耐摩擦磨损性能 优于锆合金 优于锆合金 力学拉伸性能 室温抗拉强度约500 MPa 室温抗拉强度约500 MPa 抗内压爆破性能 44.4 MPa（400℃） 35 MPa（940℃，80 μm） 耐蠕变性能 径向应变0.69%（400℃, 130 MPa） 径向应变0.57%~0.7% （385℃, 107.5 MPa） 
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表 2 FeCrAl包壳材料堆外性能试验与评价
Table 2. Out-of-pile Performance Test and Evaluation of FeCrAl Cladding
技术指标 NPIC 国外 包壳管尺寸 长 4 m、直径9.5 mm、壁厚0.37~0.40 mm的管材 长4 m、直径9.5 mm、壁厚<0.40 mm的管材 拉伸性能（室温） 屈服强度约720 MPa 屈服强度约600 MPa 抗拉强度约880 MPa 抗拉强度约800 MPa 耐高温水蒸气氧化性能 平衡常数（Kp）值量级为10−11~10−13，比锆合金低4个数量级 Kp值量级为10−11~10−13，比锆合金低4个数量级 耐均匀腐蚀性能 300 d腐蚀后的增重为5~7 mg/dm2，比锆合金低1个数量级 300 d腐蚀后的增重为1~5 mg/dm2，比锆合金低1个数量级 蠕变性能 蠕变指数16.76 蠕变指数10~20 辐照考验 开展了板材、管材离子辐照、中子辐照（研究堆） 开展了板材离子辐照、中子辐照（商用沸水堆）
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表 3 SiC复合包壳堆外性能试验与评价
Table 3. Out-of-pile Performance Test and Evaluation of SiC Composite Cladding
技术指标 NPIC 国外 包壳管长度/m 1.5 4 密度/(g·cm−3) >2.8 >2.7 开孔孔隙率/% 约10 约10 壁厚/mm 0.8与1 0.7~2.1 轴拉强度/MPa 240~270 230~270 环拉
强度/MPa240 200~340 气密性/
(Pa·m3·s−1)约10−10 约10−3（带端塞）
约10−10（热循环后）腐蚀失重/
(mg·dm−2·d−1)0.23（含氧水环境） 0.02（电站水环境） 热导率/
(W·m−1·K−1)11 8.5~13 热膨胀系数/
(10−6·K−1)3.8~4.6（室温~1300℃） 2.5~6.5（300~1400℃）
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表 4 几种燃料热物理性能对比
Table 4. Physical Performance Comparison of Nuclear Fuels
物理性能 UO2 U3Si2 UN 密度/(g·cm−3) 10.96 12.2 14.3 铀密度/[g(U)·cm−3] 9.66 13.52 11.31 热导率(673~1473 K)/(W·m−1·K−1) 6~2.5 13.0~22.3 15~27.3 熔点/K 3130 1938 2953
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表 5 UN-CDM燃料芯块部分堆外性能对比
Table 5. Out-of-pile Performance Comparison of UN-CDM Fuel Pallet between NPIC and Abroad
物项 NPIC 国外 UN微球 碳铀比≥2.6
铀含量≥94.2%
密度：90%T.D.碳铀比≥2.6（ORNL）
铀含量≥94%
密度：92%T.D.TRISO SiC涂层 密度：约3.0 g/cm3
热膨胀系数：约5×10−6℃−1密度：约3.2 g/cm3（ORNL，法马通公司）
热膨胀系数：约5.11×10−6℃−1CDM芯块 相体积分数：约38%
基体密度：95%T.D.相体积分数：约45%（ORNL，法马通公司）
基体密度：97%T.D.
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表 6 ATF及包壳材料的主要特点及发展阶段
Table 6. Major Pros and Cons of ATF and Claddings and Corresponding Development Stage
物项 优势 劣势 技术路线发展阶段 包壳 Cr涂层锆合金 锆合金包壳体系成熟，商业化应用速度快 仍有锆水反应风险 近期 FeCrAl合金 导热性好，热膨胀系数小，抗氧化、耐腐蚀 中子吸收截面较大，塑性加工困难，成型难度大 中远期 SiC复合材料 基础性能优异，高温下蒸汽氧化速率低、强度高、化学性能稳定，极端工况下安全系数高 耐水热腐蚀性能不佳 中远期 燃料 增强型UO2 密度更合理、晶粒尺寸更大，提升燃料芯块导热性能，减弱PCI 铀密度提升存在上限 近期 高铀密度燃料 铀密度高、导热性能好 铀硅化物熔点偏低，UN燃料耐水腐蚀性差 中远期 CDM燃料 具备超强的裂变气体包容能力，抗辐照性能优异 铀装量低 中远期
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