Preliminary Analytical Study of the Effect of Accident Tolerant Fuel on Fuel Rod Performance under LOCA Condition
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摘要: 事故容错燃料（ATF）包壳材料是在福岛核事故后为了提高燃料元件抵御严重事故的性能而提出的新一代核燃料概念，与目前的Zr-4合金包壳相比，ATF包壳材料能够在较长时间内抵御事故后果，同时还能保持或提高其在正常运行工况下的性能。基于FRAPTRAN-2.0程序，针对两种ATF包壳材料（FeCrAl和SiC），通过改进包壳材料热物性模型、包壳力学行为模型和氧化模型，开发了适用于ATF包壳材料的燃料棒性能瞬态分析程序。以MT-1实验台架的燃料棒为对象，对其失水事故（LOCA）工况进行计算分析，研究了ATF包壳材料在该事故工况下的热工水力瞬态响应特性。结果表明，相比传统的Zr-4合金包壳，ATF包壳材料不仅可以降低LOCA下的包壳峰值温度，还能延缓或防止包壳失效。
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关键词:
- 事故容错燃料（ATF） /
- 失水事故（LOCA） /
- FRAPTRAN-2.0 /
- 燃料棒性能分析
Abstract: Accident tolerant fuel (ATF) cladding material is a new generation of nuclear fuel concept proposed after the Fukushima nuclear accident to improve the performance of fuel elements against severe accidents. Compared with the current Zr-4 alloy cladding material, ATF cladding material can resist the consequences of accidents for a long time, while maintaining or improving its performance under normal operating conditions. In this paper, based on the code FRAPTRAN-2.0 and two ATF cladding materials (FeCrAl and SiC), a transient analysis code of fuel rod performance for ATF cladding materials was developed by improving the thermalphysical model, mechanical behavior model and oxidation model of cladding materials. Then the fuel rods of the MT-1 experimental stand were used as the objects for the computational analysis of its LOCA condition, and the thermal-hydraulic transient response characteristics of ATF cladding materials under this condition are studied. The analysis results show that compared with the conventional Zr-4 alloy cladding, the ATF cladding material can not only reduce the peak cladding temperature (PCT) under LOCA, but also delay or prevent cladding failure. -
图 2 FeCrAl材料与Zr-4材料屈服应力的对比
RXA Zr-2和SRA Zr-4为锆合金材料；T35Y2、C35M和APM/APMT为FeCrAl合金材料
Figure 2. Comparison of Yield Srength between FeCrAl and Zr-4 Alloys
图 3 基于UTS准则和Tresca准则模拟的FeCrAl包壳爆裂失效时环向应力、棒内压力与实验数据的对比
Figure 3. Comparison of Hoop Stress and Rod Internal Pressure at Burst of FeCrAl Cladding Based on UTS and Tresca Failure Criteria with Experimental Data
图 5 爆裂节点处不同材料的芯块中心和包壳表面温度
Figure 5. Pellet Center and Cladding Surface Temperatures of Different Cladding Materials at Burst Nodes
图 6 ATF材料和Zr-4合金材料的体积热容
Figure 6. Volumetric Heat Capacity of ATF Cladding Materials and Zr-4 Alloy Materials
图 8 爆裂节点处不同材料的包壳环向应变
Figure 8. Hoop Strain of Different Cladding Materials at Burst Nodes
图 9 爆裂节点处不同材料的包壳环向应力
Figure 9. Hoop Stress of Different Cladding Materials at Burst Nodes
图 10 爆裂节点处不同材料的气体间隙宽度
Figure 10. Gap Width of Different Cladding Materials at Burst Nodes
图 11 爆裂节点处不同材料的气体间隙压力
Figure 11. Gap Pressure of Different Cladding Materials at Burst Nodes
图 12 爆裂节点处不同材料的间隙传热系数
Figure 12. Gap Heat Transfer Coefficient of Different Cladding Materials at Burst Nodes
图 13 爆裂节点处不同包壳材料氧化层厚度（外侧）
Figure 13. Oxide Layer Thickness of Different Cladding Materials at Burst Nodes
图 14 CVD SiC氧化层生成和挥发厚度变化
Figure 14. Variation of Oxide Layer Generation and Volatilization Thickness of CVD SiC
表 1 氧化动力学方程常数表
Table 1. Constants of Oxidation Kinetic Equation
常数 C-P模型 B-J模型 A 2.252×10−5 m2/s 9.425×10−5 m2/s B 3.5889×104 cal/mol 4.55×104 cal/mol C 1.987 cal/(mol·K) 1.987 cal/(mol·K) 1 cal=4.186 J 
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表 2 不同研究中单体SiC包壳材料的力学性能
Table 2. Mechanical Properties of Monolayer SiC Cladding Materials
参数名称 CVD SiC CVi SiC NITE SiC UTS/MPa 200~600 209~468 305~710 PLS/MPa 369 90~120, 290~344 137~517 弹性模量E/GPa 460 254~380 160~288 泊松比µ 0.21 0.13 0.13 韦伯模量 7.5 3.7~11 NITE—纳米浸渍与瞬态共晶法；CVi—化学气相渗透法
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表 3 MT-1实验燃料棒设计参数
Table 3. MT-1 Test Fuel Rod Design Parameters
设计参数 参数值及类型 包壳材料类型 Zr-4 包壳外直径/cm 0.963 包壳内直径/cm 0.841 间隙宽度/mm 0.0749 芯块外直径/cm 0.826 芯块高度/cm 0.953 燃料棒活性段长度/m 3.658 燃料棒上部腔室长度/cm 24.5 栅格间距/cm 1.275 燃料棒内压/MPa 1.55
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表 4 不同包壳材料包壳爆裂时间和位置
Table 4. Time and Location of Cladding Burst for Different Cladding Materials
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表 5 包壳峰值温度和相对高度
Table 5. Peak Temperature and Corresponding Height of Cladding
包壳材料 峰值温度/K 相对高度/m Zr-4 1142.5 2.5908 CVD SiC 1058.5 1.9812 FeCrAl 1138.1 2.286
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表 6 爆裂节点处不同包壳材料氧化层厚度
Table 6. Oxide Layer Thickness of Different Cladding Materials at Burst Nodes
包壳材料 氧化层厚度（外）/mm 氧化层厚度（内）/mm Zr-4 5.9×10−4 5.1×10−4 CVD SiC 5.6598×10−6 FeCrAl 5.0066×10−8 2.9589×10−8
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