Research on Thermal-fluid-structure Coupling Behavior for U-10Mo/Al Fuel Assemblies under Irradiation
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摘要: 为研究U-10Mo/Al燃料组件堆内辐照变形对其机械行为和热工水力行为特性的影响，基于辐照-热流固耦合分析方法，通过将非均匀辐照条件引入到燃料组件辐照-热力耦合行为的三维有限元模拟中，开展了U-10Mo/Al燃料组件堆内辐照环境下的机械和热工水力行为研究，计算分析了辐照条件下燃料组件随时间和空间变化的结构力学场和温度场的分布和演化规律。研究结果表明，U-10Mo/Al燃料组件在流场、温度场、机械力学的耦合作用下展现出典型的机械变形行为，支撑板和燃料元件均产生一定程度的弯曲；燃料组件的温度场表现出典型的非均匀空间分布特性，温度峰值出现在燃料元件肿胀量最大的位置；燃料芯体边角区域包壳、芯体的应力整体高于中心区域和支撑板。Abstract: In order to investigate the effects of in-pile mechanical deformation under irradiation on the mechanical and thermal-hydraulic characteristics of U-10Mo/Al fuel assemblies, the mechanical behavior and thermal-hydraulic behavior of U-10Mo/AI fuel assemblies under in-pile irradiation are studied by using the thermal-fluid-structure coupling analysis method under irradiation. By introducing non-uniform irradiation conditions into the irradiation-thermal-mechanical coupling behavior of the 3D finite element model for fuel assemblies, the distribution and evolution laws of structural mechanics field and temperature field of U-10Mo/Al fuel assemblies under time-dependent and location-dependent irradiation conditions are studied. The results show that under the coupling effect of flow field, temperature field, and mechanical mechanics, U-10Mo/AI fuel assemblies exhibit typical mechanical deformation behavior, and both support plates and fuel elements have a certain degree of bending; the temperature field of fuel assemblies show a typical feature of non-uniform spatial distribution, and the peak temperature occurs at the position of maximum swelling of the fuel element; the stress at the sides and corners of the pellet for cladding and the pellet is larger than that in the central region and support plates.
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图 3 燃料元件1的芯体在Y向中心面引入的裂变率
Figure 3. Fission Rate Distribution of Pellet in Central Plane of Y Direction for Fuel Element 1
图 5 燃料组件辐照80 d时在X方向和Y方向位移图（变形放大5倍）
Figure 5. Deformation of Fuel Assembly in X and Y Directions on 80th Day of Irradiation (Deflection Scale Factor: 5)
图 6 燃料组件辐照80 d时在X和Y方向沿路径1和路径2的变形
Figure 6. Deformation of Fuel Assembly in X and Y Direction along Path 1 and Path 2 on 80th Day of Irradiation
图 7 燃料组件辐照80 d时的温度场分布
Figure 7. Temperature Field Contour of Fuel Assembly on 80th Day of Irradiation
图 8 不同燃料元件中心裂变率（Z=−348 mm）
Figure 8. Fission Rate at Central Lines of Different Fuel Elements (Z=−348 mm)
图 9 不同燃料元件中心温度特性（Z=−348 mm）
Figure 9. Temperature Profiles at Central Lines of Different Fuel Elements (Z=−348 mm)
图 10 不同燃料元件厚度变化情况（Z=−348 mm）
Figure 10. Variation of Thickness of Different Fuel Elements (Z=−348 mm)
图 11 辐照80 d后截面的应力分布云图（Z=−348 mm）
Figure 11. Stress Contour of Section on 80th Day of Irradiation （Z=−348 mm）
表 1 边界条件
Table 1. Boundary Conditions
边界条件 数值 计算域入口速度/（m·s−1） 3.7 入口水温/K 308 耦合面初始温度/K 320 出口压力/MPa 0 系统压力/MPa 1.5 
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[1] KIM Y S, HOFMAN G L. Fission product induced swelling of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2011, 419(1-3): 291-301. doi: 10.1016/j.jnucmat.2011.08.018 [2] KIM Y S, HOFMAN G L, CHEON J S, et al. Fission induced swelling and creep of U–Mo alloy fuel[J]. Journal of Nuclear Materials, 2013, 437(1-3): 37-46. doi: 10.1016/j.jnucmat.2013.01.346 [3] YAN F, JIAN X B, DING S R. Effects of UMo irradiation creep on the thermo-mechanical behavior in monolithic UMo/Al fuel plates[J]. Journal of Nuclear Materials, 2019, 524: 209-217. doi: 10.1016/j.jnucmat.2019.07.006 [4] JO D, PARK J, CHAE H. Development of thermal hydraulic and margin analysis code for steady state forced and natural convective cooling of plate type fuel research reactors[J]. Progress in Nuclear Energy, 2014, 71: 39-51. doi: 10.1016/j.pnucene.2013.11.006 [5] LI L F, FANG D, ZHANG D L, et al. Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements[J]. Annals of Nuclear Energy, 2019, 134: 284-298. doi: 10.1016/j.anucene.2019.06.030 [6] KENNE J C, SOLBREKKEN G L. Coupled fluid structure interaction (FSI) modeling of parallel plate assemblies[C]//Proceedings of the ASME 2011 International Mechanical Engineering Congress and Exposition. Denver: American Society of Mechanical Engineers, 2011: 159-167. [7] RICE A. Intercode advanced fuels and cladding comparison using BISON, FRAPCON, and FEMAXI fuel performance codes[D]. Columbia: University of South Carolina, 2015. [8] HE Y N, CHEN P, WU Y W, et al. Preliminary evaluation of U3Si2-FeCrAl fuel performance in light water reactors through a multi-physics coupled way[J]. Nuclear Engineering and Design, 2018, 328: 27-35. [9] LIU R, ZHOU W Z. Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor[J]. Annals of Nuclear Energy, 2017, 109: 298-309. doi: 10.1016/j.anucene.2017.05.037 [10] SCHULTHESS J L, LLOYD W R, RABIN B, et al. Mechanical properties of irradiated U-Mo alloy fuel[J]. Journal of Nuclear Materials, 2019, 515: 91-106. doi: 10.1016/j.jnucmat.2018.12.025 [11] MARCHBANKS M F. ANS materials databook: ORNL/M-4582[R]. Oak Ridge: Oak Ridge National Lab. , 1995. [12] OZALTUN H, SHEN M H H, MEDVEDEV P. Assessment of residual stresses on U10Mo alloy based monolithic mini-plates during Hot Isostatic Pressing[J]. Journal of Nuclear Materials, 2011, 419(1-3): 76-84. doi: 10.1016/j.jnucmat.2011.08.029 -
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