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| WWER反应堆压力容器热–力耦合行为 |
| Thermo-mechanical Coupling Behavior for Pressure Vessel of WWER Reactor |
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| DOI：10.3969/j.issn.1674-6457.2023.06.023 |
| 中文关键词: 压力容器 中子辐照 热–力耦合 有限元 UMAT功能 |
| 英文关键词: pressure vessel neutron irradiation thermo-mechanical coupling finite element UMAT function |
| 基金项目:河北省杰出青年科学基金(E2019203452);华中科技大学模具技术国家重点实验室开放课题(P2020–013);中核集团领创基金(JJXM–JTLC–2020–04) |
| Author Name | Affiliation | | MAO Jian-jun | First Sub-Institute, Nuclear Power Institute of China, Chengdu 610005, China | | PAN Rong-jian | First Sub-Institute, Nuclear Power Institute of China, Chengdu 610005, China | | QIN Jian-tao | First Sub-Institute, Nuclear Power Institute of China, Chengdu 610005, China | | ZHAO Hui | National Engineering Research Center for Equipment and Technology of Cold Strip Rolling, School of Mechanical Engineering, Yanshan University, Hebei Qinhuangdao 066004, China | | YANG Chong | National Engineering Research Center for Equipment and Technology of Cold Strip Rolling, School of Mechanical Engineering, Yanshan University, Hebei Qinhuangdao 066004, China | | GUO Dong-xu | National Engineering Research Center for Equipment and Technology of Cold Strip Rolling, School of Mechanical Engineering, Yanshan University, Hebei Qinhuangdao 066004, China | | SHI Bao-dong | National Engineering Research Center for Equipment and Technology of Cold Strip Rolling, School of Mechanical Engineering, Yanshan University, Hebei Qinhuangdao 066004, China | | WU Lu | First Sub-Institute, Nuclear Power Institute of China, Chengdu 610005, China |
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| 中文摘要: |
| 目的 研究纯Fe、Fe–Cr和Fe–Ni二元体系合金及Fe–Cr–Ni三元体系合金材料压力容器在辐照条件下的热–力耦合行为。方法 选用纯Fe、Fe–36Ni和16MND5二元体系合金以及SA508–3三元体系合金材料为研究对象，采用ABAQUS有限元软件建立压力容器模型，基于UMAT功能将Zr–4包壳材料热源的热膨胀系数模型导入有限元软件中，模拟不同合金材料的压力容器在中子辐照和高温、高压作用下的热–力耦合行为，分别分析压力容器温度场、位移场和应力场的分布情况及随辐照时间的变化情况。结果 包壳温度由内壁向外壁依次降低，包壳内壁温度为353 ℃，最大温差为20 ℃。Fe–36Ni合金受到的最大应力为3.45 MPa，而纯铁受到的最大应力只有1.2 MPa。在中子辐照作用下温度和应力主要集中在压力容器的中心部位，而在压力容器的上下两端容易产生位移集中。结论 合金体系的不同不影响辐照作用下压力容器的温度场、位移场和应力场的分布规律。温度、位移和应力值的大小随着合金体系的改变而改变，温度场和应力场对合金体系更为敏感，即辐照作用下燃料元件的宏观力学性能对合金元素具有敏感性。 |
| 英文摘要: |
| The work aims to study the thermo-mechanical coupling behavior of pure Fe, Fe-Cr, Fe-Ni binary system alloy and Fe-Cr-Ni ternary system alloy pressure vessels under irradiation. In this study, pure Fe, Fe-36Ni, 16MND5 binary system alloy and SA508-3 ternary system alloy were selected to establish a pressure vessel model through ABAQUS finite element software. Based on the UMAT function, the thermal expansion coefficient models of Zr-4 cladding material heat source were introduced into the finite element software to simulate the thermo-mechanical coupling behavior of pressure vessels with different alloy materials under neutron irradiation, high temperature and high pressure, to analyze the distribution of temperature field, displacement field and stress field of pressure vessels and their changes with irradiation time. The results showed that the temperature of the cladding decreased from the inner wall to the outer wall. The inner wall temperature was 353 ℃, and the maximum temperature difference was 20 ℃. The maximum stress of Fe-36Ni alloy was 3.45 MPa, while that of pure iron was only 1.2 MPa. It meant that the temperature and stress were mainly concentrated in the center of the pressure vessels under the irradiation, while the displacement concentration was easy to occur at the upper and lower ends of the pressure vessels. The distribution of temperature field, displacement field and stress field of pressure vessels under irradiation is not affected by different alloy systems. The values of temperature, displacement and stress vary with the alloy system. The temperature field and stress field are more sensitive to the alloy system. In other words, the macro-mechanical properties of the irradiated fuel elements are sensitive to the alloy elements. |
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