| 邱阳,李玉光,周高斌,谢国福,张尚林,胡甜,王晓童.反应堆压力容器保温层辐射屏蔽组件传热计算分析及屏蔽材料试验研究[J].装备环境工程,2022,19(5):140-148. QIU Yang,LI Yu-guang,ZHOU Gao-bin,XIE Guo-fu,ZHANG Shang-lin,HU Tian,WANG Xiao-tong.Heat Transfer Calculation, Simulation Analysis and Material Test of the Radiation Shield Assembly of Reactor Pressure Vessel Insulation[J].Equipment Environmental Engineering,2022,19(5):140-148. |
| 反应堆压力容器保温层辐射屏蔽组件传热计算分析及屏蔽材料试验研究 |
| Heat Transfer Calculation, Simulation Analysis and Material Test of the Radiation Shield Assembly of Reactor Pressure Vessel Insulation |
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| DOI：10.7643/issn.1672-9242.2022.05.018 |
| 中文关键词: 反应堆压力容器保温层 辐射屏蔽材料 硼硅树脂 传热计算 仿真分析 热态性质试验中图分类号:TL328 文献标识码:A 文章编号:1672-9242(2022)05-0140-09 |
| 英文关键词:reactor pressure vessel thermal insulation radiation shield material borosilicate resin heat transfer calculation simulation analysis thermal state property test |
| 基金项目: |
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| Author | Institution |
| QIU Yang | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| LI Yu-guang | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| ZHOU Gao-bin | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| XIE Guo-fu | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| ZHANG Shang-lin | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| HU Tian | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
| WANG Xiao-tong | Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu 610041, China |
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| 中文摘要: |
| 目的 确保华龙一号HPR1000反应堆压力容器保温层辐射屏蔽组件在运行工况下的可靠性、安全性以及能够有效执行其功能。方法 采用基于传热理论结合经验公式的理论计算方法，以及流固耦合的有限元仿真分析，对辐射屏蔽组件的运行温度进行计算。针对屏蔽材料在受热状态下的性质变化，进行一系列的热态性质试验。结果 理论计算方法得到的结果为163.36~168.74 ℃，有限元仿真分析得到的结果为236.85~266.85 ℃，两者偏差约100 ℃。对造成该种差异的原因进行了分析，发现仿真分析方法得到的结果的置信度更高。屏蔽材料在受热状态下，其体积膨胀率可达到38.82%，而当屏蔽材料受热超过其温度限值204 ℃后，将出现明显的粉化等物理状态恶化的趋势。结论 流固耦合的有限元仿真分析方法更适用于辐射屏蔽组件的传热过程计算，同时获取了屏蔽材料物理性状受热变化趋势，对屏蔽组件的选材及结构设计具有指导意义。 |
| 英文摘要: |
| In order to ensure the reliability, safety and functionality of the radiation shield assembly of HPR1000 RPV insulation under operation conditions, the operation temperature of radiation shield assembly is calculated by using the calculation analysis (based on heat transfer theory and empirical formula) and finite element simulation analysis (with fluid-structure interaction). The result from calculation analysis is 163.366~168.74 ℃ and meanwhile, the result from finite element simulation analysis is 236.85~266.85 ℃, of which a large deviation of about 100 ℃ appeared. The reason that caused this difference has been studied, and the results of the finite element simulation analysis have been found with a higher confidence level. Besides, a series of hot performance tests have been conducted to study the qualitative change of radiation shielding material. The volume expansion ratio under heat conditions of the radiation shielding material is 38.82%, and obvious pulverization and physical deterioration appeared after the temperature of radiation shielding material exceeded 204 ℃. Briefly, through the study of this paper, finite element simulation analysis with fluid-structure interaction was found to be more applicable for the heat transfer calculation of radiation shield assembly, and the physical characteristics change under heat conditions of radiation shielding material was studied. These conclusions have a great guiding significance to the structure and strength design of the radiation shield assembly. |
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