葛攀和, 李敏, 李杨柳, 胡古, 柯国土. 温差热电转换型空间热管冷却反应堆瞬态分析程序开发及验证[J]. 原子能科学技术, 2024, 58(1): 69-83. DOI: 10.7538/yzk.2023.youxian.0068
引用本文: 葛攀和, 李敏, 李杨柳, 胡古, 柯国土. 温差热电转换型空间热管冷却反应堆瞬态分析程序开发及验证[J]. 原子能科学技术, 2024, 58(1): 69-83. DOI: 10.7538/yzk.2023.youxian.0068
GE Panhe, LI Min, LI Yangliu, HU Gu, KE Guotu. Development and Verification of Transient Analysis Program for Thermoelectric Space Heat Pipe Cooled Reactor[J]. Atomic Energy Science and Technology, 2024, 58(1): 69-83. DOI: 10.7538/yzk.2023.youxian.0068
Citation: GE Panhe, LI Min, LI Yangliu, HU Gu, KE Guotu. Development and Verification of Transient Analysis Program for Thermoelectric Space Heat Pipe Cooled Reactor[J]. Atomic Energy Science and Technology, 2024, 58(1): 69-83. DOI: 10.7538/yzk.2023.youxian.0068

温差热电转换型空间热管冷却反应堆瞬态分析程序开发及验证

Development and Verification of Transient Analysis Program for Thermoelectric Space Heat Pipe Cooled Reactor

  • 摘要: 热管冷却反应堆采用固态堆芯设计、高温热管传热,具有结构简单、非能动、高可靠性等优点。为研究温差热电转换型空间热管冷却反应堆电源系统的瞬态特性,本文针对该型电源系统中最主要的系统(包括堆本体、高温热管、温差热电转换系统)建立了详细的数学物理模型,并开发了系统瞬态分析程序,其中堆本体模型基于OpenFOAM进行模块开发,耦合了点堆动力学模型和反应性反馈模型。通过文献和试验数据分别验证了高温热管及温差热电转换模型,结果与参考值符合较好,其中温差热电转换模块发电功率与试验值的相对偏差小于2.75%。采用该程序对KRUSTY进行了建模分析,开展了反应性引入、热电转换模块失效、负荷跟踪、主动冷却丧失工况下的瞬态分析,并与试验值进行了对比。结果表明,在上述瞬态工况下堆芯燃料表面温度与试验值的偏差小于4.1 K,程序计算结果与试验值符合较好。

     

    Abstract: Heat pipe cooled reactor has the advantages of simple structure, passive heat transfer and high reliability, owning to the design of solid reactor core and heat transfer using high-temperature heat pipe. In order to study the transient and safety characteristic of space heat pipe cooled reactor with thermoelectric conversion, the detailed mathematical and physical models were established for the most key system of the reactor including the reactor, high temperature heat pipe, thermoelectric conversion system. The reactor model was developed by coupling point-kinetic model, reactivity feedback model and power distribution model based on OpenFOAM, in which three different interface heat transfer models were developed to couple different regions in solid reactor. The reactor model overcome modeling difficulty of some typical accident scenarios such as heat pipe failure accident, the actual distribution and variation of temperature can be accurately obtained. The two-dimensional transient heat pipe model was present which was suitable for transient simulation of high-temperature heat pipe after startup. The transient working condition of a sodium heat pipe was simulated, the result fits quite well with the thermal resistance network model and two-dimensional model. For the thermoelectric generator, the one-dimensional transient model was established, in which the effect of Peltier heat, Fourier's heat conduction, Joule heat and Thomson heat was considered, the dynamic behaviors of thermoelectric generator under different thermal conditions can be simulated. In order to testify the thermoelectric generator model, a BiTe-based thermoelectric module was built and verified with the experiment data under two different working conditions. The output electric power deviation compared with experiment data is 2.47% and 2.75% under two working conditions. The transient system analysis program for thermoelectric space heat pipe cooled reactor was developed and fully verified with the experimental data of the KRUSTY prototype reactor. The detailed KRUSTY reactor model was established in the program, the accident conditions of the KRUSTY were calculated including reactivity control, thermoelectric conversion module failure, loading following and active heat removal accident. The results show that the simulation results of program are in good agreement with test data, the max deviation of surface fuel temperature is less than 4.1 K under these accident conditions and the accuracy of the model is proved. The program will provide effective analysis and research tool for the transient characteristic study of space heat pipe cooled reactor with thermoelectric conversion.

     

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