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作 者:张凌义 李潘潇 张胤 王成龙[1] 田文喜[1] 苏光辉[1] 秋穗正[1] ZHANG Lingyi;LI Panxiao;ZHANG Yin;WANG Chenglong;TIAN Wenxi;SU Guanghui;QIU Suizheng(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China)
机构地区:[1]西安交通大学核科学与技术学院,陕西西安710049
出 处:《原子能科学技术》2023年第8期1525-1533,共9页Atomic Energy Science and Technology
摘 要:小型热管反应堆电源技术具有续航久、结构紧凑、环境适应性强、固有安全性高等优势,可以适配于多种领域。本文以双模式热管堆非核原理样机NUSTER2.0为对象,在COMSOL中建立高温热管、温差发电装置及斯特林装置理论模型并耦合形成系统模型,对样机运行特性及力学特性进行数值仿真研究。15 kW加热功率稳态工况下,仿真结果与实验结果的热管温度分布及动、静态模块主要运行参数均吻合良好,最大相对误差为6.73%,初步验证了模型可靠性。变功率仿真结果确定了斯特林撞杆阈值为16.5 kW,并预估静态模块在25 kW附近达到效率峰值。系统启动瞬态仿真得到了“3-5-10-15 kW”阶梯式功率平台下的样机启动特性,并提出了样机启动策略。系统热力耦合稳态工况确定了样机应力危险区,并求得15 kW工况中堆芯热膨胀率为1.21%,热管-堆芯基体和热管-集热基体耦合处的最大应力分别为160 MPa和97 MPa。本文为NUSTER2.0样机的特性研究和实验设计提供了数值分析基础。Due to the advantages of long service life,compact structure,strong environmental adaptability and high inherent safety,the heat pipe reactor power supply system is worth studying.The NUSTER2.0 dual-mode heat pipe reactor non-nuclear prototype built by Xi’an Jiaotong University adopts the integrated design of“simulated reactor core-high temperature heat pipe-Stirling generator-thermoelectric power generation”.The combination of the dynamic module coupled with Stirling and the static module coupled with thermoelectric power generation device can meet the diversified demands of energy.In this paper,the steady-state experiment of NUSTER2.0 was carried out to verify the design,and the system coupling simulation of the prototype was carried out by COMSOL multiphysics to analyze its operation and mechanical characteristics.In the 15 kW thermal power steady-state experiment,the generating power of the dynamic module is 2019 W,and the static module is 493.2 W.The overall thermoelectric conversion efficiency is 16.7%,which verifies the engineering feasibility of the design.The system simulation model is coupled with the thermal resistance network model of high temperature heat pipe,the equivalent thermal conductivity model of thermoelectric power generation device and the Stirling adiabatic analysis program.The heat source of fuel rod and the heat sink of cooling water were simulated by heat flux boundary and convective boundary respectively.Under 15 kW thermal power,the steady-state simulation results are in good agreement with the experimental results on both the heat pipe temperature distribution and the main operating parameters of the dynamic and static modules,while the maximum relative error is 6.73%,which verifies that the coupled model is reliable.The variable thermal power steady-state simulation determines that the limit due to Stirling is 16.5 kW,and predicts that the static module will reach the peak efficiency near 25 kW.The system start-up transient simulation obtains the start-up characteristics unde
分 类 号:TL334[核科学技术—核技术及应用]
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