Effect analysis of power density distribution & temperature dependent thermo-physical properties along MSR fuel channels applying neutronic and thermal hydraulic approach

IF 2.6 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Mohammad Khan, Nayeem bin Zahid, Saad Islam, Ali Mahdi
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Abstract

One of the potential Generation IV reactors is MSR for its several advantages including actinides burning, production of hydrogen, and fissile breeding. The distinct feature that sets the MSR apart from other reactors is the mixing of fissile material with molten halide salt, playing the vital role of both the heat transferring coolant and heat generating fuel. This dual-function fluid circulates through a graphite moderator matrix, forming a complex system that poses significant computational challenges, particularly for coupled neutronic-thermal hydraulic simulations. To address these challenges, simplified assumptions—such as sinusoidal power distributions and temperature-independent material properties—are often employed. In this study, a single MSR fuel channel is analysed under varying power density distribution assumptions, with and without incorporating the temperature dependence of material properties, using a decoupled neutronic and thermal-hydraulic modelling approach. To determine the power distribution via neutron flux profiles, a probabilistic approach was employed using the Monte Carlo particle transport code OpenMC. For the thermal-hydraulic analysis, the Reynolds-Averaged Navier–Stokes (RANS) equations with the k–ε turbulence model were utilized and implemented using the state-of-the-art commercial computational fluid dynamics software, ANSYS Fluent. The results were compared to analytical solutions available in the literature, as well as to results obtained through fully coupled neutronic-thermal hydraulic simulations. The study revealed that assuming uniform heat generation in the MSR channel significantly affects the temperature profile along the channel. It also indicated that axial variations in heat generation are the most influential factor affecting the temperature distribution. Additionally, other flow properties such as velocity profiles and Nusselt number distributions were examined.
应用中子和热水力方法对MSR燃料通道功率密度分布和温度相关热物性的影响分析
潜在的第四代反应堆之一是MSR,因为它有几个优点,包括锕系元素燃烧、氢的产生和裂变增殖。MSR不同于其他反应堆的显著特点是,它将可裂变材料与熔融卤化物盐混合在一起,在传热冷却剂和发热燃料中发挥着至关重要的作用。这种双重功能的流体在石墨慢化剂基体中循环,形成了一个复杂的系统,给计算带来了重大挑战,特别是在耦合中子-热液压模拟中。为了应对这些挑战,通常采用简化的假设,例如正弦功率分布和与温度无关的材料特性。在本研究中,使用解耦的中子和热工模型方法,在不同功率密度分布假设下,分析了单个MSR燃料通道,并考虑了材料特性对温度的依赖性。利用蒙特卡罗粒子输运代码OpenMC,采用概率方法确定中子通量分布。为了进行热液分析,使用了具有k -ε湍流模型的reynolds - average Navier-Stokes (RANS)方程,并使用最先进的商用计算流体动力学软件ANSYS Fluent进行了实现。结果与文献中可用的解析解以及通过完全耦合的中子-热水力模拟得到的结果进行了比较。研究表明,假设MSR通道均匀产热会显著影响通道沿线的温度分布。轴向产热变化是影响温度分布的最主要因素。此外,还研究了其他流动特性,如速度分布和努塞尔数分布。
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来源期刊
Nuclear Engineering and Technology
Nuclear Engineering and Technology 工程技术-核科学技术
CiteScore
4.80
自引率
7.40%
发文量
431
审稿时长
3.5 months
期刊介绍: Nuclear Engineering and Technology (NET), an international journal of the Korean Nuclear Society (KNS), publishes peer-reviewed papers on original research, ideas and developments in all areas of the field of nuclear science and technology. NET bimonthly publishes original articles, reviews, and technical notes. The journal is listed in the Science Citation Index Expanded (SCIE) of Thomson Reuters. NET covers all fields for peaceful utilization of nuclear energy and radiation as follows: 1) Reactor Physics 2) Thermal Hydraulics 3) Nuclear Safety 4) Nuclear I&C 5) Nuclear Physics, Fusion, and Laser Technology 6) Nuclear Fuel Cycle and Radioactive Waste Management 7) Nuclear Fuel and Reactor Materials 8) Radiation Application 9) Radiation Protection 10) Nuclear Structural Analysis and Plant Management & Maintenance 11) Nuclear Policy, Economics, and Human Resource Development
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