基于CFD RANS湍流模型的实验试验台熔盐(FLiNaK)热物性对热管的影响

IF 0.9 Q3 NUCLEAR SCIENCE & TECHNOLOGY EPJ Nuclear Sciences & Technologies Pub Date : 2019-08-01 DOI:10.1051/epjn/2019027
Ramiro Freile, M. Kimber
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引用次数: 1

摘要

在液体燃料熔盐堆(MSR)中,设计时需要考虑的一个关键因素是中子力学、热力学和热水学等不同物理特性之间的强耦合。在热工水力学方面,要求对传热进行很好的表征。为此,用于FLiNaK流动的湍流模型必须是有效的,并且必须准确描述其热物理性质。在文献中,每种材料属性都有几种表达,差异可能很大。本研究的目的是证明和量化热物理性质的不确定性对msr热水力重要性的关键指标的影响,特别是传热系数。为了实现这一点,使用RANS k-ω SST模型的计算流体动力学(CFD)模拟与已发表的熔盐实验数据进行了比较。使用了FLiNaK材料性能的各种相关性。观察到,FLiNaK热物性的不确定性导致热系数的显著变化。受此影响,研究人员进行了额外的CFD模拟,以获得每种热物性的敏感性系数。有了这些信息,每一种材料特性的变化对传热系数的影响被量化,执行一次一个因素的方法(OAT)。灵敏度分析结果表明,对测定换热系数最关键的热物理性质是粘度和导热系数。更具体地说,无量纲敏感系数(定义为传热相对于各自性能变化的百分比)分别为- 0.51和0.67。根据不同的相关性,这些性质的最大变化百分比分别为18%和26%,这使得预测的传热系数的变化分别高达9%和17%的粘度和导热系数。结果还表明,使用siider - Tate相关比使用Dittus - Boelter相关更能捕获模拟中发现的Nusselt数趋势。未来的工作将适应额外的湍流模型和更高保真度的物理,这将有助于确定siider Tate表达式是否真正捕捉到感兴趣的物理,或者当前工作中看到的协议是否仅仅反映了所采用的单一湍流模型。
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Influence of molten salt-(FLiNaK) thermophysical properties on a heated tube using CFD RANS turbulence modeling of an experimental testbed
In a liquid fuel molten salt reactor (MSR) a key factor to consider upon its design is the strong coupling between different physics present such as neutronics, thermo-mechanics and thermal-hydraulics. Focusing in the thermal-hydraulics aspect, it is required that the heat transfer is well characterized. For this purpose, turbulent models used for FLiNaK flow must be valid, and its thermophysical properties must be accurately described. In the literature, there are several expressions for each material property, with differences that can be significant. The goal of this study is to demonstrate and quantify the impact that the uncertainty in thermophysical properties has on key metrics of thermal hydraulic importance for MSRs, in particular on the heat transfer coefficient. In order to achieve this, computational fluid dynamics (CFD) simulations using the RANS k-ω SST model were compared to published experiment data on molten salt. Various correlations for FLiNaK’s material properties were used. It was observed that the uncertainty in FLiNaK’s thermophysical properties lead to a significant variance in the heat coefficient. Motivated by this, additional CFD simulations were done to obtain sensitivity coefficients for each thermophysical property. With this information, the effect of the variation of each one of the material properties on the heat transfer coefficient was quantified performing a one factor at a time approach (OAT). The results of this sensitivity analysis showed that the most critical thermophysical properties of FLiNaK towards the determination of the heat transfer coefficient are the viscosity and the thermal conductivity. More specifically the dimensionless sensitivity coefficient, which is defined as the percent variation of the heat transfer with respect to the percent variation of the respective property, was −0.51 and 0.67 respectively. According to the different correlations, the maximum percent variations for these properties is 18% and 26% respectively, which yields a variation in the predicted heat transfer coefficient as high as 9% and 17% for the viscosity and thermal conductivity, respectively. It was also demonstrated that the Nusselt number trends found from the simulations were captured much better using the Sieder Tate correlation than the Dittus Boelter correlation. Future work accommodating additional turbulence models and higher fidelity physics will help to determine whether the Sieder Tate expression truly captures the physics of interest or whether the agreement seen in the current work is simply reflective of the single turbulence model employed.
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来源期刊
EPJ Nuclear Sciences & Technologies
EPJ Nuclear Sciences & Technologies NUCLEAR SCIENCE & TECHNOLOGY-
CiteScore
1.00
自引率
20.00%
发文量
18
审稿时长
10 weeks
期刊最新文献
Technical note: stable and unstable reactors Templates of expected measurement uncertainties for neutron-induced capture and charged-particle production cross section observables Templates of expected measurement uncertainties for (n, xn) cross sections Templates of expected measurement uncertainties for total neutron cross-section observables Templates of expected measurement uncertainties for prompt fission neutron spectra
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