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首页> 外文期刊>Annals of nuclear energy >Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model
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Steady- and transient-state analyses of fully ceramic microencapsulated fuel loaded reactor core via two-temperature homogenized thermal-conductivity model

机译:通过两温均化导热模型对全陶瓷微囊燃料负载反应堆堆芯的稳态和瞬态分析

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Fully ceramic microencapsulated (FCM) fuel, a type of accident-tolerant fuel (ATF), consists of TRISO particles randomly dispersed in a SiC matrix. In this study, for a thermal analysis of the FCM fuel with such a high heterogeneity, a two-temperature homogenized thermal-conductivity model was applied by the authors. This model provides separate temperatures for the fuel-kernels and the SiC matrix. It also provides more realistic temperature profiles than those of harmonic- and volumetric-average thermal conductivity models, which are used for thermal analysis of a fuel element in VHTRs having a composition similar to the FCM fuel, because such models are unable to provide the fuel-kernel and graphite matrix temperatures separately. In this study, coupled with a neutron diffusion model, a FCM fuel-loaded reactor core is analyzed via a two-temperature homogenized thermal-conductivity model at steady- and transient-states. The results are compared to those from harmonic- and volumetric-average thermal conductivity models, i.e., we compare k_(eff) eigenvalues, power distributions, and temperature profiles in the hottest single-channel at steady-state. At transient-state, we compare total powers, reactivity, and maximum temperatures in the hottest single-channel obtained by the different thermal analysis models. The different thermal analysis models and the availability of fuel-kernel temperatures in the two-temperature homogenized thermal-conductivity model for Doppler temperature feedback cause significant differences as revealed by comparisons.
机译:完全陶瓷微囊(FCM)燃料是一种耐事故性燃料(ATF),由TRISO颗粒随机分散在SiC基质中组成。在这项研究中,为了对具有如此高的非均质性的FCM燃料进行热分析,作者采用了两个温度均一的导热系数模型。该模型为燃料内核和SiC基体提供了单独的温度。与谐波和体积平均热导率模型相比,该模型还提供了更逼真的温度曲线,后者用于成分与FCM燃料相似的VHTR中燃料元素的热分析,因为此类模型无法提供燃料-内核温度和石墨基质温度分别。在这项研究中,结合中子扩散模型,通过在稳态和瞬态下的两温均质导热模型分析了FCM装载燃料的反应堆堆芯。将结果与谐波和体积平均导热系数模型的结果进行比较,即我们比较稳态下最热的单通道中的k_(eff)特征值,功率分布和温度曲线。在瞬态下,我们比较了通过不同热分析模型获得的最热单通道中的总功率,反应性和最高温度。比较显示,在多普勒温度反馈的两温均质导热模型中,不同的热分析模型和燃料内核温度的可用性造成了显着差异。

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