H2020 INSPYRE燃料蠕变试验的建模

A. Fedorov, Kevin Zwijsen, S. V. Til
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引用次数: 0

摘要

为了更好地了解核燃料的辐照蠕变,作为H2020欧洲项目INSPYRE的一部分,NRG在荷兰Petten的高通量反应堆(HFR)中准备了一个单独的效应辐照实验,旨在测量堆内燃料蠕变作为温度、通量、燃烧和轴压载荷的函数。这种连续类型的测量将提供大量数据集,从而更详细地了解辐照期间的燃料行为。为了支持实验并最佳地利用所产生的数据,建立了实验模型,以更好地预测燃料样品在辐照期间的行为。本文描述了将1.5D燃油性能代码TRANSURANUS (TU)与有限元分析(FEA)耦合在一起的数值模型。利用有限元法对实验进行了热分析。这种方法能够模拟一个相当复杂的实验几何,并包括轴向热传输,这在TU中没有实现。TU被修改,以便使用通过有限元分析获得的燃料颗粒温度,并包括实验中存在的轴向负荷。该模型通过几个试验案例进行了验证,并用于预测在可预见的辐照情景中燃料的行为。该模型的结果将在将来用于优化实验中使用的辐照参数和分析辐照过程中获得的数据。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Modelling of the H2020 INSPYRE Fuel Creep Experiment
To better understand irradiation creep of nuclear fuel, NRG has prepared, as part of the H2020 European project INSPYRE, a separate effect irradiation experiment in the High Flux Reactor (HFR) in Petten (the Netherlands) aiming to measure fuel creep in-pile as a function of temperature, flux, burn-up and axial pressure load. This continuous type of measurement will supply a large data set, leading to more detailed knowledge on fuel behaviour during irradiation. To support the experiment and make optimal use of the generated data, a model is created of the experiment to better predict the behaviour of the fuel samples during irradiation. The current paper describes the numerical model, which couples the 1.5D fuel performance code TRANSURANUS (TU) with a Finite Element Analysis (FEA). The thermal analysis of the experiment is carried out using the FEA. Such approach enables to model a rather complex geometry of the experiment, and to include axial heat transport, which is not implemented in TU. TU is modified in order to use the fuel pellet temperatures obtained using the FEA and to include the axial load present in the experiment. The model is validated against several test cases and used to predict the fuel behaviour during a selection of foreseen irradiation scenario’s. Results of the model will be used in the future for optimization of the irradiation parameters used in the experiment and for analysis of the data obtained during the irradiation.
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