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首页> 外文期刊>Annals of nuclear energy >Module for thermomechanical modeling of LWR fuel in multiphysics simulations
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Module for thermomechanical modeling of LWR fuel in multiphysics simulations

机译:多物理场模拟中的轻水堆燃料热力学建模模块

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We have developed a new light-weight fuel behavior code FINIX, specifically designed for modeling of LWR fuel rods in multiphysics simulations. A thermomechanical description of the rod is required especially in transient conditions, where the heat transfer and changes in the rod's physical dimensions are strongly coupled. In addition to the mechanical deformations, FINIX solves the temperature distribution in the rod and the heat flux from the cladding to the coolant, allowing two-way coupling of the fuel behavior simulation with both neutronics and thermal hydraulics simulations. In this paper, we describe the FINIX module and compare its performance with experimental data and FRAPTRAN-1.4, a widely used fuel behavior code. The comparison reveals good agreement in both cases. We also demonstrate how FINIX can be integrated into multiphysics simulations. Coupled with the Monte Carlo reactor physics code Serpent, we simulate a fast reactivity transient with the fuel temperature and fission power solved self-consistently. With the reactor dynamics codes TRAB-1D and TRAB3D/SMABRE, we simulate a fast power transient and a PWR main steam line break. The latter serves as an example of coupled fuel behavior, neutronics and system-level thermal hydraulics simulation. (c) 2014 Elsevier Ltd. All rights reserved.
机译:我们已经开发了一种新的轻型燃料行为代码FINIX,专门用于在多物理场仿真中为轻水堆燃料棒建模。特别是在瞬态条件下,需要对棒进行热力学描述,在瞬态条件下,传热和棒物理尺寸的变化是紧密耦合的。除了机械变形之外,FINIX还解决了杆中的温度分布以及从包层到冷却剂的热通量的问题,从而使燃料行为模拟与中子学和热力学模拟能够双向耦合。在本文中,我们描述了FINIX模块,并将其性能与实验数据和广泛使用的燃料行为代码FRAPTRAN-1.4进行了比较。比较表明在两种情况下都具有良好的一致性。我们还将演示如何将FINIX集成到多物理场仿真中。结合蒙特卡罗反应堆物理代码“蛇形”,我们模拟了一个快速反应性瞬态,燃料温度和裂变功率自洽地得到了解决。使用反应堆动力学代码TRAB-1D和TRAB3D / SMABRE,我们模拟了快速功率瞬变和PWR主蒸汽管线中断的情况。后者是耦合燃料性能,中子学和系统级热力水力模拟的一个示例。 (c)2014 Elsevier Ltd.保留所有权利。

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