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A Multi-Physics Adaptive Time Step Coupling Algorithm for Light-Water Reactor Core Transient and Accident Simulation

机译:一种多物理自适应时间步长耦合算法,用于光 - 反应器核心瞬态和事故模拟

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摘要

A new reactor core multi-physics system addresses the pellet-to-cladding heat transfer modeling to improve full-core operational transient and accident simulation used for assessment of reactor core nuclear safety. The rigorous modeling of the heat transfer phenomena involves strong interaction between neutron kinetics, thermal-hydraulics and nuclear fuel performance, as well as consideration of the pellet-to-cladding mechanical contact leading to dramatic increase in the gap thermal conductance coefficient. In contrast to core depletion where parameters smoothly depend on fuel burn-up, the core transient is driven by stiff equation associated with rapid variation in the solution and vulnerable to numerical instability for large time step sizes. Therefore, the coupling algorithm dedicated for multi-physics transient must implement adaptive time step and restart capability to achieve prescribed tolerance and to maintain stability of numerical simulation. This requirement is met in the MPCORE (Multi-Physics Core) multi-physics system employing external loose coupling approach to facilitate the coupling procedure due to little modification of constituent modules and due to high transparency of coupling interfaces. The paper investigates the coupling algorithm performance and evaluates the pellet-to-cladding heat transfer effect for the rod ejection accident of a light water reactor core benchmark.
机译:一种新的反应堆核心多物理系统解决了颗粒到熔接的传热建模,以改善用于评估反应堆核心核安全性的全核运算瞬态和事故模拟。传热现象的严格建模涉及中子动力学,热液压和核燃料性能之间的强烈相互作用,以及考虑颗粒到包层的机械接触,导致间隙热导系数的显着增加。与核心耗尽相反,参数平滑地取决于燃料烧伤,芯瞬态由与解决方案中快速变化相关的硬质方程驱动,并且容易受到数值不稳定性的大型时间步长。因此,专用于多物理瞬态的耦合算法必须实现自适应时间步长并重新启动能力以实现规定的公差并保持数值模拟的稳定性。在采用外部松散耦合方法的MPCore(多物理核心)多物理系统中满足该要求,以便于耦合过程,由于对组成模块几乎没有修改,并且由于耦合界面的高透明度。本文研究了耦合算法性能,并评估了光水反应堆核心基准的杆喷射事故的颗粒覆盖传热效果。

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