A Geometric Multiscale modelling approach to the analysis of MSR plant dynamics

IF 3.3 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Progress in Nuclear Energy Pub Date : 2015-08-01 DOI:10.1016/j.pnucene.2015.02.014
Matteo Zanetti , Antonio Cammi , Carlo Fiorina , Lelio Luzzi
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引用次数: 17

Abstract

In the framework of the Generation IV International Forum (GIF-IV), six innovative concepts of nuclear reactors have been proposed as suitable to guarantee a safe, sustainable and proliferation resistant source of nuclear energy. Among these reactors, a peculiar role is played by the Molten Salt Reactor (MSR), which is the only one with a liquid and circulating fuel. This feature leads to a complex and highly coupled behaviour, which requires careful investigations, as a consequence of some unusual features like the drift of Delayed Neutron Precursors (DNP) along the primary circuit and heat transfer with a heat-generating fluid. The inherently coupled dynamics of the MSRs asks for innovative approaches to perform reliable transient analyses. The node-wise implicitly-coupled solution of the Partial Differential Equations (PDE) that govern the different phenomena in a reactor would offer in this sense an ideal solution. However, such an approach (hereinafter referred to as Multi-Physics – MP) requires a huge amount of computational power. In this work, we propose and assess a Geometric Multiscale approach on MSR, addressing the core modelling with a 3-D MP approach and the remaining part of the system – e.g., the cooling loop – with simplified 0-D models based on Ordinary Differential Equations (ODE). The aim is to conjugate the accuracy of the MP modelling approach with acceptable computation loads. Reference is made to the Molten Salt Reactor Experiment (MSRE), due to the availability of a detailed design and experimental data that are used for assessment and preliminary validation of the developed simulation tool.

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MSR植物动力学分析的几何多尺度建模方法
在第四代国际论坛(GIF-IV)的框架内,提出了六种创新的核反应堆概念,认为它们适合确保安全、可持续和防扩散的核能来源。在这些反应堆中,熔盐堆(MSR)起着特殊的作用,它是唯一一个使用液体和循环燃料的反应堆。由于一些不寻常的特征,如延迟中子前体(DNP)沿着主回路的漂移和与发热流体的传热,这一特征导致了复杂和高度耦合的行为,需要仔细研究。msr的内在耦合动力学要求创新的方法来执行可靠的瞬态分析。在这种意义上,控制反应器中不同现象的偏微分方程(PDE)的节点隐式耦合解将提供理想的解决方案。然而,这种方法(以下称为多物理场- MP)需要大量的计算能力。在这项工作中,我们提出并评估了一种基于MSR的几何多尺度方法,使用3-D MP方法解决核心建模问题,并使用基于常微分方程(ODE)的简化0-D模型解决系统的其余部分(例如冷却回路)。目的是将MP建模方法的精度与可接受的计算负载结合起来。参考了熔盐反应堆实验(MSRE),因为有详细的设计和实验数据可用于评估和初步验证开发的模拟工具。
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来源期刊
Progress in Nuclear Energy
Progress in Nuclear Energy 工程技术-核科学技术
CiteScore
5.30
自引率
14.80%
发文量
331
审稿时长
3.5 months
期刊介绍: Progress in Nuclear Energy is an international review journal covering all aspects of nuclear science and engineering. In keeping with the maturity of nuclear power, articles on safety, siting and environmental problems are encouraged, as are those associated with economics and fuel management. However, basic physics and engineering will remain an important aspect of the editorial policy. Articles published are either of a review nature or present new material in more depth. They are aimed at researchers and technically-oriented managers working in the nuclear energy field. Please note the following: 1) PNE seeks high quality research papers which are medium to long in length. Short research papers should be submitted to the journal Annals in Nuclear Energy. 2) PNE reserves the right to reject papers which are based solely on routine application of computer codes used to produce reactor designs or explain existing reactor phenomena. Such papers, although worthy, are best left as laboratory reports whereas Progress in Nuclear Energy seeks papers of originality, which are archival in nature, in the fields of mathematical and experimental nuclear technology, including fission, fusion (blanket physics, radiation damage), safety, materials aspects, economics, etc. 3) Review papers, which may occasionally be invited, are particularly sought by the journal in these fields.
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