Multiphysics modelling and preliminary analysis on the freeze valve behaviour in a Molten Salt Fast Reactor

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
S. Deanesi , A. Cammi , S. Lorenzi
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Abstract

In the Molten Salt Fast Reactor (MSFR), the safety function related to criticality and cooling is also delivered via draining tanks developed to accommodate liquid fuel discharged by gravity during normal maintenance or accidental events. In particular, a safety barrier that is under investigation to manage accidental scenarios consists of a salt-frozen plug designed to melt in case of loss of power or overheating. Specifically, the salt plug should melt as a consequence of an unintended temperature increase, allowing the salt to drain into a safety tank. The mechanism based on the state of the plug embraces the passive safety concept, highlighting the importance of delving into the steady state of the freeze valve and the transient behaviour. This paper proposes a preliminary analysis of the behaviour of the freeze valve within a domain that represents a symmetric portion of the MSFR primary loop. The model, developed in OpenFOAM, couples melting and solidification phenomena to a multiphysics solver, coupling neutronics and thermal-hydraulics. The 3D domain represents 1/16th of the MSFR fuel loop and is equipped with a cylindrical region that mimics the presence of the freeze valve. Two scenarios are considered to assess the impact on the freeze plug behaviour of initial and boundary conditions meant to represent different cooling strategies. When the plug is coupled with the MSFR fuel loop, the selection of boundary and initial conditions strongly affects the plug melting time. This highlights the need for design specifications for the geometry and the cooling mechanisms to correctly operate the freeze valves.
熔盐快堆冻结阀特性的多物理场建模与初步分析
在熔盐快堆(MSFR)中,与临界和冷却相关的安全功能也通过开发的排水罐来提供,以容纳在正常维护或意外事件期间由重力排出的液体燃料。特别值得一提的是,一种正在调查中的安全屏障是由一个盐冻插头组成的,该插头在断电或过热的情况下会融化。具体来说,盐塞应该由于意外的温度升高而融化,从而使盐排到安全罐中。基于塞子状态的机制包含了被动安全概念,强调了深入研究冷冻阀稳态和瞬态行为的重要性。本文提出了冻结阀的行为在一个域内的初步分析,表示MSFR主回路的对称部分。该模型是在OpenFOAM中开发的,将熔化和凝固现象耦合到一个多物理场求解器中,耦合了中介学和热水学。3D区域代表了MSFR燃料回路的1/16,并配备了一个模拟冷冻阀存在的圆柱形区域。考虑了两种情况来评估初始条件和边界条件对冻结塞行为的影响,这意味着不同的冷却策略。当塞与MSFR燃料循环耦合时,边界条件和初始条件的选择对塞熔化时间有较大影响。这突出了对几何形状和冷却机制的设计规范的需求,以正确操作冷冻阀。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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