{"title":"Multiphysics modelling and preliminary analysis on the freeze valve behaviour in a Molten Salt Fast Reactor","authors":"S. Deanesi , A. Cammi , S. Lorenzi","doi":"10.1016/j.nucengdes.2025.114486","DOIUrl":null,"url":null,"abstract":"<div><div>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.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"445 ","pages":"Article 114486"},"PeriodicalIF":2.1000,"publicationDate":"2025-09-28","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549325006636","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}
引用次数: 0
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.
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.