{"title":"3D numerical investigation of fragmentation of wood’s metal in water and estimation of particle size distribution","authors":"M. Chandra Kumar , A. Jasmin Sudha","doi":"10.1016/j.nucengdes.2025.114223","DOIUrl":null,"url":null,"abstract":"<div><div>During a severe accident in a nuclear reactor, the molten nuclear fuel may interact with the liquid coolant in the form of jet in the reactor vessel. In this work hydrodynamic fragmentation of the Wood’s metal which is a simulant material for corium in water is studied. The 3D numerical model is developed in the open-source DNS solver Basilisk code and validated with experimental results found in literature for low temperature Wood’s metal water system with a discrepancy of about 2.3%. Volume of Fluid (VOF) technique is adopted to capture the liquid–liquid interface and Adaptive Mesh Refinement (AMR), to reduce the computational time. From the sensitivity study on mesh refinement levels, refinement level 12 is chosen, striking a balance between accuracy and computational time. The mass and size distributions of the fragments along the lateral and vertical direction are also studied. A parametric study has been carried out by varying the jet initial velocities to study its influence on the break up and particle size distribution. Detached mass fraction is estimated and particle size distribution is obtained for all the cases and a correlation has been developed between the MMD of the fragments and Weber number.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"442 ","pages":"Article 114223"},"PeriodicalIF":2.1000,"publicationDate":"2025-06-12","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/S0029549325004005","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
During a severe accident in a nuclear reactor, the molten nuclear fuel may interact with the liquid coolant in the form of jet in the reactor vessel. In this work hydrodynamic fragmentation of the Wood’s metal which is a simulant material for corium in water is studied. The 3D numerical model is developed in the open-source DNS solver Basilisk code and validated with experimental results found in literature for low temperature Wood’s metal water system with a discrepancy of about 2.3%. Volume of Fluid (VOF) technique is adopted to capture the liquid–liquid interface and Adaptive Mesh Refinement (AMR), to reduce the computational time. From the sensitivity study on mesh refinement levels, refinement level 12 is chosen, striking a balance between accuracy and computational time. The mass and size distributions of the fragments along the lateral and vertical direction are also studied. A parametric study has been carried out by varying the jet initial velocities to study its influence on the break up and particle size distribution. Detached mass fraction is estimated and particle size distribution is obtained for all the cases and a correlation has been developed between the MMD of the fragments and Weber number.
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.