{"title":"A detailed review on critical flow experiments and models","authors":"Gengyuan Tian , Yuan Zhou , Yanping Huang , Yuan Yuan , Chengtian Zeng","doi":"10.1016/j.anucene.2025.111441","DOIUrl":null,"url":null,"abstract":"<div><div>Critical flow is a significant phenomenon in reactor safety analysis, which has remained a research focus for several decades. The critical flow rate determines the rate of coolant loss in the reactor and the rate of pressure relief in the primary loop. Owing to the multiplicity of parameters influencing critical flow and the complexity of the flow phenomenon, there exists an incomplete cognition of the critical flow phenomenon at present, and precisely calculating the critical flow rate under various working conditions is extremely challenging. Consequently, this paper presents a comprehensive review of the experimental and theoretical studies on critical flow carried out in various thermodynamic regions. It summarizes the current progress and deficiencies in experimental research and concurrently compiles the experimental research data to offer database support for other researchers engaged in theoretical studies of critical flow. A brief but comprehensive overview of the existing theoretical models and general modeling framework for critical flow phenomena is provided. It is conducive to the further understanding and investigation of the critical flow phenomenon.</div></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":"219 ","pages":"Article 111441"},"PeriodicalIF":1.9000,"publicationDate":"2025-04-12","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Annals of Nuclear Energy","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0306454925002580","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
Critical flow is a significant phenomenon in reactor safety analysis, which has remained a research focus for several decades. The critical flow rate determines the rate of coolant loss in the reactor and the rate of pressure relief in the primary loop. Owing to the multiplicity of parameters influencing critical flow and the complexity of the flow phenomenon, there exists an incomplete cognition of the critical flow phenomenon at present, and precisely calculating the critical flow rate under various working conditions is extremely challenging. Consequently, this paper presents a comprehensive review of the experimental and theoretical studies on critical flow carried out in various thermodynamic regions. It summarizes the current progress and deficiencies in experimental research and concurrently compiles the experimental research data to offer database support for other researchers engaged in theoretical studies of critical flow. A brief but comprehensive overview of the existing theoretical models and general modeling framework for critical flow phenomena is provided. It is conducive to the further understanding and investigation of the critical flow phenomenon.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.