{"title":"Research on the key design of emergency core cooling scheme for Tsinghua high flux reactor","authors":"","doi":"10.1016/j.anucene.2024.110898","DOIUrl":null,"url":null,"abstract":"<div><p>This paper introduces the updated emergency core cooling scheme for Tsinghua High Flux Reactor. The corresponding Relap5 model is established and key designs are studied by simulating the corresponding loss-of-coolant accidents. These key designs specifically involve ACC internal pressure, ACC coolant temperature, ACC liquid fraction, ACC location, emergency pumps, check valves at pressure vessel inlets, the design of pressure vessel outlet, connection between the dry pool and the reactor pool, and operation pressure. Through analysis, some general conclusions are obtained, which can be used to guide the design of emergency core cooling system in the near future. Critical heat flux is predicted by Sudo correlations during loss-of-coolant accidents. According to minimum departure from nucleate boiling ratio, core safety margin is evaluated. By studying these key designs, the current scheme can be better understood and more safety margins can be found.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-05","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/S0306454924005619","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
This paper introduces the updated emergency core cooling scheme for Tsinghua High Flux Reactor. The corresponding Relap5 model is established and key designs are studied by simulating the corresponding loss-of-coolant accidents. These key designs specifically involve ACC internal pressure, ACC coolant temperature, ACC liquid fraction, ACC location, emergency pumps, check valves at pressure vessel inlets, the design of pressure vessel outlet, connection between the dry pool and the reactor pool, and operation pressure. Through analysis, some general conclusions are obtained, which can be used to guide the design of emergency core cooling system in the near future. Critical heat flux is predicted by Sudo correlations during loss-of-coolant accidents. According to minimum departure from nucleate boiling ratio, core safety margin is evaluated. By studying these key designs, the current scheme can be better understood and more safety margins can be found.
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.