Xiaojia Li , Xiaoqiang He , Chong Chen , Dongqing Wang , Binghuo Yan , Laishun Wang
{"title":"Experimental study on CHF enhancement of different oxidized surfaces of low carbon steel in nanofluid","authors":"Xiaojia Li , Xiaoqiang He , Chong Chen , Dongqing Wang , Binghuo Yan , Laishun Wang","doi":"10.1016/j.anucene.2024.110923","DOIUrl":null,"url":null,"abstract":"<div><p>Considerable research has been undertaken to explore the use of nanofluids for augmenting the critical heat flux in the in-vessel retention (IVR) strategy deployed in reactors, demonstrating significant improvements in CHF. However, it is important to consider the potential bias in previous studies on surface CHF due to the oxidation of low carbon steel, which is commonly used in reactor vessels, in both air and water under real-life conditions. This study represents the initial investigation into the oxidation behavior of low carbon steel in an air environment, followed by subsequent boiling in water. The results indicate that when the mild steel surface is pre-oxidized in air, the CHF value in deionized water decreases. However, this effect is not readily apparent in nanofluids. Consequently, it suggests that CHF under real operational conditions could be lower than anticipated. Additionally, nanofluids significantly increase the CHF of surface, however, the enhancement of CHF for oxidized surfaces in water is not as pronounced, a point which has never been mentioned by researchers. The mechanisms of surface oxidation and nanofluid-induced CHF enhancement are explained. Consequently, this paper provides important reference value for studying the application of nanofluids in IVR accidents.</p></div>","PeriodicalId":8006,"journal":{"name":"Annals of Nuclear Energy","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-09-15","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/S0306454924005863","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
Considerable research has been undertaken to explore the use of nanofluids for augmenting the critical heat flux in the in-vessel retention (IVR) strategy deployed in reactors, demonstrating significant improvements in CHF. However, it is important to consider the potential bias in previous studies on surface CHF due to the oxidation of low carbon steel, which is commonly used in reactor vessels, in both air and water under real-life conditions. This study represents the initial investigation into the oxidation behavior of low carbon steel in an air environment, followed by subsequent boiling in water. The results indicate that when the mild steel surface is pre-oxidized in air, the CHF value in deionized water decreases. However, this effect is not readily apparent in nanofluids. Consequently, it suggests that CHF under real operational conditions could be lower than anticipated. Additionally, nanofluids significantly increase the CHF of surface, however, the enhancement of CHF for oxidized surfaces in water is not as pronounced, a point which has never been mentioned by researchers. The mechanisms of surface oxidation and nanofluid-induced CHF enhancement are explained. Consequently, this paper provides important reference value for studying the application of nanofluids in IVR accidents.
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.