“单侧高热负荷条件下用于聚变反应堆导流器的螺旋管传热特性”的勘误[j]。J. Adv.核反应堆。工业技术，3 (2021)213-225 [j]

{"title":"“单侧高热负荷条件下用于聚变反应堆导流器的螺旋管传热特性”的勘误[j]。J. Adv.核反应堆。工业技术，3 (2021)213-225 [j]","authors":"Ji Hwan Lim , Su Won Lee , Hoongyo Oh , Minkyu Park , Donkoan Hwang , Moo Hwan Kim , HangJin Jo","doi":"10.1016/j.jandt.2022.02.002","DOIUrl":null,"url":null,"abstract":"","PeriodicalId":100689,"journal":{"name":"International Journal of Advanced Nuclear Reactor Design and Technology","volume":"4 1","pages":"Page 25"},"PeriodicalIF":0.0000,"publicationDate":"2022-03-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://www.sciencedirect.com/science/article/pii/S2468605022000023/pdfft?md5=c85a2a0d669d7f7632523a464d54bcc5&pid=1-s2.0-S2468605022000023-main.pdf","citationCount":"0","resultStr":"{\"title\":\"Corrigendum to “Heat-transfer characteristics of screw tube in one-side high heat load condition for fusion reactor divertor application”[Int. J. Adv. Nucl. Reactor. Des. Technol. 3 (2021) 213–225]\",\"authors\":\"Ji Hwan Lim , Su Won Lee , Hoongyo Oh , Minkyu Park , Donkoan Hwang , Moo Hwan Kim , HangJin Jo\",\"doi\":\"10.1016/j.jandt.2022.02.002\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"\",\"PeriodicalId\":100689,\"journal\":{\"name\":\"International Journal of Advanced Nuclear Reactor Design and Technology\",\"volume\":\"4 1\",\"pages\":\"Page 25\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2022-03-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"https://www.sciencedirect.com/science/article/pii/S2468605022000023/pdfft?md5=c85a2a0d669d7f7632523a464d54bcc5&pid=1-s2.0-S2468605022000023-main.pdf\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"International Journal of Advanced Nuclear Reactor Design and Technology\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S2468605022000023\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"International Journal of Advanced Nuclear Reactor Design and Technology","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S2468605022000023","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}