液态CsIO3与多晶UO2固体表面的相互作用

H. Ishii, Y. Ohishi, H. Muta, M. Uno, K. Kurosaki
{"title":"液态CsIO3与多晶UO2固体表面的相互作用","authors":"H. Ishii, Y. Ohishi, H. Muta, M. Uno, K. Kurosaki","doi":"10.3327/taesj.j19.017","DOIUrl":null,"url":null,"abstract":"Understanding the behavior of melted volatile fission products ( FPs ) on the fuel contributes to the precise assessment of the release behaviour during a severe nuclear accident. A previous study revealed that liquid CsI shows abnormally high wettability with measured contact angles of almost zero degrees against the polycrystalline UO 2 solid surface. [ K. Kurosaki et al., Sci. Rep. 7, Article number: 11449 ( 2017 ) . ] . In this study, we focus on the melting behavior of CsIO 3 and revealed that liquid CsIO 3 also shows high wettability on the polycrystalline UO 2 solid surface. However, after melting, CsIO 3 decomposed and only Cs reacted with the polycrystalline UO 2 solid surface and I was only ab-sorbed on the solid surface. When the CsI had melted on the polycrystalline UO 2 solid surface, both Cs and I were able to penetrate inside the UO 2 pellets. In short, when Cs and I exist as CsIO 3 , Cs and I will be separately released during severe accidents. These findings suggest that the release mecha nisms of Cs and I could be strongly affected by the chemical species in the irradiated fuels.","PeriodicalId":55893,"journal":{"name":"Transactions of the Atomic Energy Society of Japan","volume":"1 1","pages":""},"PeriodicalIF":0.0000,"publicationDate":"2020-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Interaction of Liquid CsIO3 with a Polycrystalline UO2 Solid Surface\",\"authors\":\"H. Ishii, Y. Ohishi, H. Muta, M. Uno, K. Kurosaki\",\"doi\":\"10.3327/taesj.j19.017\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"Understanding the behavior of melted volatile fission products ( FPs ) on the fuel contributes to the precise assessment of the release behaviour during a severe nuclear accident. A previous study revealed that liquid CsI shows abnormally high wettability with measured contact angles of almost zero degrees against the polycrystalline UO 2 solid surface. [ K. Kurosaki et al., Sci. Rep. 7, Article number: 11449 ( 2017 ) . ] . In this study, we focus on the melting behavior of CsIO 3 and revealed that liquid CsIO 3 also shows high wettability on the polycrystalline UO 2 solid surface. However, after melting, CsIO 3 decomposed and only Cs reacted with the polycrystalline UO 2 solid surface and I was only ab-sorbed on the solid surface. When the CsI had melted on the polycrystalline UO 2 solid surface, both Cs and I were able to penetrate inside the UO 2 pellets. In short, when Cs and I exist as CsIO 3 , Cs and I will be separately released during severe accidents. These findings suggest that the release mecha nisms of Cs and I could be strongly affected by the chemical species in the irradiated fuels.\",\"PeriodicalId\":55893,\"journal\":{\"name\":\"Transactions of the Atomic Energy Society of Japan\",\"volume\":\"1 1\",\"pages\":\"\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2020-01-01\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Transactions of the Atomic Energy Society of Japan\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.3327/taesj.j19.017\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"Q4\",\"JCRName\":\"Engineering\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Transactions of the Atomic Energy Society of Japan","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.3327/taesj.j19.017","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q4","JCRName":"Engineering","Score":null,"Total":0}
引用次数: 0

摘要

了解熔化的挥发性裂变产物(FPs)在燃料上的行为有助于精确评估严重核事故中的释放行为。先前的一项研究表明,液态CsI与多晶uo2固体表面的接触角几乎为零,显示出异常高的润湿性。[K. Kurosaki et al.], Sci。提案7,文号:11449(2017)。] . 在本研究中,我们重点研究了csio3的熔融行为,发现液态csio3在多晶uo2固体表面也表现出很高的润湿性。而熔融后csio3分解,只有Cs与多晶uo2固体表面反应,I仅在固体表面被吸收。当CsI在多晶UO 2固体表面熔化时,Cs和I都能够穿透UO 2颗粒内部。简而言之,当Cs和我作为CsIO 3存在时,当发生严重事故时,Cs和我将被分开释放。这些发现表明,辐照燃料中的化学物质可能会强烈影响Cs和I的释放机制。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
Interaction of Liquid CsIO3 with a Polycrystalline UO2 Solid Surface
Understanding the behavior of melted volatile fission products ( FPs ) on the fuel contributes to the precise assessment of the release behaviour during a severe nuclear accident. A previous study revealed that liquid CsI shows abnormally high wettability with measured contact angles of almost zero degrees against the polycrystalline UO 2 solid surface. [ K. Kurosaki et al., Sci. Rep. 7, Article number: 11449 ( 2017 ) . ] . In this study, we focus on the melting behavior of CsIO 3 and revealed that liquid CsIO 3 also shows high wettability on the polycrystalline UO 2 solid surface. However, after melting, CsIO 3 decomposed and only Cs reacted with the polycrystalline UO 2 solid surface and I was only ab-sorbed on the solid surface. When the CsI had melted on the polycrystalline UO 2 solid surface, both Cs and I were able to penetrate inside the UO 2 pellets. In short, when Cs and I exist as CsIO 3 , Cs and I will be separately released during severe accidents. These findings suggest that the release mecha nisms of Cs and I could be strongly affected by the chemical species in the irradiated fuels.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Transactions of the Atomic Energy Society of Japan
Transactions of the Atomic Energy Society of Japan Energy-Nuclear Energy and Engineering
CiteScore
0.50
自引率
0.00%
发文量
16
期刊最新文献
Promotive Effects of Siltfence on Deposition of Suspended Particles: Evaluations of Diffusion Suppression of Radionuclides in Rectangular Open Channel via Numerical Simulations Circulation of Radioactive Cesium in Deciduous Broad-leaved Forests due to the Fukushima Daiichi Nuclear Power Plant Accident Machine Learning Sintering Density Prediction Model for MOX Fuel Pellet マイナーアクチノイド核変換用窒化物燃料の乾式再処理における崩壊熱の影響 Evaluation of external dose exposure of workers during house demolition and dose reduction work in a difficult-to-return zone
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1