• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利：CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法，用中文像聊天一样搜索，搜遍4000万医学文献。AI智能推荐，让科研检索更轻松。

立即免费搜索

文件翻译

保留排版，准确专业，支持PDF/Word/PPT等文件格式，支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述，25分钟生成高质量综述，智能提取关键信息，辅助科研写作。

立即免费体验

压水堆模拟一回路水中质子辐照核级不锈钢的晶界氧化

Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor.

作者信息

Deng Ping, Peng Qunjia, Han En-Hou

机构信息

Nuclear Power Institute of China, Chengdu City, 610213, China.

Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang City, 110016, China.

出版信息

Sci Rep. 2021 Jan 14;11(1):1371. doi: 10.1038/s41598-020-80600-x.

DOI:10.1038/s41598-020-80600-x
PMID:33446760
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC7809272/
Abstract

Grain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail.

摘要

研究了质子辐照的304核级不锈钢在压水反应堆一回路水中的晶界（GB）氧化。通过结合原子探针断层扫描和透射电子显微镜，在“逐个原子”的基础上研究晶界处形成的氧化物和氧化物前驱体的微观结构来进行此项研究。结果表明，增加辐照剂量会促进晶界氧化，这与晶界处形成的不同氧化物和氧化物前驱体相对应。已详细讨论了氧化物和氧化物前驱体与晶界氧化行为的相关性。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/62b5fc99b09d/41598_2020_80600_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/542c2bf2cde1/41598_2020_80600_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/f933a53a20a3/41598_2020_80600_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/97d56b225bde/41598_2020_80600_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/dda26ca22ec0/41598_2020_80600_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/6d3c5cb64534/41598_2020_80600_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/62b5fc99b09d/41598_2020_80600_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/542c2bf2cde1/41598_2020_80600_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/f933a53a20a3/41598_2020_80600_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/97d56b225bde/41598_2020_80600_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/dda26ca22ec0/41598_2020_80600_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/6d3c5cb64534/41598_2020_80600_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/b3ba/7809272/62b5fc99b09d/41598_2020_80600_Fig6_HTML.jpg

相似文献

1
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor.压水堆模拟一回路水中质子辐照核级不锈钢的晶界氧化
Sci Rep. 2021 Jan 14;11(1):1371. doi: 10.1038/s41598-020-80600-x.
2
Author Correction: Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor.作者更正：压水堆模拟一回路水中质子辐照核级不锈钢的晶界氧化
Sci Rep. 2021 Apr 22;11(1):9162. doi: 10.1038/s41598-021-88868-3.
3
Examinations of oxidation and sulfidation of grain boundaries in alloy 600 exposed to simulated pressurized water reactor primary water.研究合金 600 暴露于模拟压水堆一回路水中晶界的氧化和硫化情况。
Microsc Microanal. 2013 Jun;19(3):676-87. doi: 10.1017/S1431927613000421. Epub 2013 Apr 17.
4
Recrystallisation behaviour of a fully austenitic Nb-stabilised stainless steel.一种完全奥氏体化的铌稳定不锈钢的再结晶行为。
J Microsc. 2019 Apr;274(1):3-12. doi: 10.1111/jmi.12776. Epub 2018 Dec 17.
5
Three-dimensional geometrical and topological characteristics of grains in conventional and grain boundary engineered 316L stainless steel.常规及晶界工程316L不锈钢中晶粒的三维几何和拓扑特征
Micron. 2018 Jun;109:58-70. doi: 10.1016/j.micron.2018.04.002. Epub 2018 Apr 10.
6
Evaluation of Grain Boundary Network and Improvement of Intergranular Cracking Resistance in 316L Stainless Steel after Grain Boundary Engineering.316L不锈钢晶界工程后晶界网络评估及抗晶间开裂性能的改善
Materials (Basel). 2019 Jan 12;12(2):242. doi: 10.3390/ma12020242.
7
Using transmission Kikuchi diffraction to study intergranular stress corrosion cracking in type 316 stainless steels.利用透射菊池衍射研究316型不锈钢的晶间应力腐蚀开裂。
Micron. 2015 Aug;75:1-10. doi: 10.1016/j.micron.2015.04.011. Epub 2015 Apr 27.
8
Level-Set Modeling of Grain Growth in 316L Stainless Steel under Different Assumptions Regarding Grain Boundary Properties.316L不锈钢中晶界特性不同假设下晶粒长大的水平集建模
Materials (Basel). 2022 Mar 25;15(7):2434. doi: 10.3390/ma15072434.
9
Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation.重离子辐照后纳米结构铁素体合金14YWT中纳米级偏析的研究
Materials (Basel). 2022 Oct 17;15(20):7257. doi: 10.3390/ma15207257.
10
Probing Grain-Boundary Chemistry and Electronic Structure in Proton-Conducting Oxides by Atom Probe Tomography.通过原子探针层析技术探测质子导体氧化物中的晶界化学和电子结构。
Nano Lett. 2016 Nov 9;16(11):6924-6930. doi: 10.1021/acs.nanolett.6b02918. Epub 2016 Oct 5.

引用本文的文献

1
Long-time irradiation effect on corrosion behavior of aluminum alloy in pool water of low-power research reactor.长期辐照对低功率研究堆池水中铝合金腐蚀行为的影响
Sci Rep. 2023 Oct 9;13(1):17007. doi: 10.1038/s41598-023-44287-0.