期刊论文

Xiao, W.

中文

核技术

0253-3219

2022

45

10

9-17

10.11889/j.0253-3219.2022.hjs.45.100202

湖南省自然科学基金(No.2020JJ5467)资助 第一作者：雷明，男，1988年出生，2015年于南华大学获硕士学位，研究领域为核燃料 通信作者：肖魏魏，E-mail：xiaowei_tw618@sina.com 收稿日期：2022-04-26，修回日期：2022-07-05 Supported by Natural Science Foundation of Hunan Province (No.2020JJ5467) Firstauthor:LEIMing,male,bornin1988,graduatedfromUniversityofSouthChinawithamaster'sdegreein2015,focusingonnuclearfuel Corresponding author: XIAO W eiwei , E-mail: xiaowei_tw618@sina.com Received date: 2022-04-26, revised date: 2022-07-05

本校为第一机构

2011年的福岛核事故暴露出锆合金包壳抗高温氧化性能的不足。为此，国际核燃料领域提出了耐事故燃料这一概念。Cr涂层锆合金包壳作为耐事故燃料包壳近期可商用的技术途径得到了广泛关注。本文旨在研究Cr涂层Zr-4合金在不同温度下的高温氧化行为，采用多弧离子镀技术制备Cr涂层Zr-4合金样品，并在800?1 200 ℃空气气氛中氧化4 h，采用扫描电子显微镜（Scanning Electron Microscope，SEM）、能量色散谱仪（Energy Dispersive Spectrometer，EDS）、电子背散射衍射（Electron Backscatter Diffraction，EBSD）和掠射角X射线衍射仪（X-ray diffractometer，XRD）表征Cr涂层Zr-4合金样品在高温氧化前...

[Background] The Fukushima nuclear accident in 2011 exposed the shortcoming of high temperature oxidation resistance of zirconium alloy cladding. For this reason, the concept of accident tolerant fuel was proposed in the international nuclear fuel field. Cr-coated zirconium alloy cladding, as an accident tolerant fuel cladding near-term commercial technology approach, has received extensive attention. [Purpose] This study aims to study the high-temperature oxidation behavior of Cr-coated Zr-4 alloys at different temperatures. [Methods] Cr-coate...