Enhancing the oxidation behaviors of Zr alloys for nuclear fuel cladding using nanolamellar Cr/CrN coating

被引：10

作者：

Meng, Chuiyi ^{[1
]}

Ma, Jiaojiao ^{[1
]}

Wang, Hui ^{[2
]}

Liu, Wenguan ^{[1
]}

Hu, Yong ^{[3
]}

Zhang, Baoliang ^{[3
]}

Tu, Menghe ^{[3
]}

Yuan, Cenxi ^{[1
]}

He, Xiujie ^{[1
]}

机构：

[1] Sun Yat Sen Univ, Sino French Inst Nucl Engn & Technol, Zhuhai 519082, Guangdong, Peoples R China

[2] Chengdu Univ, Inst Adv Study, Interdisciplinary Mat Res Ctr, Chengdu 610106, Sichuan, Peoples R China

[3] China Inst Atom Energy, Beijing 102413, Peoples R China

来源：

CORROSION SCIENCE | 2024年 / 227卷

基金：

中国国家自然科学基金;

关键词：

Nanolamellar coating; Cr coating; CrN coating; Accident-tolerant fuel; Oxidation; HIGH-TEMPERATURE OXIDATION; CRN; RESISTANCE; SURFACE;

D O I：

10.1016/j.corsci.2023.111725

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Cr, CrN, and nanolamellar Cr/CrN coatings were deposited on Zr-4 substrate by multi-arc ion plating in Ar, N2, and Ar + N2, respectively. The oxidation behaviors of these various types of Cr-based coatings in steam under different temperature-time conditions were compared. The nanolamellar Cr/CrN coating had a smaller weight gain, a smoother oxide surface, fewer pores, no cracks, and could block the interdiffusion between Cr-Zr by generating a ZrN layer. The designed nanolamellar Cr/CrN coating can effectively combine the advantages of Cr and CrN coatings to show better resistance to oxidation. Oxidation mechanisms have also been discussed in detail.

引用

页数：13

共 43 条

[1] Steam Oxidation Evaluation of Fe–Cr Alloys for Accident Tolerant Nuclear Fuel Cladding
B. A. Pint
K. A. Unocic
Oxidation of Metals, 2017, 87 : 515 - 526
[2] The high-temperature oxidation and mechanical properties of the Cr/Zr and CrN/Zr coating
Zhou, Teng
Gao, Xiong
Chen, Huan
Zhang, Rui-Qian
Shang, Lunlin
Zhang, Guangan
Cai, Zhen-Bing
SURFACE TOPOGRAPHY-METROLOGY AND PROPERTIES, 2022, 10 (03)
[3] Steam Oxidation Evaluation of Fe-Cr Alloys for Accident Tolerant Nuclear Fuel Cladding
Pint, B. A.
Unocic, K. A.
OXIDATION OF METALS, 2017, 87 (3-4): : 515 - 526
[4] Restraining the Cr-Zr interdiffusion of Cr-coated Zr alloys in high temperature environment: A Cr/CrN/Cr coating approach
Yang, Jianqiao
Shang, Lunlin
Sun, Jiyuan
Bai, Shuyuan
Wang, Shuzhong
Liu, Junkai
Yun, Di
Ma, Dayan
CORROSION SCIENCE, 2023, 214
[5] Evaluation of corrosion and oxidation behaviors of TiAlCrN coatings for nuclear fuel cladding
Ma, Xian-Feng
Wu, Ya-Wen
Tan, Jie
Meng, Chui-Yi
Yang, Liu
Dang, Wei-An
He, Xiu-Jie
SURFACE & COATINGS TECHNOLOGY, 2019, 358 : 521 - 530
[6] SiC coating as hydrogen permeation reduction and oxidation resistance for nuclear fuel cladding
Usui, Takahiro
Sawada, Akihiko
Amaya, Masaki
Suzuki, Akihiro
Chikada, Takumi
Terai, Takayuki
JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2015, 52 (10) : 1318 - 1322
[7] Autoclave grid-to-rod fretting corrosion behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization
Zhao, Yahuan
Bai, Yaxiong
Yang, Jie
Shen, Yifei
Lou, Yuxin
Zhang, Kun
Wu, Yiheng
Li, Yangxin
Li, Jin
Cui, Zhexin
Wei, Tianguo
Ma, Shuo
Shen, Zhao
Wang, Hui
Zeng, Xiaoqin
CORROSION SCIENCE, 2024, 239
[8] Monitoring the oxidation of nuclear fuel cladding using Raman spectroscopy
Mi, Hongyi
Mikael, Solomon
Allen, Todd
Sridharan, Kumar
Butt, Darryl
Blanchard, James P.
Ma, Zhenqiang
JOURNAL OF NUCLEAR MATERIALS, 2014, 445 (1-3) : 7 - 11
[9] Oxidation behavior of RF magnetron sputtered Cr-SiC-Cr composites coating on zircaloy fuel cladding
Li, Guangbin
Liu, Yanhong
Zhang, Yingchun
Li, Huailin
Wang, Xiaojing
Zheng, Mingmin
MATERIALS RESEARCH EXPRESS, 2019, 6 (09):
[10] Review on the Preparation and High-Temperature Oxidation Resistance of Metal Coating for Fuel Cladding Zirconium Alloys
Sun, Ling
Xiao, Yuchen
Huang, Weijiu
Luan, Baifeng
Wu, Baoan
Tang, Huiyi
NUCLEAR SCIENCE AND ENGINEERING, 2024, 198 (04) : 755 - 770

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