Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy

Wu Yazhen; Xi Hang; Li Guoyun; Liu Xiaosong; Zhang Haisheng; Sun Kai; Ning Zhien; Fang Zhongqiang; Liu Shasha

doi:10.13832/j.jnpe.2023.02.0116

Volume 44 Issue 2

Apr. 2023

Turn off MathJax

Article Contents

Article Navigation > Nuclear Power Engineering > 2023 > 44(2): 116-121

Wu Yazhen, Xi Hang, Li Guoyun, Liu Xiaosong, Zhang Haisheng, Sun Kai, Ning Zhien, Fang Zhongqiang, Liu Shasha. Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy[J]. Nuclear Power Engineering, 2023, 44(2): 116-121. doi: 10.13832/j.jnpe.2023.02.0116

Citation:

Wu Yazhen, Xi Hang, Li Guoyun, Liu Xiaosong, Zhang Haisheng, Sun Kai, Ning Zhien, Fang Zhongqiang, Liu Shasha. Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy[J]. Nuclear Power Engineering, 2023, 44(2): 116-121. doi: 10.13832/j.jnpe.2023.02.0116

Citation:

Wu Yazhen, Xi Hang, Li Guoyun, Liu Xiaosong, Zhang Haisheng, Sun Kai, Ning Zhien, Fang Zhongqiang, Liu Shasha. Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy[J]. Nuclear Power Engineering, 2023, 44(2): 116-121. doi: 10.13832/j.jnpe.2023.02.0116

PDF( 11094 KB)

Influence of Neutron Irradiation on Mechanical Properties of Cr-coated Zirconium Alloy

doi: 10.13832/j.jnpe.2023.02.0116

Nuclear Power Institute of China, Chengdu, 610213, China

Received Date: 2022-05-19
Rev Recd Date: 2022-07-05
Publish Date: 2023-04-15

Abstract

Abstract

In order to study the influence of neutron irradiation on the mechanical properties of Cr-coated zirconium alloy, a neutron irradiation test is carried out in this paper for the Cr-coated zirconium alloy prepared by multi-arc ion plating technology. The mechanical properties were conducted by in situ tensile tests and the coating adhesion was analyzed by micron morphology characterization. Results show that Cr coating zircaloy has a similar irradiation effect with commercial zircaloy cladding. Compared with uncoated zircaloy, Cr coating shows that the yield strength and tensile strength increased but percentage elongation after fracture decreased．The Cr coating shows cracks till a large tensile strain without peeling off before rupture. The Cr coating exhibits good mechanical properties and excellent adhesion with Zircaloy Tubes.
- Accident tolerant fuel (ATF) cladding,
- Cr-coated,
- Mechanical properties,
- Neuron irradiation

FullText(HTML)

References(14)

References

[1]	王彦峰,耿娟娟,王毅飞,等. Zr-4合金表面耐事故Cr涂层制备及组织性能[J]. 稀有金属材料与工程,2021, 50(9): 3353-3360.
[2]	CHEN H, WANG X M, ZHANG R Q. Application and development progress of Cr-based surface coatings in nuclear fuel element: I. Selection, preparation, and characteristics of coating materials[J]. Coatings, 2020, 10(9): 808. doi: 10.3390/coatings10090808
[3]	BISCHOFF J, DELAFOY C, VAUGLIN C, et al. AREVA NP's enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding[J]. Nuclear Engineering and Technology, 2018, 50(2): 223-228. doi: 10.1016/j.net.2017.12.004
[4]	KIM H G, KIM I H, JUNG Y I, et al. Out-of-pile performance of surface-modified Zr cladding for accident tolerant fuel in LWRs[J]. Journal of Nuclear Materials, 2018, 510: 93-99. doi: 10.1016/j.jnucmat.2018.07.061
[5]	KASHKAROV E, AFORNU B, SIDELEV D, et al. Recent advances in protective coatings for accident tolerant Zr-based fuel claddings[J]. Coatings, 2021, 11(5): 557. doi: 10.3390/coatings11050557
[6]	ALI A, KIM H G, HATTAR K, et al. Ion irradiation effects on Cr-coated zircaloy-4 surface wettability and pool boiling critical heat flux[J]. Nuclear Engineering and Design, 2020, 362: 110581. doi: 10.1016/j.nucengdes.2020.110581
[7]	段振刚,陈平,周毅,等. 耐事故燃料用Cr涂层锆合金包壳研究进展[J]. 核技术,2022, 45(3): 030001.
[8]	黄鹤,邱长军,陈勇,等. 锆合金表面磁控溅射与多弧离子镀Cr涂层的高温抗氧化性能[J]. 中国表面工程,2018, 31(2): 51-58. doi: 10.11933/j.issn.1007-9289.20170903002
[9]	李锐,刘彤. 脉冲激光熔覆制备ATF包壳Cr涂层的工艺与性能研究[J]. 核动力工程,2019, 40(1): 74-77.
[10]	杨红艳,张瑞谦,彭小明,等. 锆合金包壳表面涂层研究进展[J]. 表面技术,2017, 46(1): 69-77.
[11]	王昱,陈乐,张瑞谦,等. 锆合金管表面Cr涂层的环向拉伸与压扁性能研究[J]. 材料保护,2020, 53(7): 16-22.
[12]	王昱,陈乐,陈寰,等. 锆合金管表面Cr涂层的室温与高温拉伸性能研究[J]. 材料保护,2020, 53(7): 61-66.
[13]	BISCHOFF J, DELAFOY C, CHAARI N, et al. Cr-coated cladding development at Framatome[C]//Proceedings of TopFuel 2018 - Light Water Reactor (LWR) Fuel Performance Meeting 2018. Prague: HAL, 2018.
[14]	杨健乔,恽迪,刘俊凯. 铬涂层锆合金耐事故燃料包壳材料事故工况行为研究进展[J]. 材料导报,2022, 36(1): 20080283.