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

被引：0

作者：

Wu Y. ^{[1
]}

Xi H. ^{[1
]}

Li G. ^{[1
]}

Liu X. ^{[1
]}

Zhang H. ^{[1
]}

Sun K. ^{[1
]}

Ning Z. ^{[1
]}

Fang Z. ^{[1
]}

Liu S. ^{[1
]}

机构：

[1] Nuclear Power Institute of China, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2023年 / 44卷 / 02期

关键词：

Accident tolerant fuel (ATF) cladding; Cr-coated; Mechanical properties; Neuron irradiation;

D O I：

10.13832/j.jnpe.2023.02.0116

中图分类号：

学科分类号：

摘要：

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. © 2023 Yuan Zi Neng Chuban She. All rights reserved.

引用

页码：116 / 121

页数：5

共 14 条

[1]

50, 9, pp. 3353-3360, (2021)

[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, Coatings, 10, 9, (2020)

[3]

BISCHOFF J, DELAFOY C, VAUGLIN C, Et al., AREVA NP's enhanced accident-tolerant fuel developments: focus on Cr-coated M5 cladding, Nuclear Engineering and Technology, 50, 2, pp. 223-228, (2018)

[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, Journal of Nuclear Materials, 510, pp. 93-99, (2018)

[5]

KASHKAROV E, AFORNU B, SIDELEV D, Et al., Recent advances in protective coatings for accident tolerant Zr-based fuel claddings, Coatings, 11, 5, (2021)

[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, Nuclear Engineering and Design, 362, (2020)

[7]

45, 3, (2022)

[8]

31, 2, pp. 51-58, (2018)

[9]

40, 1, pp. 74-77, (2019)

[10]

46, 1, pp. 69-77, (2017)

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