中子辐照对耐事故燃料FeCrAl合金力学性能的影响研究

雷阳; 张海生; 毛建军; 刘晓松; 乔英杰; 王鹏; 吴亚贞; 肖文霞

doi:10.13832/j.jnpe.2022.01.0097

中子辐照对耐事故燃料FeCrAl合金力学性能的影响研究

doi: 10.13832/j.jnpe.2022.01.0097

1.
中国核动力研究设计院，成都， 610213
2.
哈尔滨工程大学，哈尔滨， 150001

基金项目: 国家重点研发计划项目（2016YFB0700105）

详细信息

作者简介:
雷　阳（1987—），男，副研究员，现从事核燃料及核材料辐照后性能检验工作，E-mail: lyeiang1818@126.com

中图分类号: TG139⁺.4
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出版历程
- 收稿日期: 2020-11-30
- 修回日期: 2021-01-07
- 刊出日期: 2022-02-01

Effect of Neutron Irradiation on Mechanical Properties of Accident-Tolerant Fuel FeCrAl Alloys

1.
Nuclear Power Institute of China, Chengdu, 610213, China
2.
Harbin Engineering University, Harbin, 150001, China

摘要

摘要: FeCrAl合金具有良好的抗高温氧化和力学性能，能够作为燃料包壳材料。为研究FeCrAl合金的辐照力学性能，开展了不同元素成分含量和2×10¹⁹ cm⁻²、8×10¹⁹ cm⁻²2种中子注量辐照下的FeCrAl合金力学性能试验，并在室温和380℃下测试了FeCrAl合金的拉伸性能，获得了不同Cr和Al含量FeCrAl合金的抗拉强度和屈服强度，并研究了Al含量、Cr/Al含量配比及中子辐照对FeCrAl合金力学性能的影响。研究表明，FeCrAl合金强度随着Al含量增加大致呈增加趋势；经2×10¹⁹ cm⁻²中子辐照后，FeCrAl合金强度有较大提升；再经8×10¹⁹ cm⁻²中子辐照后，FeCrAl合金强度升高不明显。该研究结果为耐事故燃料（ATF）包壳材料的研发选型提供了重要的数据支撑。
- FeCrAl合金 /
- 耐事故燃料 /
- 力学性能 /
- 辐照效应
Abstract: FeCrAl alloy has good high-temperature oxidation resistance and mechanical properties and can be used as fuel cladding material. In order to study the irradiation mechanical properties of FeCrAl alloy, FeCrAl alloy mechanical properties test with different element contents and 2×10¹⁹ cm⁻² and 8×10¹⁹ cm⁻²neutron fluence irradiation was carried out, the tensile properties of FeCrAl alloys were tested at room temperature and 380℃, and the tensile strength and yield strength of FeCrAl alloys with different Cr and Al contents were obtained. The effects of Al content, Cr/Al content ratio and neutron irradiation on the mechanical properties of FeCrAl alloy were studied. The results show that the strength of FeCrAl alloy generally increases with the increase of Al content; After 2×10¹⁹ cm⁻² neutron irradiation, the strength of FeCrAl alloy is greatly improved; After 8×10¹⁹ cm⁻²neutron irradiation, the strength of FeCrAl alloy does not increase significantly. The research results provide important data support for the R&D and selection of accident-tolerant fuel cladding.
- FeCrAl alloy /
- Accident-tolerant fuel (ATF) /
- Mechanical properties /
- Irradiation effect

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图 1 辐照试验装置结构示意图

Figure 1. Schematic Diagram of the Irradiation Test Device Structure

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图 2 不同Al含量的FeCrAl合金强度对比

Figure 2. Strength Comparison of FeCrAl Alloys with Different Al Contents

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图 3 不同Cr/Al含量比的FeCrAl合金抗拉强度对比

Figure 3. Comparison of Tensile Strength of FeCrAl Alloys with Different Cr/Al Content Ratios

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图 4 不同中子注量辐照后FeCrAl合金性能对比

Figure 4. Comparison of Properties of FeCrAl Alloys Irradiated by Different Neutron Fluences

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