Effect of Hydrogen, Hydride Orientation and Temperature on Low-Cycle Fatigue Resistance of Zr-1%Nb Fuel Rod Claddings

Q2 Energy

Nuclear and Radiation Safety Pub Date : 2021-12-15 DOI:10.32918/nrs.2021.4(92).07

G. Riedkina, V. Grytsyna, S. Klymenko, Т. Chernyayeva

引用次数: 0

Abstract

Low-cycle fatigue testing was conducted on annular samples with an outer diameter of 9.13 mm, a wall thickness of 0.68 mm and a width of 2.7 mm, namely: non-hydrogenated samples (cut out of standard Zr‑1%Nb cladding tubes); hydrogenated samples with a hydrogen concentration of 50 ... 400 ppm; samples cut out from hydrogenated dummy claddings after hydride reorientation tests performed according to various test modes. The tests were conducted at the temperatures of 25, 180, 350, 400 and 450 °С. The results obtained demonstrate that with increasing the hydrogen content in Zr-1%Nb alloy claddings the fatigue life increases.

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氢、氢化物取向和温度对Zr-1%Nb燃料棒包层抗低周疲劳性能的影响

对外径9.13 mm、壁厚0.68 mm、宽2.7 mm的环形试样进行低周疲劳试验，即:未氢化试样(从标准Zr - 1%Nb包层管中切割出来);氢化样品的氢浓度为50…400 ppm;根据各种试验模式进行氢化物重定向试验后，从氢化假包层中切割出的样品。测试分别在25、180、350、400和450°С温度下进行。结果表明，随着Zr-1%Nb合金熔覆层中氢含量的增加，合金的疲劳寿命增加。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

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来源期刊

Nuclear and Radiation Safety Energy-Nuclear Energy and Engineering

CiteScore

0.80

自引率

0.00%

发文量

期刊介绍： General issues of nuclear energy use; nuclear energy (reactor theory and calculations, operation of nuclear power plants, NPP safety analysis (probabilistic safety analysis, deterministic safety analysis), research reactors, nuclear fuel and structural materials, fuel elements; neutron physics; general safety issues; decommissioning of nuclear facilities; long-term operation, spent fuel and radioactive waste management; radiation safety; I&C, physical protection.