核废处理回转煅烧炉用高温合金氧化行为研究#br#

王琴, 王成旭, 刘仲礼

doi:10.16577/j.issn.1001-1560.2025.0013

材料保护 >

2025 , Vol. 58 >Issue 1: 109 - 115

DOI: https://doi.org/10.16577/j.issn.1001-1560.2025.0013

研究论文

核废处理回转煅烧炉用高温合金氧化行为研究#br#

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¹河南机电职业学院机电工程学院； ²烟台大学核装备与核工程学院

刘仲礼(1973－)，博士，教授，主要研究方向为高端装备材料及工艺研究，电话:13573577615，E-mail: liuzhongli＠ytu.edu.cn

收稿日期: 2024-07-22

修回日期: 2024-09-25

录用日期: 2024-09-27

网络出版日期: 2025-02-28

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Study on the Oxidation Behavior of High-Temperature Alloys in Rotary Calciners for Nuclear Waste Treatment

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(1.School of Mechanical and Electrical Engineering， Henan Mechanical and Electrical Vocational College， Zhengzhou 451191， China；2.School of Nuclear Equipment and Engineering， Yantai University， Yantai 264005， China)

LIU Zhongli(1973－)， Ph.D.， Professor， Research Focus: High-End Equipment Materials and Process， Tel.:13573577615， E-mail: liuzhongli＠ytu.edu.cn

Received date: 2024-07-22

Revised date: 2024-09-25

Accepted date: 2024-09-27

Online published: 2025-02-28

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摘要

两步法冷坩埚玻璃固化技术是目前国际主流的高水平放射性废物处理方法，而回转煅烧炉作为其中的关键设备，其结构材料的高温氧化问题关乎该技术的工业化应用，具有重要的研究意义。高温合金具有较好的高温强度，然而其能否作为回转煅烧炉的结构部件有待验证。对316H 不锈钢、镍基690、哈氏N 合金与镍基625 合金4 种高温合金进行了高温氧化试验。通过测量样品的增重，绘制氧化动力学曲线，采用X 射线衍射(XRD)、扫描电镜(SEM)和能谱仪(EDS)分析氧化膜的物相组成、形貌与成分，分析4 种高温合金的氧化机理。结果表明:在600℃下4 种试样都表现出较好的耐氧化性能，其增重均较小。 800 ℃时，哈氏N 合金和316H 不锈钢的耐氧化性能较差，氧化层疏松且有脱落；镍基690 合金的耐氧化性能较好，其氧化层较致密，但氧化膜颗粒较粗大。镍基625 合金的耐氧化性能最佳，氧化速率常数Kp约为1.43×10－7 mg2/(cm4∙s)，其氧化膜由稳定的Cr2O3组成，且氧化膜均匀致密，晶粒细小。镍基625 合金因具有优异的耐氧化性能，可用作回转煅烧炉的结构材料，有利于延长设备的使用寿命。

关键词： 核废处理; 高温合金; 回转煅烧炉; 高温氧化

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王琴, 王成旭, 刘仲礼 . 核废处理回转煅烧炉用高温合金氧化行为研究#br#[J]. 材料保护, 2025 , 58(1) : 109 -115 . DOI: 10.16577/j.issn.1001-1560.2025.0013

Abstract

The two-step cold crucible glass vitrification technology is currently the international mainstream high-level radioactive waste treatment method， and the high-temperature oxidation problem of the structural material of the rotary calcination furnace， as a key equipment， is related to the industrial application of this technology and has important research significance.High-temperature alloy exhibit good high-temperature strength.However， whether it can be used as structural components for the rotary calciner remains to be verified.In this study， high-temperature oxidation tests were conducted on four high-temperature alloys: 316H stainless steel， nickel-based alloy 690， Hastelloy N， and nickel-based alloy 625.The weight gain of the samples was measured， and oxidation kinetics curves were plotted.The phase composition， morphology and composition of the oxide scales were analyzed using X-ray diffraction (XRD)， scanning electron microscopy (SEM) and energydispersive spectroscopy (EDS).The oxidation mechanisms of the four high-temperature alloy were analyzed.The results showed that all four samples exhibited good oxidation resistance at 600 ℃， with relatively small weight gains.At 800 ℃， Hastelloy N and 316H stainless steel showed poor oxidation resistance，with loose oxide layers and spallation.Nickel -based alloy 690 demonstrated better oxidation resistance，with a denser oxide layer， although the oxide particles were relatively large.Nickel- based alloy 625 exhibited the best oxidation resistance， with an oxidation rate constant Kp of approximately 1.43×10－7 mg2/(cm4∙s).The oxide scale was composed of stable Cr2O3， and the oxide layer was uniform， dense and fine-grained.Due to its excellent oxidation resistance，nickel-based alloy 625 can be used as a structural material for rotary calciners， which is beneficial for extending the service life of the equipment.

Key words： nuclear waste treatment; high-temperature alloy; rotary calciner; high-temperature oxidation

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