Study of oxidation behavior and tensile properties of candidate superalloys in the air ingress simulation scenario

被引:7
作者
Du, Bin [1 ]
Li, Haoxiang [1 ]
Zheng, Wei [1 ]
He, Xuedong [1 ]
Ma, Tao [1 ]
Yin, Huaqiang [1 ]
机构
[1] Tsinghua Univ, Inst Nucl & New Energy Technol, Key Lab Adv Reactor Engn & Safety, Minist Educ, Beijing 100084, Peoples R China
基金
中国国家自然科学基金; 国家重点研发计划;
关键词
VHTR; Air ingress; Superalloy; High-temperature corrosion; Tensile properties; HIGH-TEMPERATURE; ALLOY; 617; DEGREES-C; HELIUM; CORROSION;
D O I
10.1016/j.net.2022.09.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
Air ingress incidents are major safety accidents in very-high-temperature reactors (VHTRs). Air con-taining a high volume fraction of oxygen may cause severe oxidation of core components at the VHTR, especially for the significantly thin alloy tube wall in the intermediate heat exchanger (IHE). The research objects of this study are Inconel 617 and Incoloy 800H, two candidate alloys for IHE in VHTR. The air ingress accident scenario is simulated with high-temperature air flow at 950 degrees C. A continuous oxide scale was formed on the surfaces of both the alloys after the experiment. Because the oxide scale of Inconel 617 has a loose structure, whereas that of Incoloy 800H is denser, Inconel 617 exhibited significantly more severe internal oxidation than Incoloy 800H. Further, Inconel 617 showed a significant decrease in ul-timate tensile strength and plasticity after aging for 200 h, whereas Incoloy 800H maintained its tensile properties satisfactorily. Through control experiment under vacuum, we preliminarily concluded that serious internal oxidation is the primary reason for the decline in the tensile properties of Inconel 617.(c) 2023 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
引用
收藏
页码:71 / 79
页数:9
相关论文
共 30 条
[1]   Computational phase diagrams for the Nd-based magnets based on the combined ab initio/CALPHAD approach [J].
Abe, Taichi ;
Chen, Ying ;
Saengdeejimg, Arkapol ;
Kobayashi, Yoshinao .
SCRIPTA MATERIALIA, 2018, 154 :305-310
[2]   A review and safety aspects of modular high-temperature gas-cooled reactors [J].
Alshehri, Salman M. ;
Said, Ibrahim A. ;
Usman, Shoaib .
INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2021, 45 (08) :11479-11492
[3]   Energy: Nuclear power's new dawn [J].
Butler, D .
NATURE, 2004, 429 (6989) :238-240
[4]   Assessing the kinetics of high temperature oxidation of Inconel 617 in a dedicated HTR impure helium facility coupling thermogravimetry and gas phase chromatography [J].
Chapovaloff, J. ;
Rouillard, F. ;
Combrade, P. ;
Pijolat, M. ;
Wolski, K. .
JOURNAL OF NUCLEAR MATERIALS, 2013, 441 (1-3) :293-300
[5]  
Chase M W., 1998, J Phys Chem Ref Data, V9, P1, DOI 10.18434/T42S31
[6]   CORROSION OF METALLIC MATERIALS IN HTR-HELIUM ENVIRONMENTS [J].
GRAHAM, LW .
JOURNAL OF NUCLEAR MATERIALS, 1990, 171 (01) :76-83
[7]  
Guo JT, 2010, Materials science and engineering for superalloy
[8]   CATION DIFFUSION IN CR2O3 [J].
HAGEL, WC ;
SEYBOLT, AU .
JOURNAL OF THE ELECTROCHEMICAL SOCIETY, 1961, 108 (12) :1146-1152
[9]   Oxidation behaviour of an Alloy 617 in very high-temperature air and helium environments [J].
Jang, Changheui ;
Lee, Daejin ;
Kim, Daejong .
INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2008, 85 (06) :368-377
[10]   Thermal Degradation Behavior of Inconel 617 Alloy [J].
Jo, Tae Sun ;
Kim, Se-Hoon ;
Kim, Dae-Gun ;
Park, Ji Yeon ;
Kim, Young Do .
METALS AND MATERIALS INTERNATIONAL, 2008, 14 (06) :739-743