Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments

被引:15
作者
Xue, Chaochao [1 ,2 ]
Mao, Yulong [3 ]
Zhang, Ziyu [1 ]
Tan, Jibo [1 ]
Wu, Xinqiang [1 ]
Han, En-Hou [1 ]
Ruan, Tianming [3 ]
Li, Jinggang [3 ]
Liao, Jiapeng [3 ]
机构
[1] Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Mat, Shenyang 110016, Peoples R China
[2] Univ Sci & Technol China, Sch Mat Sci & Engn, RChina, Shenyang 110016, Peoples R China
[3] China Nucl Power Technol Res Inst, RChina, Shenzhen 518000, Peoples R China
关键词
Crud deposition mechanism; Nuclear power plant; Simulation facility; Zirconium alloy cladding; Porous structure; Boron enrichment; SIMULATED PRIMARY WATER; PWR PRIMARY WATER; DISSOLVED HYDROGEN; HEATED SURFACES; IRON-OXIDE; BORON; CHEMISTRY; MODEL;
D O I
10.1016/j.jnucmat.2022.153899
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized oxygenated water environments was investigated. Porous crud with typical boiling chimney was found on the cladding surface which is similar to the crud observed in nuclear power plants. Crud particles were identified as Fe2O3 and NiFe2O4 when Fe3+ was added individually and Fe3+ and Ni2+ were injected simultaneously, respectively. Boron enrichment was detected on the whole cross section of the porous crud layer. The mechanisms of crud deposition on the fuel cladding and the boron enrichment within the crud are discussed. (C) 2022 Elsevier B.V. All rights reserved.
引用
收藏
页数:12
相关论文
共 40 条
[1]  
ASAKURA Y, 1978, NUCL SCI ENG, V67, P1
[2]   IRON-OXIDE DEPOSITION ON HEATED SURFACES IN PRESSURIZED BOILING WATER [J].
ASAKURA, Y ;
KIKUCHI, M ;
UCHIDA, S ;
YUSA, H ;
MIKI, M .
NUCLEAR SCIENCE AND ENGINEERING, 1979, 72 (01) :117-120
[3]  
Baek S.-H., 2014, NUCL PLANT CHEM C 20
[4]   Effects of heat flux on fuel crud deposition and sub-cooled nucleate boiling in simulated PWR primary water at 13 MPa [J].
Baek, Seung Heon ;
Shim, Hee-Sang ;
Kim, Jung Gu ;
Hur, Do Haeng .
ANNALS OF NUCLEAR ENERGY, 2019, 133 :178-185
[5]   Effects of dissolved hydrogen on fuel crud deposition and subcooled nucleate boiling in PWR primary water at 328 °C [J].
Baek, Seung Heon ;
Shim, Hee-Sang ;
Kim, Jung Gu ;
Hur, Do Haeng .
NUCLEAR ENGINEERING AND DESIGN, 2019, 345 :85-93
[6]   Effect of chemical etching of fuel cladding surface on crud deposition behavior in simulated primary water of PWRs at 328 °C [J].
Baek, Seung Heon ;
Shim, Hee-Sang ;
Kim, Jung Gu ;
Hur, Do Haeng .
ANNALS OF NUCLEAR ENERGY, 2018, 116 :69-77
[7]   Visualization and acoustic emission monitoring of nucleate boiling on rough and smooth fuel cladding surfaces at atmospheric pressure [J].
Baek, Seung Heon ;
Shim, Hee-Sang ;
Kim, Jung Gu ;
Hur, Do Haeng .
NUCLEAR ENGINEERING AND DESIGN, 2018, 330 :429-436
[8]  
Blok J., 2002, P INT C WAT CHEM NUC, P1
[9]  
Byers W.A., 2014, P INT C NUCL ENG
[10]  
Chen J.X., 2006, P INT C WAT CHEM NUC