Liquid metal embrittlement of 12Cr ferritic/martensitic steel thin-walled tubes exposed to liquid lead-bismuth eutectic - Details

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In　this　work,　liquid　metal　embrittlement　(LME)　susceptibility　of　12Cr　ferritic/martensitic　(F/M)　thin-walled　tubes　has　been　tested　in　liquid　lead-bismuth　eutectic　(LBE)　under　different　temperatures　(i.e.,　350,　400　and　450　°C),　oxygen　concentrations　(i.e.,　oxygen-poor　and　oxygen-saturated)　and　strain　rates　(i.e.,　5　×10−5,　1　×10−6　and　5　×10−7　s−1).　The　results　show　that　LME　occurs　under　nearly　all　the　testing　conditions,　and　the　most　influential　factors　upon　the　LME　susceptibility　are　oxygen　concentration　and　strain　rate.　Transmission　electron　microscopy　(TEM)　characterization　at　crack　tips　shows　that　LME　cracks　propagate　preferentially　along　microstructural　boundaries,　such　as　martensite　lath　boundaries,　subgrain　boundaries　and　carbides/lath　interphase　boundaries.　©　2021　Elsevier　Ltd

Keyword：

Bismuth Carbides Crack tips Embrittlement Eutectics Ferrite High resolution transmission electron microscopy Liquid metals Oxygen Strain rate Thin walled structures

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[ 1 ] [Wang, Hao]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 2 ] [Gong, Xing]Advanced Nuclear Energy Research Team, Department of Nuclear Science and Technology, College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen; 518060, China
[ 3 ] [Xiao, Jun]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 4 ] [Chai, Linjiang]College of Materials Science and Engineering, Chongqing University of Technology, Chongqing; 400054, China
[ 5 ] [Yu, Zhiyang]State Key Laboratory of Photocatalysis on Energy and Environment, College of Chemistry, Fuzhou University, Fuzhou; 350002, China
[ 6 ] [Chen, Haitao]Advanced Nuclear Energy Research Team, Department of Nuclear Science and Technology, College of Physics and Optoelectronic Engineering, Shenzhen University, Shenzhen; 518060, China
[ 7 ] [Zhao, Ke]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 8 ] [Zhou, Jun]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 9 ] [Liu, Guiliang]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 10 ] [Chen, Yong]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China
[ 11 ] [Qiu, Shaoyu]Science and Technology on Reactor Fuel and Materials Laboratory, Nuclear Power Institute of China, Chengdu; 610213, China

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Source ：

Corrosion Science

ISSN： 0010-938X

Year： 2022

Volume： 195

8 . 3

JCR@2022

7 . 4 0 0

JCR@2023

ESI HC Threshold：91

JCR Journal Grade：1

CAS Journal Grade：1

Cited Count：

WoS CC Cited Count： 0

SCOPUS Cited Count： 14

ESI Highly Cited Papers on the List： 0 Unfold All

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Chinese Cited Count：

30 Days PV： 1

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