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Author:

Lin, J. (Lin, J..) | Zhou, Z. (Zhou, Z..) | Ji, S. (Ji, S..) | Wan, Z. (Wan, Z..) | Lu, L. (Lu, L..)

Indexed by:

Scopus SCIE

Abstract:

The zirconium alloy clad tube provides a protection and room for the nuclear reaction of fuel rods in the nuclear power plant. The clad tubes are usually sealed up by pressure resistance welding with the end plugs. The non-equilibrium physical metallurgy, caused by welding, often brings about a non-uniformity of microstructure and corrosion resistance in the zirconium alloy joint. In order to investigate the influence of the microstructure on the service performance of the welded joint corrosion experiments were designed and conducted by amplifying the mechanical and heat-affected zone in the joint, using a thermal and mechanical simulation machine. It was shown that the amplified sample had the similar microstructure and micro hardness with the mechanical and heat-affected zone. The corrosion rate of the mechanical and heat-affected zone was higher than that of the base metal of the clad tube. A heat treatment after welding was proposed to weaken the influence of microstructure difference on its corrosive resistance. It was shown that the corrosive resistance could be improved by modifying the microstructure appearance and the distribution of the second phase particles. © 2025 Korean Nuclear Society

Keyword:

Heat treatment Corrosion resistance Zirconium alloy Pressure resistance welded joint Clad tube

Author Community:

  • [ 1 ] [Lin J.]College of Materials Science and Engineering, Beijing University of Technology, Beijing, 100124, China
  • [ 2 ] [Zhou Z.]College of Materials Science and Engineering, Beijing University of Technology, Beijing, 100124, China
  • [ 3 ] [Ji S.]College of Materials Science and Engineering, Beijing University of Technology, Beijing, 100124, China
  • [ 4 ] [Wan Z.]College of Materials Science and Engineering, Beijing University of Technology, Beijing, 100124, China
  • [ 5 ] [Lu L.]Suzhou Nuclear Power Research Institute, Suzhou, 215004, China

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Source :

Nuclear Engineering and Technology

ISSN: 1738-5733

Year: 2025

Issue: 7

Volume: 57

2 . 7 0 0

JCR@2022

Cited Count:

WoS CC Cited Count:

SCOPUS Cited Count:

ESI Highly Cited Papers on the List: 0 Unfold All

WanFang Cited Count:

Chinese Cited Count:

30 Days PV: 14

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