Failure analysis of damaged tungsten monoblock components of upper divertor outer target in EAST fusion device

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

2 Scopus Citations
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Author(s)

  • Kang Wang
  • Xiang Zan
  • Dahuan Zhu
  • Laima Luo
  • Rui Ding
  • Yucheng Wu

Detail(s)

Original languageEnglish
Pages (from-to)2307-2316
Journal / PublicationNuclear Engineering and Technology
Volume56
Issue number6
Online published2 Feb 2024
Publication statusPublished - Jun 2024

Link(s)

Abstract

A melting failure of W monoblock components of the upper divertor outer target in EAST occurred during the plasma campaigns in 2019. The failure characters and microstructure evolution of the failed W monoblock have been well investigated on one string (W436 string). Near the strike point region where heat flux density is highest, macroscopic cracks and severe surface damage such as dimensional change, melting and solidification are visible in several W monoblocks. At the same time, debonding, melting and migration of Cu/CuCrZr cooling tube components introduced fatal damage to the structure and function. The heat-induced microstructure evolution in the rest part has been examined via hardness tests and metallography. From the heat flux surface to the cooling tube, hardness increased gradually and the recrystallized grains could be found in the region with the highest temperature, while recrystallization grains also appear in some W monoblocks near the cooling tube area. The detailed microstructure has been investigated by metallography and EBSD. Such cases in EAST provide experiences on the extreme condition of accidental loss of coolant or higher discharge power in future devices. © 2024 Korean Nuclear Society.

Research Area(s)

  • Crack, Divertor, EAST fusion device, Recrystallization, Tungsten monoblock

Citation Format(s)

Failure analysis of damaged tungsten monoblock components of upper divertor outer target in EAST fusion device. / Wang, Kang; Xi, Ya; Zan, Xiang et al.
In: Nuclear Engineering and Technology, Vol. 56, No. 6, 06.2024, p. 2307-2316.

Research output: Journal Publications and ReviewsRGC 21 - Publication in refereed journalpeer-review

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