Published June 2012 | Version v1
Journal article

Development of welding methods for dissimilar joint of Alloy 690 and stainless steel for PWR components

  • 1. IHI Corp., Corporate Research and Development, Tokyo (Japan)
  • 2. IHI Corp., Nuclear Power Operations, Yokohama, Kanagawa (Japan)

Description

In this study, hot crack susceptibility of several kinds of Alloy 690 weld materials was evaluated by Varestraint and hot ductility testing. The susceptibilities of the Solidification Cracking (SC), the Liquation Cracking (LC), and the Ductility Dip Cracking (DDC) of each filler material were independently evaluated by spot-Varestraint and transverse-Varestraint testing, and the susceptibilities of their DDC were compared through hot ductility testing. As some filler materials had low crack susceptibilities, we applied these filler materials to an Alloy 690 and stainless steel dissimilar pipe joint, which would be applied to the safe-end joint of a PWR reactor vessel. Proper welding conditions for all-position welding were selected from the viewpoints of weldability and process stability. Welding conditions can be organized using the power ratio equation, and the soundness of the practical joints and their properties were confirmed. (author)

Additional details

Publishing Information

Journal Title
IHI Giho
Journal Volume
52
Journal Issue
2
Journal Page Range
p. 66-71
ISSN
1882-3041

Optional Information

Notes
5 refs., 12 figs., 4 tabs.