Report on FY 2020 Welding Parameters Optimization and the Fabrication of Qualified Alloy 709 Welds

Zhili Feng, Tao Dai, Doug Kyle, Yanli Wang, Yiyu Wang

Research output: Book/ReportCommissioned report

Abstract

Alloy 709 is an attractive candidate construction material for the Sodium Fast Reactor (SFR). As part of the Alloy 709 Intermediate Term Test Program, this work covers the development of the technical basis for weld fabrication and weld qualification of Alloy 709. The phase of research reported herein focused on the issue of weld solidification cracking recently experienced in both experimental heats and a commercial heat of Alloy 709 with relatively high phosphorous levels.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2020

Keywords

  • 36 MATERIALS SCIENCE
  • 22 GENERAL STUDIES OF NUCLEAR REACTORS

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