Report on FY 2021 Fabrication and Testing of Qualified Alloy 709 Welds at ORNL

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

Research output: Book/ReportCommissioned report

Abstract

Alloy 709 is a candidate construction material for the Sodium Fast Reactor (SFR). As part of the Alloy 709 ASME Code Case development team under the Advanced Reactor Technologies (ART) Program, this work covers the development of the technical basis for weld fabrication and weld qualification of Alloy 709. This report summarizes the research conducted in FY 2021 and relevant results from previous reporting periods, aimed at welding commercial heat of Alloy 709 plates of relatively high phosphorous (P) level in support of ASME code case data package. Welding, code qualification tests, and associated microstructure characterization were carried out in determining the effect of P levels of weld wire on the weldability of the high P commercial heat of Alloy 709. The Alloy 709 weld creep strength was evaluated though preliminary creep testing.
Original languageEnglish
Place of PublicationUnited States
DOIs
StatePublished - 2021

Keywords

  • 36 MATERIALS SCIENCE
  • 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
  • 42 ENGINEERING

Fingerprint

Dive into the research topics of 'Report on FY 2021 Fabrication and Testing of Qualified Alloy 709 Welds at ORNL'. Together they form a unique fingerprint.

Cite this