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 language | English |
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Place of Publication | United States |
DOIs | |
State | Published - 2020 |
Keywords
- 36 MATERIALS SCIENCE
- 22 GENERAL STUDIES OF NUCLEAR REACTORS