Daniel P. Abraham, Sean M. McDeavitt
Stainless steel-zirconium alloys are being developed for the disposal of radioactive metal isotopes isolated using an electrometallurgical treatment technique to treat spent nuclear fuel. The nominal waste forms are stainless steel-15 wt% zirconium alloy and zirconium-8 wt% stainless steel alloy. These alloys are generated in yttria crucibles by melting the starting materials at 1600°C under an argon atmosphere. This paper discusses the microstructures, corrosion and mechanical test results, and thermophysical properties of the metal waste form alloys.
@article{af176c23-49c5-43cc-a810-f290315e64af,
title={Metal waste forms from the electrometall},
author={Daniel P. Abraham and Sean M. McDeavitt},
year={2026},
language={en}
}TY - JOUR TI - Metal waste forms from the electrometall AU - Daniel P. Abraham AU - Sean M. McDeavitt PY - 2026 LA - en ER -
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