Chemical interaction and compatibility of uranium mononitride and alumina forming austenitic stainless steel
• Chemical compatibility between UN and AFA was investigated at 823, 1023, and 1373 K. • Little to no chemical interaction was observed between UN and preoxidized AFA. • AlN formation was observed along the interface between UN not containing UO 2 and as-cast AFA. • No AlN formation was observed between UN doped with small weight percents of UO 2 and as-cast AFA. Uranium mononitride (UN) and alumina forming austenitic (AFA) stainless steel are a potential fuel-cladding combination for the lead-cooled fast reactor (LFR). Chemical compatibility between UN and AFA steel needs to be verified before implementation in a nuclear reactor. Diffusion couple experiments at 823 K and 1023 K were conducted for nonirradiated UN samples in contact with as-cast (no thermally grown Al 2 O 3 ) and preoxidized (with thermally grown Al 2 O 3 ) AFA for 500 and 1000 hours in an inert environment. Preoxidized AFA exhibited little to no interaction with all UN samples tested at both 823 K and 1023 K, displaying the stability and capability of the Al 2 O 3 layer to prevent chemical interaction and inter-diffusion with UN. Chemical interaction occurs between UN and as-cast AFA. At 1023 K, an aluminum and nitrogen rich phase (likely AlN) formed along the interface of as-cast AFA and UN samples. At 823 K the AlN phase was not prominently observed due to the reduced diffusivity of aluminum through AFA. The aluminum and nitrogen-enriched phase was also observed in a high temperature pressure-assisted test sample of UN and as-cast AFA thermally treated at 1373 K. In UN samples doped with a low weight percent of UO 2 (< 3 wt%), AlN was not detected along the interface at either temperatures, and an Al 2 O 3 layer likely formed along the interface and prevented further chemical interaction between UN and as-cast AFA.
Authors
- Bruce A. Pint (ORCID: https://orcid.org/0000-0002-9165-3335)
- Dong Zhao (ORCID: https://orcid.org/0000-0001-9137-7257)
- Erofili Kardoulaki (ORCID: https://orcid.org/0000-0002-0982-5127)
- Jiheon Jun (ORCID: https://orcid.org/0000-0001-9500-5637)
- Andre Broussard (ORCID: https://orcid.org/0000-0002-9606-2585)
- Jie Lian (ORCID: https://orcid.org/0000-0002-9060-8831)
- Kevin Yan (ORCID: https://orcid.org/0009-0009-0989-8017)
Institutions
- Oak Ridge National Laboratory (US)
- Los Alamos National Laboratory (US)
- Rensselaer Polytechnic Institute (US)
Publication Details
- Journal
- Journal of Nuclear Materials
- Published
- 2025-03-11
- DOI
- https://doi.org/10.1016/j.jnucmat.2025.155748
- Citations
- 2
- Primary Topic
- Nuclear Materials and Properties
- Type
- article
- Field-Weighted Citation Impact
- 1.04
Funders
- Office of Nuclear Energy
- National Research Council Canada
- Nuclear Energy University Program