Diffusion studies of U-Zr alloys with Fe alloys at 650 C and 700 C - 5263
- 1. Radiochemistry Group, University of Nevada, Las Vegas, 4505 S Maryland Pkwy, Las Vegas, NV, USA 89154 (United States)
- 2. TerraPower, LLC, 330 120th Ave NE, Suite 100, Bellevue, WA, USA 98005 (United States)
Description
Diffusion studies of uranium-zirconium alloys with iron alloys are relevant in the developments of metallic nuclear fuels for fast neutron reactors. Metallic fuels have preferable qualities in reactors, such as the ability to reach higher burn-ups and be manufactured with available space to accommodate swelling from fission gases. Zirconium is commonly included in the fuel because it stabilizes the irradiation behavior of uranium and reduces fuel-clad interactions. It also has a small neutron capture cross-section. Earlier diffusion studies have reported the interactions of uranium and iron and uranium alloyed with zirconium and iron. In this work it is demonstrated that diffusion couples of both uranium and uranium-zirconium alloys with both iron and HT-9 stainless steel (12Cr-1MoVW) strongly interact, and both exhibit behaviors similar to uranium-iron diffusion. Additionally, there are new phases consistent with those found in the Fe-U-Zr ternary phase diagram, but chromium is not found in the interaction regions. Another key difference when uranium-zirconium is coupled with HT-9 is that the diffusion rates are much smaller. This result is interesting because it suggests an interaction between zirconium and chromium, despite a negligible rate of diffusion for chromium. Hence, diffusion experiments involving uranium and uranium-zirconium with chromium have also been performed and the results will be presented elsewhere. (authors)
Availability note (English)
Available (USB stick) from: SFEN, 103 rue Reaumur, 75002 Paris (France)Additional details
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire - SFEN
- Imprint Place
- Paris (France)
- ISBN
- 978-1-4951-6286-2
- Imprint Title
- GLOBAL 2015 Proceedings
- Imprint Pagination
- 2455 p.
- Journal Page Range
- p. 1342-1346
Conference
- Title
- Nuclear fuel cycle for a low-carbon future
- Acronym
- GLOBAL 2015
- Dates
- 21-24 Sep 2015
- Place
- Paris (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 49058563
- Subject category
- S36: MATERIALS SCIENCE;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY-HT-9; BENCH-SCALE EXPERIMENTS; DIFFUSION; IRON; IRON ALLOYS; MICROSTRUCTURE; TEMPERATURE DEPENDENCE; URANIUM; URANIUM ALLOYS; ZIRCONIUM ALLOYS
- Descriptors DEC
- ACTINIDE ALLOYS; ACTINIDES; ALLOYS; CARBON ADDITIONS; CHROMIUM ALLOYS; CHROMIUM STEELS; CORROSION RESISTANT ALLOYS; ELEMENTS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MARTENSITIC STEELS; MATERIALS; METALS; MOLYBDENUM ADDITIONS; MOLYBDENUM ALLOYS; STAINLESS STEELS; STEEL-CR12MOV; STEELS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENTS; VANADIUM ADDITIONS; VANADIUM ALLOYS
Optional Information
- Notes
- 7 refs.