Microstructural anomalies in hot-isostatic pressed U–10wt.% Mo fuel plates with Zr diffusion barrier

Journal Article · Fri May 01 00:00:00 EDT 2015 · Materials Characterization

DOI:https://doi.org/10.1016/j.matchar.2015.03.015· OSTI ID:1188616

Park, Y. ^[1]; Eriksson, N. ^[1]; Keiser, D. D. ^[2]; Jue, J. ^[2]; Rabin, B. ^[2]; Moore, G. ^[2]; Sohn, Y. H. ^[1]

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1. Univ. of Central Florida, Orlando, FL (United States). Advanced Materials Processing and Analysis Center (AMPAC)
2. Idaho National Lab. (INL), Idaho Falls, ID (United States)

Microstructural anomalies in the co-rolled-and-HIP'ed U–10 wt.% Mo (U10Mo) metallic fuel plate with Zr diffusion barrier assembly were examined as a function of HIP temperature (from 520 to 580 °C) and duration (45, 60, 90, 180 and 345 min) by scanning and transmission electron microscopy. The anomalies observed in this study are carbide/oxide inclusions within the U10Mo fuel alloy, and regions of limited interaction between the U10Mo alloy and Zr barrier, frequently associated with carbide/oxide inclusions. In the U10Mo alloy, the cF8, Fm3m (225) UC phase (a=4.955 Å) and cF12, Fm3m (225) UO₂ phase (a=5.467 Å) were observed throughout the U10Mo alloy with an approximate volume percent of 0.5 to 1.8. The volume percent of the UC–UO₂ inclusions within the U10Mo alloy did not change as functions of HIP temperature and time. These inclusion phases, located near the surface of the U10Mo alloy, were frequently observed to impede the development of interdiffusion and reaction between the U10Mo alloy and Zr diffusion barrier. The regions of limited interaction between the U10Mo and Zr barrier decreased with an increase in HIP temperature, however no noticeable trend was observed with an increase in HIP duration at constant temperature of 560 °C.

• Research Organization: Idaho National Lab. (INL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• DOE Contract Number: AC07-05ID14517
• OSTI ID: 1188616
• Report Number(s): INL/JOU-15-35647; TRN: US1500207
• Journal Information: Materials Characterization, Vol. 103, Issue C; ISSN 1044-5803
• Publisher: Elsevier
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
URANIUM DIOXIDE
FCC LATTICES
URANIUM CARBIDES
FUEL PLATES
MOLYBDENUM ALLOYS
URANIUM BASE ALLOYS
BINARY ALLOY SYSTEMS
INCLUSIONS
MICROSTRUCTURE
PRESSING
NUCLEAR FUELS
TEMPERATURE RANGE 0400-1000 K
TEMPERATURE DEPENDENCE
ZIRCONIUM
TIME DEPENDENCE
SCANNING ELECTRON MICROSCOPY
TRANSMISSION ELECTRON MICROSCOPY
COATINGS
URANIUM ALLOY