Published June 2016 | Version v1
Journal article

Orientation-Dependent Surface Faceting in UO2

  • 1. Argonne National Laboratory: 9700 S Cass Ave, Lemont, Illinois, 60439 (United States)
  • 2. Rensselaer Polytechnic Institute, 110 Eighth Street, Troy, New York, 12180 (United States)

Description

The surface behavior of UO2 plays an important role throughout the lifetime of this widely-used commercial nuclear fuel, from manufacturing to waste storage. UO2 surface properties affect fuel swelling behavior by determining the morphology, size and distribution of fission gas bubbles. Additionally, UO2 surface characteristics influence fracture behavior, which is controlled by the thermodynamics of fracture surfaces. Therefore, detailed understanding of the fundamental surface behavior will help advance prediction of the fuel performance of UO2. Due to significant anisotropy in surface tension, faceting features form after annealing in both UO2 and many other crystalline materials. Knowledge of the correlation between crystallographic orientation and surface faceting features will expand the fundamental knowledge of UO2 surface characteristics, leading to a better understanding of fission gas swelling and fracture mechanisms. Inherent characterization technique limited previous studies on the crystallographic orientation of UO2 surface facets to low Miller index surfaces in single crystal specimens. In this study, synchrotron Laue microdiffraction was utilized to examine the crystallographic orientation of grains on the coarse surface of a polycrystalline UO2 specimen. The results were then compared with the surface morphology, obtained from scanning electron microscopy (SEM), so that a general correlation between the surface faceting features and crystallographic orientation in UO2 can be established. Both the fundamental surface characteristics and the crystallographic orientation measurements obtained in this study help advance the experiment validation of MARMOT, a mesoscale multi-physics code that predicts the coevolution of microstructure and properties within reactor fuel during its lifetime in the reactor. The MARMOT code is an indispensable component of the MOOSE-BISON-MARMOT (MBM) code suite that has been developed by Idaho National Laboratory to enable next generation fuel performance modeling capability as a part of the Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program Fuels Product Line (FPL). In this study, the surface-faceting features of UO2 were found to be dominated by the triple-plane structure and its variants. With this knowledge, by measuring the directions of the <110> edges, the crystallographic orientation of a surface UO2 grain can be precisely deduced in most regions of the standard stereogram triangle (SST) of the surface normal. (authors)

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
114
Journal Issue
1
Journal Page Range
p. 1075-1076
ISSN
0003-018X

Conference

Title
Annual Meeting of the American Nuclear Society. Embedded topical meeting 'Nuclear fuels and structural material for the next generation nuclear reactors'
Dates
12-16 Jun 2016
Place
New Orleans, LA (United States)

Optional Information

Notes
8 refs.; Available from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 United States