Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing

Collette, R.; King, J.; Buesch, C.; Keiser, Jr., D. D.; Williams, W.; Miller, B. D.; Schulthess, J.

doi:10.1016/j.jnucmat.2016.03.028

Analysis of irradiated U-7wt%Mo dispersion fuel microstructures using automated image processing

Journal Article · Fri Apr 01 00:00:00 EDT 2016 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2016.03.028· OSTI ID:1294498

Collette, R. ^[1]; ^[1]; Buesch, C. ^[2]; Keiser, Jr., D. D. ^[3]; Williams, W. ^[3]; Miller, B. D. ^[3]; Schulthess, J. ^[3]

Colorado School of Mines, Golden, CO (United States)
Oregon State Univ., Corvallis, OR (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

The High Performance Research Reactor Fuel Development (HPPRFD) program is responsible for developing low enriched uranium (LEU) fuel substitutes for high performance reactors fueled with highly enriched uranium (HEU) that have not yet been converted to LEU. The uranium-molybdenum (U-Mo) fuel system was selected for this effort. In this study, fission gas pore segmentation was performed on U-7wt%Mo dispersion fuel samples at three separate fission densities using an automated image processing interface developed in MATLAB. Pore size distributions were attained that showed both expected and unexpected fission gas behavior. In general, it proved challenging to identify any dominant trends when comparing fission bubble data across samples from different fuel plates due to varying compositions and fabrication techniques. Here, the results exhibited fair agreement with the fission density vs. porosity correlation developed by the Russian reactor conversion program.

Research Organization:: Idaho National Laboratory, Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: AC07-05ID14517

OSTI ID:: 1294498

Alternate ID(s):: OSTI ID: 1341165
OSTI ID: 22592614

Report Number(s):: INL/JOU--15-35414; PII: S0022311516301015

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 475; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
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automated image analysis
fission bubbles
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nuclear fuel
porosity

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