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RRFM 2009 Transactions - European Nuclear Society

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CHARACTERIZATION OF THE MICROSTRUCTURE OF IRRADIATED<br />

U-MO DISPERSION FUEL WITH A MATRIX THAT CONTAINS SI<br />

D. D. KEISER, JR., A. B. ROBINSON, J. F. JUE, P. MEDVEDEV, AND M. R. FINLAY 1<br />

<strong>Nuclear</strong> Fuels and Materials Division, Idaho National Laboratory<br />

P. O. Box 1625, Idaho Falls, Idaho 83403 USA<br />

1 Austalian <strong>Nuclear</strong> Science and Technology Organization<br />

PMB 1, Menai, NSW, 2234,<br />

Australia<br />

ABSTRACT<br />

RERTR U-Mo dispersion fuel plates are being developed for application in research reactors throughout<br />

the world. Of particular interest is the irradiation performance of U-Mo dispersion fuels with Si added to<br />

the Al matrix. Si is added to improve the performance of U-Mo dispersion fuels. Microstructural<br />

examinations have been performed on fuel plates with Al-2Si matrix after irradiation to around 50% LEU<br />

burnup. Si-rich layers were observed in many areas around the various U-7Mo fuel particles. In one local<br />

area of one of the samples, where the Si-rich layer had developed into a layer devoid of Si, relatively<br />

large fission gas bubbles were observed in the interaction phase. There may be a connection between<br />

the growth of these bubbles and the amount of Si present in the interaction layer. Overall, it was found<br />

that having Si-rich layers around the fuel particles after fuel plate fabrication positively impacted the<br />

overall performance of the fuel plate.<br />

1. Introduction<br />

The United States Reduced Enrichment for Research and Test Reactors (RERTR) Fuel<br />

development program is actively developing low enriched uranium (LEU) fuels for the world’s<br />

research reactors that are currently fueled by uranium enriched to more than 20% 235 U [1].<br />

To assess the performance of U-Mo dispersion fuels with Si-doped matrices, different reactor<br />

experiments have been conducted using the Advanced Test Reactor (ATR). For the purpose of<br />

conducting scanning electron microscopy examinations on irradiated samples, the RERTR-6<br />

experiment has been of particular interest since the experiment was extracted from ATR over<br />

three years ago, and as a result, small samples can be handled in the Electron Microscopy<br />

Laboratory (EML). This paper will discuss results of recent microstructural characterization<br />

using a scanning electron microscope (SEM) that was performed on a fuel plate with Al-2Si<br />

matrix, irradiated as part of the RERTR-6 experiment. Optical metallography (OM) data will also<br />

be included. Focus will be given to the partitioning behavior of Si amongst the microstructural<br />

phases and how the presence of Si affects the development of interaction layers at the U-<br />

7Mo/matrix interface. Comparisons are made to the other irradiation experiments that have<br />

been reported for fuel plates with U-7Mo fuel dispersed in Al-2Si matrix.<br />

2. Experimental<br />

2.1 Irradiation Testing<br />

The RERTR-6 experiment was the first experiment to test “second generation” U-Mo fuels<br />

designed to overcome the fuel performance problems encountered in U-Mo/Al dispersions [2].<br />

In this experiment, the fuel materials were tested to high burn-up under moderate flux and<br />

moderate temperature conditions. The fuel plates were positioned edge-on to the core, and as a<br />

result had a neutron flux across the widths of the fuel plates.<br />

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