Published 1987 | Version v1
Journal article

Unirradiated characteristics of U-Si alloys as dispersed-phase fuels

  • 1. Argonne National Lab., IL (USA)

Description

To satisfy the power demands of many research reactors, a new low-enriched uranium fuel with a high density and uranium content was needed. Any fuel must be compatible with aluminum and its alloys so that it may be fabricated as a dispersed-phase in aluminum alloy and aluminum matrix plate-type elements following, as nearly as possible, established commercial manufacturing techniques. The U-Si and U-Si-Al alloys at or near the composition of U3Si were immediately attractive because of work documented by Canadian researchers. The paper illustrates the U-Si system. All intermediate phases, within the experimental ability to define them, are line compounds. For the goals of the Reduced Enrichment Research and Test Reactor Program, attention has focused on U3Si (3.9 wt% Si) and U3Si2 (7.3 wt% Si) and compositions between these limits. Densities and hardness for as-arc-cast and heat-treated ingots in this composition range are shown. Photomicrographs corresponding to these compositions and conditions have been published. Because of its higher uranium content and density, U3Si was the more attractive candidate fuel even though a prolonged heat treatment is required to complete the peritectoid reaction. The U3Si2 has a tightly bonded tetragonal structure with Si-Si bonds, whereas U3Si has a less tightly bonded crystal (cubic above 7650C, tetragonal below) with no Si-Si bonds. As others have noted, U3Si2 has performed better than U3Si in an irradiation environment

Additional details

Publishing Information

Journal Title
Trans. Am. Nucl. Soc.
Journal Volume
55
Series
Trans. Am. Nucl. Soc.
Journal Page Range
282-283
ISSN
0003-018X
CODEN
TANSA

Conference

Title
American Nuclear Society winter meeting.
Dates
15-19 Nov 1987.
Place
Los Angeles, CA (USA).

Optional Information

Secondary number(s)
CONF-8711195--.