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The development of lower enrichment fuels for Canadian research reactors

Abstract

As part of the world wide move to proliferation resistant fuels, new fuels which use reduced enrichment uranium are being developed for use in the NRX and NRU reactors. A fuel consisting of particles of a USiAl alloy dispersed in an Al matrix has been selected for development along with Al-37 wt% U alloy and Al-U{sub 3}O{sub 8} cermet as backup fuels. This report outlines the progress made in the development of the Al-USiAl and Al-37 wt% U. Results show that good quality extruded rods containing either fuel can be made with techniques similar to those used to fabricate the current NRX and NRU fuels. However, the new fuels will be more expensive to make. Although the oxidation behaviour of the Al-USiAl is not as good as that of the Al-U alloys, its corrosion behaviour in high temperature water does not seem much worse. The oxidation and aqueous corrosion of A-37 wt% U are not much different from those of the Al-U alloys currently used. (author)
Authors:
Feraday, M A; Belanger, L; Grolway, C M; [1]  Foo, M T [2] 
  1. AECL, Atomic Energy of Canada Limited, Chalk River, ON (Canada)
  2. CRNL, Combustion Engineering Superheater Ltd., Moncton, NB (Canada)
Publication Date:
Aug 01, 1983
Product Type:
Conference
Report Number:
ANL/RERTR/TM-3; CONF-801144; INIS-XA-C-021
Resource Relation:
Conference: International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR), Argonne, IL (United States), 12-14 Nov 1980; Other Information: 9 refs, 12 figs, 3 tabs; PBD: Aug 1983; Related Information: In: Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology, 671 pages.
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ALUMINIUM ALLOYS; CORROSION; MATRIX MATERIALS; NRU REACTOR; NRX REACTOR; OXIDATION; TEMPERATURE DEPENDENCE; URANIUM OXIDES U3O8; URANIUM SILICIDES
Sponsoring Organizations:
U.S. Department of Energy, Assistant Secretary for Nuclear Energy, Office of Spent Fuel Management and Reprocessing Systems (United States)
OSTI ID:
20571719
Research Organizations:
Argonne National Laboratory, Argonne, IL (United States)
Country of Origin:
IAEA
Language:
English
Other Identifying Numbers:
TRN: XA04C1553023726
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
page(s) 223-247
Announcement Date:

Citation Formats

Feraday, M A, Belanger, L, Grolway, C M, and Foo, M T. The development of lower enrichment fuels for Canadian research reactors. IAEA: N. p., 1983. Web.
Feraday, M A, Belanger, L, Grolway, C M, & Foo, M T. The development of lower enrichment fuels for Canadian research reactors. IAEA.
Feraday, M A, Belanger, L, Grolway, C M, and Foo, M T. 1983. "The development of lower enrichment fuels for Canadian research reactors." IAEA.
@misc{etde_20571719,
title = {The development of lower enrichment fuels for Canadian research reactors}
author = {Feraday, M A, Belanger, L, Grolway, C M, and Foo, M T}
abstractNote = {As part of the world wide move to proliferation resistant fuels, new fuels which use reduced enrichment uranium are being developed for use in the NRX and NRU reactors. A fuel consisting of particles of a USiAl alloy dispersed in an Al matrix has been selected for development along with Al-37 wt% U alloy and Al-U{sub 3}O{sub 8} cermet as backup fuels. This report outlines the progress made in the development of the Al-USiAl and Al-37 wt% U. Results show that good quality extruded rods containing either fuel can be made with techniques similar to those used to fabricate the current NRX and NRU fuels. However, the new fuels will be more expensive to make. Although the oxidation behaviour of the Al-USiAl is not as good as that of the Al-U alloys, its corrosion behaviour in high temperature water does not seem much worse. The oxidation and aqueous corrosion of A-37 wt% U are not much different from those of the Al-U alloys currently used. (author)}
place = {IAEA}
year = {1983}
month = {Aug}
}