The development of lower enrichment fuels for Canadian research reactors
- 1. AECL, Atomic Energy of Canada Limited, Chalk River, ON (Canada)
- 2. CRNL, Combustion Engineering Superheater Ltd., Moncton, NB (Canada)
Description
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-U3O8 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)
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Additional details
Publishing Information
- Imprint Title
- Proceedings of the international meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR). Base technology
- Imprint Pagination
- 671 p.
- Journal Page Range
- p. 223-247
- Report number
- ANL/RERTR/TM--3
Conference
- Title
- International meeting on development, fabrication, and application of Reduced Enrichment fuels for Research and Test Reactors (RERTR)
- Dates
- 12-14 Nov 1980
- Place
- Argonne, IL (United States)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 36023726
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALUMINIUM ALLOYS; CORROSION; MATRIX MATERIALS; NRU REACTOR; NRX REACTOR; OXIDATION; TEMPERATURE DEPENDENCE; URANIUM OXIDES U3O8; URANIUM SILICIDES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CHALCOGENIDES; CHEMICAL REACTIONS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; MATERIALS; MATERIALS TESTING REACTORS; NATURAL URANIUM REACTORS; OXIDES; OXYGEN COMPOUNDS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SILICIDES; SILICON COMPOUNDS; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 9 refs, 12 figs, 3 tabs
- Secondary number(s)
- CONF--801144; INIS-XA-C--021