Menu
Search
Filters
Close
Menu

Save 20% on select titles with code HIDDEN24 - Shop The Sale Now

01146 INITIAL EVALUATION OF THE EFFECT OF NEUTRON ABSORBERS ON THE CORROSION OF URANIUM-ALUMINUM ALLOYS

Picture for 01146 INITIAL EVALUATION OF THE EFFECT
Available for download
Product Number: 51300-01146-SG
ISBN: 01146 2001 CP
Author: D. W. Vinson, J. I. Mickalonis, and R. L. Sindelar
$0.00
$20.00
$20.00
Aluminum-based spent nuclear fuel from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Monitored Geologic Repository. The melt-dilute treatment technology has been developed to consolidate fuel assemblies by a melting/casting process in which depleted uranium is added to reduce enrichment below 20% 235U. The melt-dilute product is essentially a binary uranium-aluminum alloy to which neutron absorber materials may be readily added. Demonstration of the compatibility and effectiveness of neutron-absorbing additions to the uranium-aluminum alloy, relative to criticality control, has been performed. The corrosion of uranium-aluminum alloys including neutron absorbers is being investigated in accordance with ASTM C1431-99. Testing includes vapor, static, single-pass flow, and electrochemical tests on surrogates of the melt-dilute treatment product. Exposure of uranium-aluminum alloys, including absorbers, to water vapor shows low post-passivation corrosion rates, similar to that of aluminum. The corrosion degradation sequences in the aqueous and vapor testing are assessed. Keywords: uranium-aluminum alloys, vapor corrosion, repository, spent nuclear fuel
Aluminum-based spent nuclear fuel from foreign and domestic research reactors is being consolidated at the Savannah River Site (SRS) for ultimate disposal in the Monitored Geologic Repository. The melt-dilute treatment technology has been developed to consolidate fuel assemblies by a melting/casting process in which depleted uranium is added to reduce enrichment below 20% 235U. The melt-dilute product is essentially a binary uranium-aluminum alloy to which neutron absorber materials may be readily added. Demonstration of the compatibility and effectiveness of neutron-absorbing additions to the uranium-aluminum alloy, relative to criticality control, has been performed. The corrosion of uranium-aluminum alloys including neutron absorbers is being investigated in accordance with ASTM C1431-99. Testing includes vapor, static, single-pass flow, and electrochemical tests on surrogates of the melt-dilute treatment product. Exposure of uranium-aluminum alloys, including absorbers, to water vapor shows low post-passivation corrosion rates, similar to that of aluminum. The corrosion degradation sequences in the aqueous and vapor testing are assessed. Keywords: uranium-aluminum alloys, vapor corrosion, repository, spent nuclear fuel
PRICE BREAKS - The more you buy, the more you save
Quantity
1+
5+
Price
$20.00
$20.00
Product tags
Also Purchased
Picture for 01142 Effect of Various Impurities on the
Available for download

01142 Effect of Various Impurities on the Transpassive Corrosion of High Purity Fe-18Cr-14Ni Alloys

Product Number: 51300-01142-SG
ISBN: 01142 2001 CP
Author: M.Mayuzumi, J.Ohta, K.Kako, and E.Kawakami
$20.00
Picture for 01154 CHROMIUM DEPLETION IN HIGH TEMPERATURE
Available for download

01154 CHROMIUM DEPLETION IN HIGH TEMPERATURE ALLOYS DURING ELEVATED TEMPERATURE EXPOSURE

Product Number: 51300-01154-SG
ISBN: 01154 2001 CP
Author: Mark A. Harper and Larry R. Walker
$20.00
Picture for 01141 CREVICE CORROSION STABILIZATION AND
Available for download

01141 CREVICE CORROSION STABILIZATION AND REPASSIVATION BEHAVIOR OF ALLOYS 625 AND 22

Product Number: 51300-01141-SG
ISBN: 01141 2001 CP
Author: B. A. Kehler, G.O. Ilevbare and J.R. Scully
$20.00
Categories
Industry
Recently viewed
Popular tags
View all

Association for Materials Protection and Performance

© AMPP All Rights Reserved.
Membership Terms of Content Use
Contact Customer Support