Fuel qualification plan for the Advanced Neutron Source Reactor
Author(s) -
G.L. Copeland
Publication year - 1995
Publication title -
osti oai (u.s. department of energy office of scientific and technical information)
Language(s) - English
Resource type - Reports
DOI - 10.2172/113994
Subject(s) - enriched uranium , uranium , nuclear engineering , nuclear reactor core , volume (thermodynamics) , fraction (chemistry) , uranium 235 , fabrication , isotopes of uranium , burnup , actinide , core (optical fiber) , radiochemistry , environmental science , neutron , process engineering , materials science , neutron temperature , engineering , nuclear physics , chemistry , nuclear chemistry , metallurgy , physics , composite material , organic chemistry , quantum mechanics , medicine , alternative medicine , pathology
This report describes the development and qualification plan for the fuel for the Advanced Neutron Source. The reference fuel is U{sub 3}Si{sub 2}, dispersed in aluminum and clad in 6061 aluminum. This report was prepared in May 1994, at which time the reference design was for a two-element core containing highly enriched uranium (93% {sup 235}U) . The reactor was in the process of being redesigned to accommodate lowered uranium enrichment and became a three-element core containing a higher volume fraction of uranium enriched to 50% {sup 235}U. Consequently, this report was not issued at that time and would have been revised to reflect the possibly different requirements of the lower-enrichment, higher-volume fraction fuel. Because the reactor is now being canceled, this unrevised report is being issued for archival purposes. The report describes the fabrication and inspection development plan, the irradiation tests and performance modeling to qualify performance, the transient testing that is part of the safety program, and the interactions and interfaces of the fuel development with other tasks
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