Fabrication of fuel rods containing /sup 233/U pelletized oxide fuels (LWBR Development Program)

Technical Report · Wed Feb 01 04:00:00 EST 1967

DOI:https://doi.org/10.2172/6741692· OSTI ID:6741692

Frankhouser, W L; Crain, H H; Fischer, R L; Suldan, J H; Eyler, J H; Speer, E L

Approximately 13 kg of U-233 were fabricated into 1 wt % UO/sub 2/-ThO/sub 2/ and 26 wt % UO/sub 2/-ZrO/sub 2/ pellets and enclosed in Zircaloy-2 cladding tubes as 1299 blanket and 377 seed rods. The U-233 contained 38 ppM of U-232, and was purified as two batches of liquid UO/sub 2/(NO/sub 3/)/sub 2/ immediately prior to processing into powder form. All fuel rods were completed within 95 days of this initial solvent extraction of the nitrate. Overall U yield of nitrate to usable materials was over 90%, and only 14 rods were rejected in welding and all without loss of contained fuel. (NSA 21: 14872)

• Research Organization: Bettis Atomic Power Lab., Pittsburgh, PA (USA)
• DOE Contract Number: AT(11-1)-GEN-14
• OSTI ID: 6741692
• Report Number(s): WAPD-TM-588
• Country of Publication: United States
• Language: English

Related Subjects

050700 -- Nuclear Fuels-- Fuels Production & Properties
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
FABRICATION
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS