An assessment of the validity of cerium oxide as a surrogate for plutonium oxide gallium removal studies

Technical Report · Mon Mar 01 04:00:00 EST 1999

DOI:https://doi.org/10.2172/329498· OSTI ID:329498

Kolman, D G; Park, Y; Stan, M; Hanrahan, Jr, R J; Butt, D P

Methods for purifying plutonium metal have long been established. These methods use acid solutions to dissolve and concentrate the metal. However, these methods can produce significant mixed waste, that is, waste containing both radioactive and chemical hazards. The volume of waste produced from the aqueous purification of thousands of weapons would be expensive to treat and dispose. Therefore, a dry method of purification is highly desirable. Recently, a dry gallium removal research program commenced. Based on initial calculations, it appeared that a particular form of gallium (gallium suboxide, Ga{sub 2}O) could be evaporated from plutonium oxide in the presence of a reducing agent, such as small amounts of hydrogen dry gas within an inert environment. Initial tests using ceria-based material (as a surrogate for PuO{sub 2}) showed that thermally-induced gallium removal (TIGR) from small samples (on the order of one gram) was indeed viable. Because of the expense and difficulty of optimizing TIGR from plutonium dioxide, TIGR optimization tests using ceria have continued. This document details the relationship between the ceria surrogate tests and those conducted using plutonia.

• Research Organization: Los Alamos National Lab., NM (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 329498
• Report Number(s): LA-UR--99-491; ON: DE99002046
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
CERIUM OXIDES
EVAPORATION
GALLIUM OXIDES
MATERIAL SUBSTITUTION
MIXED OXIDE FUELS
PERFORMANCE TESTING
PLUTONIUM OXIDES
REMOVAL
SEPARATION PROCESSES