Published 1995 | Version v1
Report Restricted

Performance of high plutonium-containing glasses for the immobilization of surplus fissile materials

Description

Plutonium from dismantled weapons is being evaluated for geological disposal. While a final waste form has not been chosen, borosilicate glass will be one of the waste forms to be evaluated. The reactivity of the reference blend glass containing the standard amount of Pu (∼0.01 wt %) to be produced by the Defense Waste Processing Facility (DWPF) is compared to that of glasses made from the same nominal frit composition but doped with 2 and 7 wt % Pu, and also equal mole percentages of Gd2O3. The Gd is added to act as a neutron poison to address criticality concerns. The four different glasses have been reacted using the PCT-B method with a SA/V of 20,000 m-1 and the Argonne Vapor Hydration Test (VHT) method. Both test methods accelerate the reaction of the glass. PCT-B is used to determine the reactivity of the glass by analyzing the solution and reacted test components, while the VHT is used to evaluate the long-term reactivity of the glass and the distribution of Pu to secondary phases that will control the long-term reaction of the glass. The results of the tests with high levels of Pu are compared to those with the nominal levels to be produced in the standard DWPF glass

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE95013773; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
ANL--CMT/CP-84590

Conference

Title
97. annual meeting of the American Ceramic Society.
Dates
30 Apr - 1 May 1995.
Place
Cincinnati, OH (United States).

INIS

Optional Information

Contract/Grant/Project number
Contract W-31-109-ENG-38
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-950401--16.