Evaluation of experimental factors that influence the application and discrimination capability of the Product Consistency Test

Technical Report · Mon Oct 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6017471· OSTI ID:6017471

Jantzen, C M

Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass will be fabricated in the Defense Waste Processing Facility (DWPF) where the glass will be poured into stainless steel canisters for eventual disposal in a geologic repository. In order to comply with the Waste Acceptance Preliminary Specifications (WAPS) the durability of the glass needs to be measured during production in order to demonstrate its long term stability and radionuclide release properties. A durability test, designated the Product Consistency Test (PCT), was developed for DWPF glass in order to meet the WAPS requirements. The response of the PCT procedure was based on extensive testing with glasses of widely differing compositions. The PCT was determined to be very reproducible, yield reliable results rapidly, and be easily performed in shielded cell facilities with radioactive samples. In the study attached, Battelle Pacific Northwest Laboratory independently verified the optimum PCT test parameters for glasses of very similar composition. During this study the following four parameters were investigated: the test duration, necessity for leachate filtration, necessity for sample washing, and the optimum ratio of the sample surface area to leachant volume. 6 refs., 17 tabs.

• Research Organization: Savannah River Site (SRS), Aiken, SC (United States)
• Sponsoring Organization: USDOE; USDOE, Washington, DC (USA)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6017471
• Report Number(s): WSRC-TR-90-526-Rev.1; ON: DE91009291
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
BOROSILICATE GLASS
PERFORMANCE TESTING
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
LEACHATES
FILTRATION
PH VALUE
RADIOACTIVE EFFLUENTS
RADIOACTIVE WASTE FACILITIES
SAVANNAH RIVER PLANT
STABILITY
SURFACE AREA
VOLUME
WASHING
WASTE FORMS
CLEANING
DISPERSIONS
GLASS
MATERIALS
MIXTURES
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
SEPARATION PROCESSES
SOLUTIONS
SURFACE PROPERTIES
TESTING
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WASTES
052001* - Nuclear Fuels- Waste Processing