Saltcake dissolution FY 1998 status report

Technical Report · Tue May 18 00:00:00 EDT 1999

DOI:https://doi.org/10.2172/782279· OSTI ID:782279

HERTING, D L

A laboratory scouting study was completed on the dissolution characteristics of Hanford waste from three single-shell waste tanks: 241-BY-102, 241-BY-106, and 241-B-106. Gross dissolution behavior (percent undissolved solids as a function of dilution) is explained in terms of characteristics of individual salts in the waste. The percentage of the sodium inventory retrievable from the tanks by dissolving saltcake at reasonable dilution levels is estimated at 86% of the total sodium for tank BY-102, 98% for BY-106, and 79% for B-106.

• Research Organization: Hanford Site (HNF), Richland, WA (United States)
• Sponsoring Organization: US DOE Office of Environmental Management (US)
• DOE Contract Number: AC06-96RL13200
• OSTI ID: 782279
• Report Number(s): HNF-3437-REV0; TRN: US0203100
• Resource Relation: Other Information: PBD: 18 May 1999
• Country of Publication: United States
• Language: English

Related Subjects

12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
DILUTION
DISSOLUTION
SODIUM COMPOUNDS
STORAGE FACILITIES
RADIOACTIVE WASTE STORAGE
HANFORD RESERVATION
RADIOACTIVE WASTES
WASTE RETRIEVAL