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HERO ID
1776283
Reference Type
Technical Report
Title
Solidification of the Hanford Law Waste Stream Produced as a Result of Near-Tank Continuous Sludge Leaching and Sodium Hydroxide Recovery
Author(s)
Harbour, JR; Reigel, MM; Johnson, FC; Crawford, C; Jantzen, C
Year
2011
Report Number
NTIS/10310045
Volume
GRA and I
Issue
GRA and I
Abstract
The U.S. Department of Energy (DOE), Office of River Protection (ORP), is responsible for the remediation and stabilization of the Hanford Site tank farms, including 53 million gallons of highly radioactive mixed wasted waste contained in 177 underground tanks. The plan calls for all waste retrieved from the tanks to be transferred to the Waste Treatment Plant (WTP). The WTP will consist of three primary facilities including pretreatment facilities for Low Activity Waste (LAW) to remove aluminum, chromium and other solids and radioisotopes that are undesirable in the High Level Waste (HLW) stream. Removal of aluminum from HLW sludge can be accomplished through continuous sludge leaching of the aluminum from the HLW sludge as sodium aluminate; however, this process will introduce a significant amount of sodium hydroxide into the waste stream and consequently will increase the volume of waste to be dispositioned. A sodium recovery process is needed to remove the sodium hydroxide and recycle it back to the aluminum dissolution process. The resulting LAW waste stream has a high concentration of aluminum and sodium and will require alternative immobilization methods. Five waste forms were evaluated for immobilization of LAW at Hanford after the sodium recovery process. The waste forms considered for these two waste streams include low temperature processes (Saltstone/Cast stone and geopolymers), intermediate temperature processes (steam reforming and phosphate glasses) and high temperature processes (vitrification). These immobilization methods and the waste forms produced were evaluated for (1) compliance with the Performance Assessment (PA) requirements for disposal at the IDF, (2) waste form volume (waste loading), and (3) compatibility with the tank farms and systems.
Keywords
Radioactive waste processing
;
*Sodium hydroxides
;
*Sludges
;
*Leaching
;
Aluminates
;
Aluminium
;
Borosilicate glass
;
Chromium
;
Compatiblity
;
Compliance
;
Dissolution
;
Hydration
;
Iron phosphates
;
Radioactive waste disposal
;
Radioisotopes
;
Solidification
;
Stabilization
;
Streams
;
Storage facilities
;
Tanks
;
Vitrification
;
Waste forms
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