Test Summary Report INEEL Sodium-Bearing Waste Vitrification Demonstration RSM-01-1

Goles, Ronald W ; Perez Jr, Joseph M ; Macisaac, Brett D

Pacific Northwest National Laboratory (U.S.)

关键词: Waste Forms;    Radioactive Waste Processing;    Idaho National Engineering Laboratory;    Sodium Compounds;    Design;   

DOI  :  10.2172/787349
RP-ID  :  PNNL-13522
RP-ID  :  AC06-76RLO1830
RP-ID  :  787349

美国|英语

来源: UNT Digital Library

【 摘 要 】

The U.S. Department of Energy's Idaho National Engineering and Environmental Laboratory is storing large amounts of radioactive and mixed wastes. Most of the sodium-bearing wastes have been calcined, but about a million gallons remain uncalcined, and this waste does not meet current regulatory requirements for long-term storage and/or disposal. As a part of the Settlement Agreement between DOE and the State of Idaho, the tanks currently containing SBW are to be taken out of service by December 31, 2012, which requires removing and treatment the remaining SBW. Vitrification is the option for waste disposal that received the highest weighted score against the criteria used. Beginning in FY 2000, the INEEL high-level waste program embarked on a program for technology demonstration and development that would lead to conceptual design of a vitrification facility in the event that vitrification is the preferred alternative for SBW disposal. The Pacific Northwest National Laboratory's Research-Scale Melter was used to conduct these initial melter-flowsheet evaluations. Efforts are underway to reduce the volume of waste vitrified, and during the current test, an overall SBW waste volume-reduction factor of 7.6 was achieved.