Operating experience during high-level waste vitrification at the West Valley Demonstration Project
This report provides a summary of operational experiences, component and system performance, and lessons learned associated with the operation of the Vitrification Facility (VF) at the West Valley Demonstration Project (WVDP). The VF was designed to convert stored high-level radioactive waste (HLW) into a stable waste form (borosilicate glass) suitable for disposal in a federal repository. Following successful completion on nonradioactive test, HLW processing began in July 1995. Completion of Phase 1 of HLW processing was reached on 10 June 1998 and represented the processing of 9.32 million curies of cesium-137 (Cs-137) and strontium-90 (Sr-90) to fill 211 canisters with over 436,000 kilograms of glass. With approximately 85% of the total estimated curie content removed from underground waste storage tanks during Phase 1, subsequent operations will focus on removal of tank heel wastes.
- Research Organization:
- West Valley Nuclear Services Co., Inc., West Valley, NY (US)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM) (US)
- DOE Contract Number:
- AC24-81NE44139
- OSTI ID:
- 754792
- Report Number(s):
- DOE/NE/44139-87; B-and-R-EX31-33000; R&D Project: OH 4001 WV (ADS Number); B&R EX31 33000; TRN: US0002988
- Resource Relation:
- Other Information: PBD: 1 Jan 1999
- Country of Publication:
- United States
- Language:
- English
Similar Records
High-Level Waste Tank Cleaning and Field Characterization at the West Valley Demonstration Project
Scaled Vitrification System III (SVS III) Process Development and Laboratory Tests at the West Valley Demonstration Project
Related Subjects
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE FACILITIES
HIGH-LEVEL RADIOACTIVE WASTES
VITRIFICATION
WASTE FORMS
RADIOACTIVE WASTE DISPOSAL
BOROSILICATE GLASS
STORAGE FACILITIES
WASTE RETRIEVAL
REMEDIAL ACTION