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In situ vitrification of the 116-B-6A crib: Large-scale demonstration results

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:6968058
; ;  [1]
  1. Battelle-Pacific Northwest Lab., Richland, WA (United States)
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A large-scale demonstration of the in situ vitrification (ISV) process was performed in April 1990 on the 116-B-6A crib in the 100 Area of the Hanford site in southeastern Washington. The 116-B-6A crib is a radioactive mixed-waste site and was selected to demonstrate the applicability of ISV to soils contaminated with mixed wastes common to many U.S. Department of Energy sites. The ISV is a thermal process that utilizes joule resistance heating to convert contaminated soil into a durable, leach-resistant, glass-and-crystalline product. The 116-B-6A crib test demonstrated the utility of the ISV process for a radioactive mixed-waste site containing a significant inventory of combustible timbers.
OSTI ID:
6968058
Report Number(s):
CONF-920606--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 65
Country of Publication:
United States
Language:
English

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Related Subjects

054000* -- Nuclear Fuels-- Health & Safety
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
BACKFILLING
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CESIUM 137
CESIUM ISOTOPES
CHROMIUM
CLEANING
CONTAMINATION
DECONTAMINATION
DISSOLUTION
ELEMENTS
EVEN-EVEN NUCLEI
FUEL ELEMENTS
GLASS
HANFORD RESERVATION
HAZARDOUS MATERIALS
IN-SITU PROCESSING
INTERMEDIATE MASS NUCLEI
ISOTOPES
LEACHING
LEAD
MATERIALS
MELTING
METALS
NATIONAL ORGANIZATIONS
NUCLEI
ODD-EVEN NUCLEI
PHASE TRANSFORMATIONS
PROCESSING
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTOR COMPONENTS
REMEDIAL ACTION
SEPARATION PROCESSES
SITE CHARACTERIZATION
SOILS
SPACERS
STRONTIUM 90
STRONTIUM ISOTOPES
TRANSITION ELEMENTS
US DOE
US ERDA
US ORGANIZATIONS
VITRIFICATION
WASTES
YEARS LIVING RADIOISOTOPES