Published 1982
| Version v1
Journal article
Vitrification of high-level liquid waste from light-water reactor fuel
- 1. Battelle, Pac Northwest Lab, Wash
Description
In the current Nuclear Waste Vitrification Project, sponsored by the Department of Energy, actual liquid waste from the processing of pressurized water reactor fuel was immobilized as a borosilicate glass product in an eight-inch diameter stainless-glass canister. The waste recovered from processing about one tonne of uranium fuel was converted to about 44 liters of glass product. This represents the total yearly waste volume for a city of about 15,000 people having all their electrical needs supplied by nuclear power. The actual vitrification process is described. 3 refs
Additional details
Publishing Information
- Journal Title
- Proc. Symp. Waste Manage.
- Journal Issue
- p. 296-314
- Series
- Proc. Symp. Waste Manage.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13684875
- Subject category
- S12: MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES;
- Descriptors DEI
- BWR TYPE REACTORS; HIGH-LEVEL RADIOACTIVE WASTES; LIQUID WASTES; PWR TYPE REACTORS; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; VITRIFICATION
- Descriptors DEC
- MANAGEMENT; RADIOACTIVE MATERIALS; RADIOACTIVE WASTES; REACTORS; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; WATER COOLED REACTORS; WATER MODERATED REACTORS