Published 1997 | Version v1
Miscellaneous

The conceptual design of an omnivorous and release-minimizing vitrification facility for LILW from NPPS

  • 1. Nuclear Power Research Laboratory, Korea Electric Power Research Institute (Korea, Republic of)

Description

A vitrification facility was conceptually designed so that all Low- and Intermediate-Level Radioactive Waste (LILW) from a pressurized water reactor (PWR) could be converted into glassy/slag waste forms with the minimization of the entrainment of volatile nuclides. Generation trends, radiological characteristics and chemical composition for LILW from Korean NPPs were examined. In order to select the most promising melters suitable for the goals, several melters that were likely to be applied to LILW vitrification were compared with one another with respect to each waste stream. An off-gas treatment system and a waste feeding system are suggested to minimize the input of volatile chemicals and radionuclides into effluents, especially, considering chemicals generated when each waste is pyrolyzed in molten glass or a pyrolysis chamber

Part of:
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety

Additional details

Publishing Information

Imprint Title
Proceedings of fifth international topical meeting on nuclear thermal hydraulics, operations and safety
Imprint Pagination
1493 p.
Journal Page Range
p. BB1.1-BB1.6

Conference

Title
5. international topical meeting on nuclear thermal hydraulics, operations and safety
Dates
14-18 Apr 1997
Place
Beijing (China)

Optional Information