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Summary of radioactive operations for Zeolite Vitrification Demonstration Program [electronic resource].

Published
Richland, Wash. : Pacific Northwest Laboratory, 1984.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description
Pages: 36 : digital, PDF file
Additional Creators
Pacific Northwest Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The Zeolite Vitrification Demonstration Program (ZVDP) has successfully vitrified the zeolite used in the Submerged Demineralizer System (SDS) at Three Mile Island (TMI) Unit 2 to a borosilicate glass product. Under the ZVDP, the US Department of Energy authorized the Pacific Northwest Laboratory (PNL) to demonstrate the vitrification process on a full scale by use of the in-can melter process. This program was accomplished in two phases. The first phase developed a glass formulation and demonstrated the vitrification process with nonradioactive materials. The second phase received three radioactive liners from the SDS and vitrified the zeolite contained in each. These studies concluded that emission of melter-generated aerosols is responsible for most radioactive, process-related losses to the off-gas system. Tritium, in the form of water vapor, is the only significant gaseous radioactive effluent generated by the vitrification of TMI zeolite waste.
Report Numbers
E 1.99:gend-038
gend-038
Subject(s)
Other Subject(s)
Note
Published through SciTech Connect.
01/01/1984.
"gend-038"
"DE84006260"
Goles, R.W.; Bryan, G.H.; Siemens, D.H.; Knox, C.A.
Funding Information
AC07-76ID01570
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