Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search
Technical Report
·
OSTI ID:449183
The bibliography contains citations concerning the processing of radioactive wastes by vitrification (the formation of a glassy material to immobilize radioactive nuclides). In-situ vitrification; proposed glass compositions; glass properties including degradation, leachability, and physical strength; and vitrification processes are discussed. Full-scale vitrification plants and international waste vitrification programs are described. Solidification of radioactive waste with borosilicate glass and synthetic rock or cement and asphalt is discussed in separate bibliographies. (Contains 50-250 citations and includes a subject term index and title list.) (Copyright NERAC, Inc. 1995)
- Research Organization:
- NERAC, Inc., Tolland, CT (United States)
- OSTI ID:
- 449183
- Report Number(s):
- PB-97-855084/XAB; TRN: 70591137
- Resource Relation:
- Other Information: DN: Updated with each order. Supersedes PB--96-863360; PBD: Jan 1997
- Country of Publication:
- United States
- Language:
- English
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