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Title: Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search

Abstract

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)

Publication Date:
Research Org.:
NERAC, Inc., Tolland, CT (United States)
OSTI Identifier:
449183
Report Number(s):
PB-97-855084/XAB
TRN: 70591137
Resource Type:
Technical Report
Resource Relation:
Other Information: DN: Updated with each order. Supersedes PB--96-863360; PBD: Jan 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; RADIOACTIVE WASTE PROCESSING; BIBLIOGRAPHIES; RADIOACTIVE WASTES; VITRIFICATION

Citation Formats

NONE. Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search. United States: N. p., 1997. Web.
NONE. Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search. United States.
NONE. Wed . "Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search". United States. doi:.
@article{osti_449183,
title = {Radioactive waste processing: Vitrification. (Latest citations from the NTIS bibliographic database). Published Search},
author = {NONE},
abstractNote = {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)},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Wed Jan 01 00:00:00 EST 1997},
month = {Wed Jan 01 00:00:00 EST 1997}
}

Technical Report:
Other availability
Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that may hold this item. Keep in mind that many technical reports are not cataloged in WorldCat.

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