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100527e19890101dcu s| f1|||||eng|d |
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20230710144645.0 |
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|a (TOE)ost5788398
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|a (TOE)5788398
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|a TOE
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|a GDWR
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|a 12
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|a E 1.99: conf-891129--6
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|a E 1.99:wsrc-rp-89-493
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|a Product consistency leach tests of Savannah River Site radioactive waste glasses
|h [electronic resource]
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|a Washington, D.C. :
|b United States. Dept. of Defense ;
|a Oak Ridge, Tenn. :
|b distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy,
|c 1989.
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|a Pages: (22 p) :
|b digital, PDF file.
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|a text
|b txt
|2 rdacontent.
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|a computer
|b c
|2 rdamedia.
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|a online resource
|b cr
|2 rdacarrier.
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|a Published through the Information Bridge: DOE Scientific and Technical Information.
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|a 01/01/1989.
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|a "wsrc-rp-89-493"
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|a " conf-891129--6"
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|a "DE92009913"
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|a 13. symposium scientific basis for nuclear waste management, Boston, MA (United States), 27 Nov - 2 Dec 1989.
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|a Bates, J.K.; Bibler, N.E.
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|a The Product Consistency Test (PCT) is a glass leach test that was developed at the Savannah River Site (SRS) to routinely confirm the durability of nuclear waste glasses that will be produced in the Defense Waste Processing Facility. The PCT is a 7 day, crushed glass leach test in deionized water at 90°C. Final leachates are filtered and acidified prior to analysis. To demonstrate the reproducibility of the PCT when performed remotely, SRS and Argonne National Laboratory have performed the PCT on samples of two radioactive glasses. The tests were also performed to compare the releases of the radionuclides with the major nonradioactive glass components and to determine if radiation from the glass was affecting the results of the PCT. The test was performed in triplicate at each laboratory. For the major soluble elements, B, Li, Na, and Si, in the glass, each investigator obtained relative precisions in the range 2--5% in the triplicate tests. This range indicates good precision for the PCT when performed remotely with master slave manipulators in a shielded cell environment.
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|b AC09-89SR18035.
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|a Us Aec.
|2 local.
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|a Materials.
|2 local.
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|a Us Organizations.
|2 local.
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|a Chemical Composition.
|2 local.
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|a Us Doe.
|2 local.
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|a Savannah River Plant.
|2 local.
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|a Separation Processes.
|2 local.
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|a Borosilicate Glass.
|2 local.
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|a Vitrification.
|2 local.
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|a Radioactive Wastes.
|2 local.
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|a Wastes.
|2 local.
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|a National Organizations.
|2 local.
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|a High-level Radioactive Wastes.
|2 local.
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|a Radiation Effects.
|2 local.
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|a Leaching.
|2 local.
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|a Dissolution.
|2 local.
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|a Us Erda.
|2 local.
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|a Radioactive Materials.
|2 local.
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|a Glass.
|2 local.
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|a Management Of Radioactive And Non-radioactive Wastes From Nuclear Facilities.
|2 edbsc.
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|a Westinghouse Savannah River Company.
|4 res.
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|a United States.
|b Department of Defense.
|4 spn.
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1 |
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|a United States.
|b Department of Energy.
|4 spn.
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|a United States.
|b Department of Energy.
|b Savannah River Site.
|4 res.
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|a United States.
|b Department of Energy.
|b Office of Scientific and Technical Information.
|4 dst.
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|u http://www.osti.gov/servlets/purl/5788398-a3oXDo/
|z Online Access
|
907 |
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|a .b59995877
|b 03-06-23
|c 05-28-10
|
998 |
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|a web
|b 05-28-10
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|d m
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|f eng
|g dcu
|h 0
|i 1
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|p Can circulate
|a University of Colorado Boulder
|b Online
|c Online
|d Online
|e E 1.99: conf-891129--6
|h Superintendent of Documents classification
|i web
|n 1
|