MIIT: International in-situ testing of nuclear-waste glasses: Performance of SRS simulated waste glass after five years of burial at the Waste Isolation Pilot Plant (WIPP)

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In July of 1986, the first in-situ test involving burial of simulated high-level waste (HLW) forms conducted in the United States was started. This program, called the Materials Interface Interactions Test or MIIT, comprises the largest, most cooperative field-testing venture in the international waste management community. In July of 1991, the experimental portion of the 5-year MIIT study was completed on schedule. During this time interval, many in-situ measurements were performed, thousands of brine analyses conducted, and hundreds of waste glass and package components exhumed and evaluated after 6 mo., 1 yr., 2 yr. and 5 yr. burial periods. Although ... continued below

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Pages: (10 p)

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Wicks, G.G. (Westinghouse Savannah River Co., Aiken, SC (United States)); Lodding, A.R. (Chalmers Univ. of Technology, Goeteborg (Sweden)); Macedo, P.B. (Catholic Univ. of America, Washington, DC (United States)) & Clark, D.E. (Florida Univ., Gainesville, FL (United States)) January 1, 1991.

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In July of 1986, the first in-situ test involving burial of simulated high-level waste (HLW) forms conducted in the United States was started. This program, called the Materials Interface Interactions Test or MIIT, comprises the largest, most cooperative field-testing venture in the international waste management community. In July of 1991, the experimental portion of the 5-year MIIT study was completed on schedule. During this time interval, many in-situ measurements were performed, thousands of brine analyses conducted, and hundreds of waste glass and package components exhumed and evaluated after 6 mo., 1 yr., 2 yr. and 5 yr. burial periods. Although analyses are still in progress, the performance of SRS waste glass based on all data currently available has been seen to be excellent thus far. Initial analyses and assessment of Savannah River (SR) waste glass after burial in WIPP at 90{degrees}C for 5 years are presented in this document.

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Pages: (10 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • 3. international conference on advances in fusion and processing of glass, New Orleans, LA (United States), 10-12 Jun 1992

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  • Other: DE92015928
  • Report No.: WSRC-MS-91-562
  • Report No.: CONF-9206194--3
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 5182710
  • Archival Resource Key: ark:/67531/metadc1060945

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  • January 1, 1991

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  • Jan. 22, 2018, 7:23 a.m.

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  • Feb. 1, 2018, 7:13 p.m.

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Wicks, G.G. (Westinghouse Savannah River Co., Aiken, SC (United States)); Lodding, A.R. (Chalmers Univ. of Technology, Goeteborg (Sweden)); Macedo, P.B. (Catholic Univ. of America, Washington, DC (United States)) & Clark, D.E. (Florida Univ., Gainesville, FL (United States)). MIIT: International in-situ testing of nuclear-waste glasses: Performance of SRS simulated waste glass after five years of burial at the Waste Isolation Pilot Plant (WIPP), article, January 1, 1991; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc1060945/: accessed December 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.