WIPP/SRL in-situ tests: MIIT program--The effects of metal package components

Conference · Tue Dec 31 04:00:00 EST 1991

OSTI ID:10131094

Covington, J A ^[1]; Wicks, G G ^[2]; Molecke, M A ^[3]

---

1. Clemson Univ., SC (United States)
2. Westinghouse Savannah River Co., Aiken, SC (United States)
3. Sandia National Labs., Albuquerque, NM (United States)

The Materials Interface Interactions Tests or MIIT is the largest in-situ testing program in progress, involving burial of many simulated nuclear waste systems and accompanying package components. In MIIT, waste glass samples were fabricated into the shape of `pineapple slices`, polished on one side. Proposed package components were also made into a similar configuration and the various glasses, metals, and geologic samples were than stacked onto heater elements within Teflon assemblies. This produced interactions of interest by creating glass/glass, glass/salt, and glass/metal interfaces. Since the outer diameter of the metal was smaller than the outer diameter of the glass, a lip was created which was also produced a glass/liquid interface, which was also studied. Overall, a total of 50 stacks or assemblies of pineapple slices were created in seven different stacking arrangements. Each individual assembly was then installed in an instrumented borehole at WIPP. Brine was then added to most of boreholes and the assemblies heated and maintained at 90{degrees}C. This was achieved by energizing the central heating and rod that traversed through the middle opening of each of the pineapple slices in each assembly. Due to the design of these units, glass, metal and geologic samples could be removed at time intervals of 6 mos., 1 year, 2 years, and 5 years. Currently, all but the 5 year samples have been removed from test and are being evaluated in laboratories of MIIT participants.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10131094
• Report Number(s): WSRC-MS--91-074; CONF-9104256--9; ON: DE92009752
• Country of Publication: United States
• Language: English

Related Subjects

052002
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
FOURIER TRANSFORM SPECTROMETERS
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
INFRARED SPECTRA
LEACHING
MASS SPECTROSCOPY
METALS
OPTICAL MICROSCOPY
PERFORMANCE TESTING
SCANNING ELECTRON MICROSCOPY
WASTE DISPOSAL AND STORAGE
WASTE FORMS
WIPP
X-RAY DIFFRACTION