Details of in situ sample retrievals and test completion for the Materials Interface Interactions Test (MIIT)
- Sandia National Labs., Albuquerque, NM (United States)
- Westinghouse Savannah River Co., Aiken, SC (United States)
The Materials Interface Interaction Tests (MIIT) program involves the comparative, performance-evaluation testing of multiple US and foreign nuclear waste glasses (nonradioactive), potential canister and overpack metals, brine, and geologic materials in the rock salt repository environment at the Waste Isolation Pilot Plant (WIPP) facility. We emplaced about 2000 materials specimens onto 50 test assemblies and exposed them to a 90 [plus minus] 10[degree]C salt-brine environment. We successfully concluded the in situ conduct of the MIIT after five years and retrieved all samples for posttest laboratory analyses. These 5-year glass and metal samples, along with samples previously retrieved after 0.5, 1, and 2 years, are being analyzed in multiple international laboratories, in a cooperative testing effort. Our focus in this paper is to summarize technical details and repository-relevant observations on the in situ conduct, sampling, and termination operations of the MIIT. Such information should be useful for the interpretation of the laboratory-based analyses and also relevant for other organizations planning or conducting similar materials-related, in situ tests.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States); Westinghouse Savannah River Co., Aiken, SC (United States)
- Sponsoring Organization:
- DOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789; AC09-76SR00001
- OSTI ID:
- 6486096
- Report Number(s):
- SAND-92-2660C; CONF-930438--11; ON: DE93012350
- Country of Publication:
- United States
- Language:
- English
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Materials Interface Interactions Test (MIIT) details and observations on in situ sample retrievals and test termination
Materials Interface Interactions Test (MIIT) details and observations on in situ sample retrievals and test termination
Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360105 -- Metals & Alloys-- Corrosion & Erosion
360604 -- Materials-- Corrosion
Erosion
& Degradation
58 GEOSCIENCES
580000 -- Geosciences
ALLOYS
ALPHA-BEARING WASTES
BRINES
CARBON STEELS
CHEMICAL REACTIONS
CONTAINERS
CORROSION
CORROSIVE EFFECTS
DISSOLUTION
ELEMENTS
FUNCTIONAL MODELS
GEOLOGY
GLASS
HEATERS
HIGH ALLOY STEELS
HIGH-LEVEL RADIOACTIVE WASTES
INTERFACES
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
MATERIALS TESTING
METALS
MINERALOGY
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PERFORMANCE
PILOT PLANTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
SALTS
SAMPLING
SEPARATION PROCESSES
STAINLESS STEELS
STEELS
TESTING
UNDERGROUND DISPOSAL
UNDERGROUND FACILITIES
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WIPP