Retrieval and analysis of simulated defense HLW (high-level waste) package experiments at the WIPP (Waste Isolation Pilot Plant)
In situ waste package performance experiments involving simulated (non-radioactive) defense high-level waste (DHLW) containers have been in progress since late 1984 at the Waste Isolation Pilot Plant (WIPP) facility. These experiments involve full-size, simulated DHLW containers of several metals and designs emplaced in the WIPP bedded rock salt. These test containers are surrounded by granular backfill (packing) materials, have in many cases been intentionally injected with brines, and are heavily instrumented. A majority of the test packages also contain nonradioactive DHLW borosilicate glass waste form, either within the container and/or outside of it. The primary purpose of these WIPP simulated DHLW experiments is to evaluate the in situ durability and performance of all waste package engineered barrier materials, and to perform package concept validation testing. Twelve of the test DHLW containers, emplaced in WIPP test Room B, have been in heated operation since 1985 and had a maximum surface temperature of about 190/degree/C. These containers were recently retrieved, after about 3 years of heated exposure, for detailed posttest laboratory analyses of: general corrosion and metallurgical degradation, waste form and backfill materials alterations, and other rock salt-brine-barrier materials near-field interactions with the ''repository'' geochemical environment. Test canisters and overpacks made of ASTM Grade-12 titanium showed essentially no visible degradation in either the base metal or welds; cast mild steel A216/WCA overpacks have suffered some uniform corrosion. 11 refs.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 6783876
- Report Number(s):
- SAND-88-1135C; CONF-881066-2; ON: DE89000440; TRN: 88-035535
- Resource Relation:
- Conference: 12. international symposium on the scientific basis for nuclear waste management, Berlin, F.R. Germany, 10 Oct 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
36 MATERIALS SCIENCE
ALPHA-BEARING WASTES
RETRIEVAL SYSTEMS
HIGH-LEVEL RADIOACTIVE WASTES
UNDERGROUND DISPOSAL
BOROSILICATE GLASS
BRINES
CORROSIVE EFFECTS
PACKAGING
RADIOACTIVE WASTE MANAGEMENT
SALT DEPOSITS
TITANIUM
WASTE RETRIEVAL
WIPP
ELEMENTS
FUNCTIONAL MODELS
GEOLOGIC DEPOSITS
GLASS
MANAGEMENT
MATERIALS
METALS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
PILOT PLANTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
TRANSITION ELEMENTS
UNDERGROUND FACILITIES
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
052002* - Nuclear Fuels- Waste Disposal & Storage
053000 - Nuclear Fuels- Environmental Aspects
360105 - Metals & Alloys- Corrosion & Erosion