WIPP/SRL in-situ testing program
Conference
·
OSTI ID:5557666
The first in situ tests of comparative nuclear waste glass performance in the US are scheduled to begin in early 1986. In these tests, multiple nonradioactive waste glass samples will be emplaced in brine and rock salt in an underground test facility under conditions closely simulating those in a salt repository. This program is a joint effort of the Waste Isolation Pilot Plant (WIPP) and the Savannah River Laboratory (SRL). Part of the WIPP/SRL program is the Materials Interface Interactions Tests or MIIT. This is an international effort which involves the burial of almost 1000 waste glass samples, consisting of 14 different glass or waste glass compositions from 7 countries. In addition to these samples, there are also over 300 potential canister or overpack metal specimens and over 500 backfill and salt geologic samples. Over 1900 relevant interactions will be studied by combining brine leachant analyses with a variety of detailed surface analytical techniques. This program is one of the largest cooperative efforts ever undertaken in the waste management field and will produce a data base that will benefit a variety of disciplines in the waste management community. 8 refs., 5 figs.
- Research Organization:
- Du Pont de Nemours (E.I.) and Co., Aiken, SC (USA). Savannah River Lab.; Sandia National Labs., Albuquerque, NM (USA)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 5557666
- Report Number(s):
- SAND-86-1038C; CONF-860418-4; ON: DE86010473
- Country of Publication:
- United States
- Language:
- English
Similar Records
WIPP/SRL in-situ and laboratory testing programs. Part I. MIIT overview, nonradioactive waste glass studies
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Technical Report
·
Thu Oct 31 23:00:00 EST 1985
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OSTI ID:6458541
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Conference
·
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Technical operations and data collection details of the in situ WIPP (Waste Isolation Pilot Plant) Materials Interface Interaction Test
Conference
·
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·
OSTI ID:6754870
Related Subjects
052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BOROSILICATE GLASS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION RESISTANT ALLOYS
DISSOLUTION
FUNCTIONAL MODELS
GEOLOGIC DEPOSITS
GLASS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH-LEVEL RADIOACTIVE WASTES
INTERFACES
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
NUCLEAR FACILITIES
PERFORMANCE TESTING
PILOT PLANTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
SALT DEPOSITS
SEPARATION PROCESSES
STAINLESS STEEL-304L
STAINLESS STEELS
STEELS
TESTING
TITANIUM ALLOYS
TITANIUM BASE ALLOYS
UNDERGROUND DISPOSAL
UNDERGROUND FACILITIES
US DOE
US ORGANIZATIONS
VITRIFICATION
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WIPP
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALLOYS
BOROSILICATE GLASS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CONTAINERS
CORROSION RESISTANT ALLOYS
DISSOLUTION
FUNCTIONAL MODELS
GEOLOGIC DEPOSITS
GLASS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH-LEVEL RADIOACTIVE WASTES
INTERFACES
IRON ALLOYS
IRON BASE ALLOYS
LEACHING
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
NUCLEAR FACILITIES
PERFORMANCE TESTING
PILOT PLANTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTES
SALT DEPOSITS
SEPARATION PROCESSES
STAINLESS STEEL-304L
STAINLESS STEELS
STEELS
TESTING
TITANIUM ALLOYS
TITANIUM BASE ALLOYS
UNDERGROUND DISPOSAL
UNDERGROUND FACILITIES
US DOE
US ORGANIZATIONS
VITRIFICATION
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WIPP