Preliminary model of repository chemistry for the Waste Isolation Pilot Plant

Conference · Sun Dec 31 23:00:00 EST 1989

OSTI ID:6650167

Brush, L H ^[1]; Gbric-Galic, D ^[2]; Reed, D T ^[3]; Tong, X ^[4]; Vreeland, R H ^[5]; Westerman, R E ^[6]

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1. Sandia National Labs., Albuquerque, NM (USA)
2. Stanford Univ., CA (USA). Dept. of Civil Engineering
3. Argonne National Lab., IL (USA)
4. Wahler (W.A.) and Associates, Palo Alto, CA (USA)
5. West Chester Univ., PA (USA). Dept. of Biology
6. Pacific Northwest Lab., Richland, WA (USA)

The design-basis, defense-related, transuranic (TRU) waste to be emplaced in the Waste Isolation Pilot Plant (WIPP) could, if sufficient H{sub 2}O and nutrients were present, produce as much as 1,500 moles of gas per drum of waste. Gas production could pressurize the repository to 150 atm (lithostatic pressure) and perhaps higher. Anoxic corrosion of Fe and Fe-base alloys and microbial degradation of cellulosics are the processes of greatest concern, but radiolysis of brine could also be important. The proposed backfill additives CaCO{sub 3}, CaO, CuSO{sub 4}, KOH, and NaOH may remove or prevent the production of some of the expected gases. Because of the heterogeneous nature of design-basis waste, the Eh and pH of any brine present in WIPP disposal rooms could vary significantly over short distances after reacting with the waste. The WIPP Project is investigating the consequences of gas production and considering engineered alternatives, including reprocessing the waste, to reduce gas production rates or potentials. Reprocessing would also reduce the range of Eh and pH expected for the repository. 12 refs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC04-76DP00789
• OSTI ID: 6650167
• Report Number(s): SAND-90-1031C; CONF-901105--5; ON: DE90016219
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALKALI METAL COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
ALPHA-BEARING WASTES
BIODEGRADATION
BRINES
CALCIUM CARBONATES
CALCIUM COMPOUNDS
CALCIUM OXIDES
CARBOHYDRATES
CARBON COMPOUNDS
CARBONATES
CELLULOSE
CHALCOGENIDES
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CONTAINERS
COPPER COMPOUNDS
COPPER SULFATES
CORROSION
DECOMPOSITION
EQUATIONS
FUNCTIONAL MODELS
HYDROGEN COMPOUNDS
HYDROXIDES
IRON ALLOYS
MANAGEMENT
MATERIALS
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
ORGANIC COMPOUNDS
OXIDES
OXYGEN COMPOUNDS
PH VALUE
PILOT PLANTS
POLYSACCHARIDES
POTASSIUM COMPOUNDS
POTASSIUM HYDROXIDES
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE FACILITIES
RADIOACTIVE WASTE MANAGEMENT
RADIOACTIVE WASTES
RADIOLYSIS
REPROCESSING
SACCHARIDES
SEPARATION PROCESSES
SODIUM COMPOUNDS
SODIUM HYDROXIDES
SULFATES
SULFUR COMPOUNDS
TRANSITION ELEMENT COMPOUNDS
UNDERGROUND DISPOSAL
UNDERGROUND FACILITIES
US DOE
US ORGANIZATIONS
WASTE DISPOSAL
WASTE MANAGEMENT
WASTES
WIPP