Modeling Interfaces to Support Low-Level Waste Disposal System Performance Assessments - 20366
Conference
·
OSTI ID:23028000
- Vanderbilt University (United States)
- Nuclear Research and Consultancy Group, Petten (Netherlands)
- Hans van der Sloot Consultancy (Netherlands)
In low-level waste (LLW) disposal sites, interfaces between cementitious materials, used as waste forms and/or engineered barriers, and the surrounding soil or backfill material are often encountered. Reactions across these interfaces may lead to chemical and structural alteration of the cementitious and backfill materials that may ultimately affect long-term performance. For example, the ingress of carbon dioxide from soil gas into a waste tank concrete shell at the Hanford Site or Savannah River Site (SRS) or a low-level waste disposal vault at SRS leads to carbonation of cement hydration products (e.g. portlandite, calcium-silicate hydrate or C-S-H, and ettringite). The result of carbonation is a decrease in pH in the cement paste portion of the tank wall or vault concrete structure that could ultimately lead to de-passivation of the embedded structural steel and, eventually, to cracking. Cracking can lead to increased ingress of water into the structure, corresponding increased release of constituents of concern, and to subsequent increased transport of these constituents to the surrounding environment. The mobility of trace constituents (e.g., radionuclides of concern) in waste forms may increase in response to changes in pH, pore structure, and mineralogical gradients. Depletion of portlandite results in subsequent decalcification of C-S-H that leads to changes in the cement strength and may lead to structural failure. At the boundary between waste forms and concrete vaults, the migration of sulfate ions from the salt waste form (e.g., the saltstone waste form used for LLW disposal at the Savannah River Site in Saltstone Disposal Units, or SDUs) into the barrier or vault concrete has been predicted to result in expansive mineral phase formation (or 'sulfate attack'). Expansive mineral formation could result in cracking and potential loss of structural integrity in the vault concrete. In the performance assessment (PA) for the SRS SDUs, prediction of both the carbonation and sulfate attack fronts are critical to assessing the long-term performance of these LLW disposal vaults. A general purpose geochemical reactive transport model has been developed in LeachXS/ORCHESTRA to evaluate typical interfaces for LLW disposal environments, including SDUs at SRS. The model may be used to predict the long-term performance of interfaces between cementitious materials and saltstone or backfill materials with respect to primary phases by considering mass transport, cement chemistry, geochemical speciation, and multi-ionic diffusion over interfaces between different materials. The present study compares the performance and interactions between vault concrete and saltstone waste form for a representative SDU scenario. The materials were characterized using pH-dependence leaching test (EPA 1313) and semi-dynamic transport tests (EPA 1315) with test results used to parameterize the interface model. The development of a credible inter model provides an important basis for supporting future PAs where carbonation and sulfate attack are important aging and degradation mechanisms. (authors)
- Research Organization:
- WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
- OSTI ID:
- 23028000
- Report Number(s):
- INIS-US--21-WM-20366
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
CALCIUM SILICATES
CARBON DIOXIDE
CARBONATES
CEMENTS
CONCRETES
CRACKING
GEOCHEMISTRY
HYDRATION
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MINERALS
PH VALUE
PORE STRUCTURE
RADIOACTIVE WASTE DISPOSAL
RADIOISOTOPES
SAVANNAH RIVER PLANT
SOILS
SULFATES
US EPA
WASTE FORMS
CALCIUM SILICATES
CARBON DIOXIDE
CARBONATES
CEMENTS
CONCRETES
CRACKING
GEOCHEMISTRY
HYDRATION
LEACHING
LOW-LEVEL RADIOACTIVE WASTES
MINERALS
PH VALUE
PORE STRUCTURE
RADIOACTIVE WASTE DISPOSAL
RADIOISOTOPES
SAVANNAH RIVER PLANT
SOILS
SULFATES
US EPA
WASTE FORMS