Published 1992 | Version v1
Report Restricted

Mechanisms of contaminant migration from grouted waste

  • 1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
  • 2. Westinghouse Savannah River Co., Aiken, SC (United States)

Description

Low-level radioactive decontaminated salt solution is generated at the Savannah River Site (SRS) from the In-Tank Precipitation process. The solution is mixed with cement, slag, and fly ash, to form a grout, termed ''Saltstone'', that will be disposed in concrete vaults at the Saltstone Disposal Facility (SDF) [1]. Of the contaminants in the Saltstone, the greatest concern to SRS is the potential release of nitrate to the groundwater because of the high initial nitrate concentration (0.25 g/cm3) in the Saltstone and the low Safe Drinking Water Act (SDWA) maximum contaminant level (MCL) of 44 mg/L. The SDF is designed to allow a slow, controlled release over thousands of years. This paper addresses a modeling study of nitrate migration from intact non-degraded concrete vaults in the unsaturated zone for the Radiological Performance Assessment (PA) of the SRS Saltstone Disposal Facility [3]. The PA addresses the performance requirements mandated by DOE Order 5820.2A [4]

Availability note (English)

MF available from INIS under the Report Number; OSTI as DE93005192; NTIS; INIS; US Govt. Printing Office Dep.

Files

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Additional details

Publishing Information

Imprint Pagination
11 p.
Report number
EGG-M--92605

Conference

Title
14. low-level radioactive waste management conference.
Dates
18-20 Nov 1992.
Place
Phoenix, AZ (United States).

Optional Information

Contract/Grant/Project number
Contract AC07-76ID01570; AC09-89SR18035
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-921137--11.