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Title: Integrated Disposal Facility Risk Assessment

Abstract

An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.

Authors:
Publication Date:
Research Org.:
CH2M (US)
Sponsoring Org.:
ENVIRONMENTAL MANAGEMENT (US)
OSTI Identifier:
812309
Report Number(s):
RPP-15834 Rev.0
EDT-622281; TRN: US0303339
DOE Contract Number:
AC27-99RL14047
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 3 Jun 2003
Country of Publication:
United States
Language:
English
Subject:
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; PERFORMANCE; RISK ASSESSMENT; SOLID WASTES; ENVIRONMENTAL IMPACTS; LOW-LEVEL RADIOACTIVE WASTES; RADIOACTIVE WASTE DISPOSAL; RADIOACTIVE WASTE FACILITIES; GROUND WATER; AIR POLLUTION; HUMAN INTRUSION

Citation Formats

MANN, F. M.. Integrated Disposal Facility Risk Assessment. United States: N. p., 2003. Web. doi:10.2172/812309.
MANN, F. M.. Integrated Disposal Facility Risk Assessment. United States. doi:10.2172/812309.
MANN, F. M.. Tue . "Integrated Disposal Facility Risk Assessment". United States. doi:10.2172/812309. https://www.osti.gov/servlets/purl/812309.
@article{osti_812309,
title = {Integrated Disposal Facility Risk Assessment},
author = {MANN, F. M.},
abstractNote = {An environmental risk assessment associated with the disposal of projected Immobilized Low-Activity Waste, solid wastes and failed or decommissioned melters in an Integrated Disposal Facility was performed. Based on the analyses all performance objectives associated with the groundwater, air, and intruder pathways were met.},
doi = {10.2172/812309},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Tue Jun 03 00:00:00 EDT 2003},
month = {Tue Jun 03 00:00:00 EDT 2003}
}

Technical Report:

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  • Laboratory testing was conducted on bulk vitrified and steam reformed waste forms to supply the input parameters needed for reactive chemical transport calculations with the Subsurface Transport Over Reactive Multiphases (STORM) code. This same code was used to conduct the 2001 ILAW performance assessment. The required input parameters for both waste forms are derived from a mechanistic model that describes the effect of solution chemistry on contaminant release rates. The single-pass flow-through test was the principal method used to obtain these input parameters, supplemented by product consistency test measurements and physical property measurements.
  • To Erik Olds 09/30/03 - An annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a full performance assessment is not issued.
  • As required by the US. Department of Energy (DOE) order on radioactive waste management (DOE 1999a) and as implemented by the ''Maintenance Plan for the Hanford Immobilized Low-Activity Tank Waste Performance Assessment'' (Mann 2004), an annual summary of the adequacy of the Hanford Immobilized Low-Activity Tank Waste Performance Assessment (ILAW PA) is necessary in each year in which a performance assessment is not issued. A draft version of the 2001 ILAW PA was sent to the DOE Headquarters (DOE/HQ) in April 2001 for review and approval. The DOE approved (DOE 2001) the draft version of the 2001 ILAW PA andmore » issued a new version of the Hanford Site waste disposal authorization statement (DAS). Based on comments raised during the review, the draft version was revised and the 2001 ILAW PA was formally issued (Mann et al. 2001). The DOE (DOE 2003a) has reviewed the final 2001 ILAW PA and concluded that no changes to the DAS were necessary. Also as required by the DOE order, annual summaries have been generated and approved. The previous annual summary (Mann 2003b) noted the change of mission from ILAW disposal to the disposal of a range of solid waste types, including ILAW. DOE approved the annual summary (DOE 2003c), noting the expanded mission. Considering the results of data collection and analysis, the conclusions of the 2001 ILAW PA remain valid as they pertain to ILAW disposal. The new data also suggest that impacts from the disposal of the other solid waste will be lower than initially estimated in the ''Integrated Disposal Facility Risk Assessment'' (Mann 2003a). A performance assessment for the Integrated Disposal Facility (IDF) will be issued in the summer of 2005.« less
  • A set of reactive chemical transport calculations was conducted with the Subsurface Transport Over Reactive Multiphases (STORM) code to evaluate the long-term performance of a representative low-activity waste glass in a shallow subsurface disposal system located on the Hanford Site. Two-dimensional simulations were run until the waste form release rates reached a quasi-stationary-state, usually after 2,000 to 4,000 yr. The primary difference between the waste form release simulations for the 2001 ILAW PA, and the simulations described herein, is the number of different materials considered. Whereas the previous PA considered only LAWABP1 glass, the current PA also describes radionuclide releasemore » from three different WTP glasses (LAWA44, LAWB45 and LAWC22), two different bulk vitrification glasses (6-tank composite and S-109), and three different grout waste forms (containing Silver Iodide, Barium Iodide and Barium Iodate). All WTP and bulk vitrification glasses perform well. However, the radionuclide release from the salt in the cast refractory surrounding the bulk vitrification waste packages is 2 to 170 times higher than the glass release rate, depending on the water recharge rate. Iodine-129 release from grouted waste forms is highly sensitive to the solubility of the iodine compound contained in the grout. The normalized iodine release rate from grout containing barium iodate is a factor of 10 higher than what the normalized release rate would be if the iodine were contained in LAWA44 glass.« less
  • The purpose of this report is to document the results from laboratory testing of the bulk vitri-fied (BV) waste form that was conducted in support of the 2005 integrated disposal facility (IDF) performance assessment (PA). Laboratory testing provides a majority of the key input data re-quired to assess the long-term performance of the BV waste package with the STORM code. Test data from three principal methods, as described by McGrail et al. (2000a; 2003a), are dis-cussed in this testing report including the single-pass flow-through test (SPFT) and product con-sistency test (PCT). Each of these test methods focuses on different aspectsmore » of the glass corrosion process. See McGrail et al. (2000a; 2003a) for additional details regarding these test methods and their use in evaluating long-term glass performance. In addition to evaluating the long-term glass performance, this report discusses the results and methods used to provided a recommended best estimate of the soluble fraction of 99Tc that can be leached from the engineer-ing-scale BV waste package. These laboratory tests are part of a continuum of testing that is aimed at improving the performance of the BV waste package.« less