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Title: SPECIAL ANALYSIS: PRODUCTION TPBAR WASTE CONTAINER DISPOSAL WITHIN THE INTERMEDIATE LEVEL VAULT

Authors:
Publication Date:
Research Org.:
SRS
Sponsoring Org.:
USDOE
OSTI Identifier:
882717
Report Number(s):
WSRC-TR-2005-00531
DOE Contract Number:
DE-AC09-96SR1850
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

HIERGESELL, ROBERT. SPECIAL ANALYSIS: PRODUCTION TPBAR WASTE CONTAINER DISPOSAL WITHIN THE INTERMEDIATE LEVEL VAULT. United States: N. p., 2005. Web. doi:10.2172/882717.
HIERGESELL, ROBERT. SPECIAL ANALYSIS: PRODUCTION TPBAR WASTE CONTAINER DISPOSAL WITHIN THE INTERMEDIATE LEVEL VAULT. United States. doi:10.2172/882717.
HIERGESELL, ROBERT. Thu . "SPECIAL ANALYSIS: PRODUCTION TPBAR WASTE CONTAINER DISPOSAL WITHIN THE INTERMEDIATE LEVEL VAULT". United States. doi:10.2172/882717. https://www.osti.gov/servlets/purl/882717.
@article{osti_882717,
title = {SPECIAL ANALYSIS: PRODUCTION TPBAR WASTE CONTAINER DISPOSAL WITHIN THE INTERMEDIATE LEVEL VAULT},
author = {HIERGESELL, ROBERT},
abstractNote = {},
doi = {10.2172/882717},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Thu Dec 01 00:00:00 EST 2005},
month = {Thu Dec 01 00:00:00 EST 2005}
}

Technical Report:

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  • This Special Analysis (SA) evaluated a unique waste disposal item, the initial Tritium Extraction Facility (TEF) waste container, to determine its suitability for disposal within the intermediate Level Vault (ILV). This waste container will be used to dispose 900 extracted Tritium Producing Burnable Absorber Rods (TPBARs) and the Lead Test Assembly (LTA) container, which will hold 32 unextracted TPBARs. Suitability was determined by evaluating the contribution of the expected radionuclide inventory of the initial TEF waste container versus the disposal limits derived for it. The conclusion of this SA is that the TEF disposal container described in this investigation willmore » not cause any exceedance of U.S. Department of Energy (DOE) Order 435.1 performance measures over the 1000-year PA compliance period and may therefore be disposed of within the ILV.« less
  • New disposal limits have been computed for the IL vaults based on several revisions to the performance assessment. The most important changes are implementation of a 1,000 year time for compliance, rather than 10,000 years, and consideration of additional radon precursors. Other revisions include refinement of the aquifer mesh to more accurately model the footprint of two intermediate level (IL) vaults, a new Pu chemistry model accounting for the different transport properties of oxidation states III/IV and V/VI, and implementation of a timed sum-of-fractions approach to setting limits. A significant decrease in the groundwater pathway limits for I-129 was speculatedmore » in the FY2003 interim measures assessment, in response to refinement of the aquifer mesh and source node definition. In fact, the new limits for these nuclides are only slightly lower. Based on the IL vault inventory as of 7/2/04 and disposal limits developed herein, the largest inventory fractions are 30 per cent for Ra-226 and the radon analysis, 11 per cent for I-129 (generic) and the groundwater pathway, and 9 percent for C-14 and the air pathway. For comparison the volume-filled fraction is at about 36 percent. Continued operation of the IL vault should not challenge performance objectives, assuming future disposal patterns are similar to historic use of the facility.« less
  • This report examines the effects of new waste-specific sorption characteristics reported for I-129 bearing wastes on inventory limits in the Intermediate Level Vault (ILV). Inventory limits are described based on the revised performance assessment model using the waste-specific Kd's. Results are compared with inventory projections of waste streams for the next ten years.
  • This revision was prepared to address comments from DOE-SR that arose following publication of revision 0. This Special Analysis (SA) addresses disposal of wastes with high concentrations of I-129 in the Intermediate-Level (IL) Vaults at the operating, low-level radioactive waste disposal facility (the E-Area Low-Level Waste Facility or LLWF) on the Savannah River Site (SRS). This SA provides limits for disposal in the IL Vaults of high-concentration I-129 wastes, including activated carbon beds from the Effluent Treatment Facility (ETF), based on their measured, waste-specific Kds.
  • This Special Analysis (SA) addresses disposal of high-concentration I-129 wastes in the Intermediate Level (IL) Vaults at the Savannah River Site E-Area Low-Level Waste Facility. This SA addresses both the existing activated carbon vessels already placed in the IL Vault and any type of future waste that contains a high concentration of I-129. An equation is developed that relates a wasteform's vault inventory limit of I-129 to the wasteform's measured Kd. This SA was prepared to meet the requirements of the U.S. Department of Energy Order 435.1 (DOE 1999a). The order specifies that a performance assessment or SA should providemore » reasonable assurance that a low-level waste disposal facility will comply with the performance objectives of the Order. In addition to the performance objectives, the Order requires, for purposes of establishing limits on the concentration of radionuclides that may be disposed of near-surface, an assessment of impacts on water resources and on hypothetical persons assumed to inadvertently intrude for a temporary period into the low-level waste disposal facility.« less