Special Analysis Air Pathway Modeling of E-Area Low-Level Waste Facility PDF Download
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Languages : en
Pages :
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Author:
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Languages : en
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Author:
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Languages : en
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The F-Area Tank Farm (FTF) is located within F-Area in the General Separations Area (GSA) of the Savannah River Site (SRS) as seen in Figure 1. The GSA contains the F and H Area Separations Facilities, the S-Area Defense Waste Processing Facility, the Z-Area Saltstone Facility, and the E-Area Low-Level Waste Disposal Facilities. The FTF is a nearly rectangular shaped area and comprises approximately 20 acres, which is bounded by SRS coordinates N 76,604.5 to N 77,560.0 and E 52,435.0 to E 53,369.0. SRS is in the process of preparing a Performance Assessment (PA) to support FTF closure. As part of the PA process, an analysis was conducted to evaluate the potential magnitude of gaseous release of radionuclides from the FTF over the 100-year institutional control period and 10,000-year post-closure compliance period. Specifically, an air and radon pathways analysis has been conducted to estimate the flux of volatile radionuclides and radon at the ground surface due to residual waste remaining in the tanks following closure. This analysis was used as the basis to estimate the dose to the maximally exposed individual (MEI) for the air pathway per Curie (Ci) of each radionuclide remaining in the combined FTF waste tanks. For the air pathway analysis, several gaseous radionuclides were considered. These included carbon-14 (C-14), chlorine-36 (Cl-36), iodine-129 (I-129), selenium-79 (Se-79), antimony-125 (Sb-125), tin-126 (Sn-126), tritium (H-3), and technetium-99 (Tc-99). The dose to the MEI was estimated at the SRS Boundary during the 100 year institutional control period. For the 10,000 year post closure compliance period, the dose to the MEI was estimated at the 100 m compliance point. For the radon pathway analysis, five parent radionuclides and their progeny were analyzed. These parent radionuclides included uranium-238 (U-238), plutonium-238 (Pu-238), uranium-234 (U-234), thorium-230 (Th-230), and radium-226 (Ra-226). The peak flux of radon-222 due to each parent radionuclide was estimated for the simulation period of 10,100 years.
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Category :
Languages : en
Pages : 5
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This Special Analysis for Components-in-Grout (CIG) expands the list of isotopes to the full suite of normal isotopes. This revision also addresses selected isotopes in special waste forms from the K and L basin resin that have waste-specific Kds and high-concentration I-129 wastes with waste-specific Kds, including Effluent Treatment Facility (ETF) activated carbon vessels. The full suite of normal isotopes was first screened using the Slit Trench screening results as a conservative approach. The isotopes that survived the screening were analyzed to determine the appropriate CIG inventory limits. The groundwater modeling was revised to incorporate improvements and changes in other recent Special Analyses and Unreviewed Disposal Question (UDQ) evaluations. The air pathway analysis was modified to consider a distributed source rather than a point source. These changes are discussed below in intruder and groundwater sections. Tables and figures are provided in appendices that are directly related to the most recent analyses. Changes to inventory limits are shown in Table 7. Inventory limits for solubility- limited radionuclides require special treatment as discussed in Section 3.1.1.3. U-238 and Pu-239 were analyzed as being solubility-limited, because otherwise they would consume excessive amounts of their inventory limits. Other U and Pu isotopes were not analyzed as being solubility- limited because they would not consume excessive amounts of inventory limits. Current and projected inventories for the K and L basin resins are compared against inventory limits for a single set of 5 CIG trenches. Projections for the K and L basin waste are through 2035, thus actual inventory consumption is dependent on the total number of CIG trenches excavated and filled through 2035. Current inventory for three ETF activated carbon vessels awaiting disposal are compared against inventory limits for a single set of 5 CIG trenches.
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Category :
Languages : en
Pages : 82
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The Weldon Spring site is a mixed waste site located in St. Charles County, Missouri. Cleanup of the site is in the planning and design stage, and various engineering activities were considered for remedial action, including excavating soils, dredging sludge, treating various contaminated media in temporary facilities, transporting and staging supplies and contaminated material, and placing waste in an engineered disposal cell. Both contaminated and uncontaminated emissions from these activities were evaluated to assess air quality impacts and potential health effects for workers and the general public during the cleanup period. A site-specific air quality modeling approach was developed to address several complex issues, such as a variety of emission sources, an array of source/receptor configurations, and complicated sequencing/scheduling. This approach can be readily adapted to reflect changes in the expected activities as engineering plans are finalized.
Author: International Atomic Energy Agency
Publisher: IAEA
ISBN:
Category : Business & Economics
Languages : en
Pages : 188
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Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.
Author: OECD Nuclear Energy Agency
Publisher: OECD Publishing
ISBN:
Category : Technology & Engineering
Languages : en
Pages : 188
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This report sets out the costs of operating disposal sites for LLW in OECD countries, as well as the factors that may affect the costs of sites being developed.
Author:
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Category :
Languages : en
Pages : 13
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The first detailed comprehensive simulation study to evaluate fate and transport of low-level, mixed, and transuranic wastes buried in the Subsurface Disposal Area (SDA) at the Idaho National Engineering and Environmental Laboratory (INEEL) has recently been conducted. The study took advantage of pertinent information relating to describing aqueous- and vapor-phase movement of contaminants in the primarily fractured basalt subsurface. The study included spatially and temporally variable infiltration, barometric pressure changes, positive down-hole air pressure during well drilling, vapor-vacuum extraction, and regional hydraulic gradients. Use of the TETRAD simulation code allowed all the pertinent information to be included into a single comprehensive model of the SDA subsurface. An overview of the model implementation and comparisons of calibrated model results to the observed vadose zone water distribution, volatile organic vapor concentrations, and aqueous concentrations of volatile organics and nitrate are presented. Additionally, comparisons between simulated and observed concentrations for other contaminants which were not used for model calibration are made. As part of this modeling exercise, inadequacies in the available data relating to characterization of non-sorbing aqueous-phase transport have been identified. Even with the identified data inadequacies, the comparisons between simulated and observed contaminants along with the calibration results give confidence that the model is a conservative representation of flow and transport in the subsurface at the SDA. The results from this modeling study are being used to guide additional data collection activities at the SDA for purposes of increasing confidence in the appropriateness of model predictions.
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309052262
Category : Science
Languages : en
Pages : 590
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Disposal of radioactive waste from nuclear weapons production and power generation has caused public outcry and political consternation. Nuclear Wastes presents a critical review of some waste management and disposal alternatives to the current national policy of direct disposal of light water reactor spent fuel. The book offers clearcut conclusions for what the nation should do today and what solutions should be explored for tomorrow. The committee examines the currently used "once-through" fuel cycle versus different alternatives of separations and transmutation technology systems, by which hazardous radionuclides are converted to nuclides that are either stable or radioactive with short half-lives. The volume provides detailed findings and conclusions about the status and feasibility of plutonium extraction and more advanced separations technologies, as well as three principal transmutation concepts for commercial reactor spent fuel. The book discusses nuclear proliferation; the U.S. nuclear regulatory structure; issues of health, safety and transportation; the proposed sale of electrical energy as a means of paying for the transmutation system; and other key issues.
Author: United States. Department of Energy. Technical Information Center
Publisher:
ISBN:
Category : Radiation
Languages : en
Pages : 740
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Author:
Publisher:
ISBN:
Category : Soil pollution
Languages : en
Pages : 182
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