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At least 901 records · Page 50
All sourcesNASA NTRSDOE OSTI
DOE OSTI2018

Natural Resource Assessment for the Proposed Environmental Management Disposal Facility (EMDF), Oak Ridge, Tennessee

A major contributor to the success of decommissioning, demolition, and remediation activities at the East Tennessee Technology Park by the U.S. Department of Energy (DOE) Oak Ridge Office of Environmental Management (OREM) has been the availability of an onsite Low-Level Waste (LLW) landfill. However, the existing LLW landfill is near capacity, with cleanup of excess facilities at the Y-12 National Security Complex (Y-12) and Oak Ridge National Laboratory (ORNL) pending. Timely provision of additional disposal capacity on the Oak Ridge Reservation (ORR) is required to remedy the threats to human health and the environment.

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DOE OSTI2019

Deep Borehole Disposal Safety Case

This report describes the current status of the safety case for the deep borehole disposal (DBD) concept. It builds on the safety case presented in Freeze et al. (2016), presenting new information and identifying additional information needs for specific safety case elements. At this preliminary phase of development, the DBD safety case focuses on the generic feasibility of the DBD concept. It is based on potential system designs, waste forms, engineering, and geologic conditions; however, no specific site or regulatory framework exists. Updated information is provided for the following safety case elements: (1) pre-closure basis and safety analysis, (2) post-closure basis and performance assessment, and (3) confidence enhancement. This research was performed as part of the deep borehole field test (DBFT). Based on revised U.S. Department of Energy (DOE) priorities in mid-2017, the DBFT and other research related to a DBD option was discontinued; ongoing work and documentation were closed out by the end of fiscal year (FY) 2017. This report was initiated as part of the DBFT and documented as an incomplete draft at the end of FY 2017. The report was finalized by Sandia National Laboratories in FY2018 without DOE funding, subsequent to the termination of the DBFT, and published in FY2019.

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DOE OSTI2019

Thermal Analysis Of Saltstone Disposal Units

SRR requested that SRNL develop a two-dimensional computer simulation model to be capable of predicting grout temperatures attained in Saltstone Disposal Units (SDUs) during the transient addition of saltstone grout and its subsequent storage period. A simulation model was developed to calculate the transient grout temperatures of the SDU facility by taking an axisymmetric and two-dimensional Computational Fluid Dynamics (CFD) approach. The final performance calculations were based on the conduction and radiation model without a convection cooling mechanism for conservative estimate of the grout temperatures and computational efficiency. While convection within the SDU is disabled in the current calculations, the simulation model has the capability of turning convection back on if desired by the user. Hence, the thermal model in its current configuration is best characterized as a finite-volume heat transfer model. However, given that the model can account for convection if desired by the user, it will be referred to as a CFD model. The grout material contains a transient heat source due to the exothermic hydration reactions of the cementitious material mixed with salt solution. The model can predict the transient temperatures at point locations within the poured grout and the overlying vapor space, and at the interior and exterior surfaces of the structure. The thermal model has been developed for two SDUs at the Savannah River Site (SRS); namely, SDU 2A and SDU 6. SDU 2A is a cylindrical unit measuring 150 feet (ft) in diameter, 22 ft tall, and holds approximately three million gallons of grout. SDU 6 is 375 ft in diameter and 43 ft high with a capacity of over thirty million gallons. Prior to performing the thermal calculations for the SDU 6 facility, the benchmarking test for the smaller SDU 2A unit was performed to establish the solution method and to verify the computational results using existing thermocouple data. Based on the Lagrangian discrete method and boundary conditions established by the SDU 2A benchmarking test, the CFD calculations were performed to predict the transient temperatures at local positions of the poured grout and air spaces within the SDU 6 structure.

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DOE OSTI2017

Special Analysis for the Disposal of Sandia National Laboratory Line Generated Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis report evaluates whether the Sandia National Laboratory (SNL) Line Generated Waste is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the SNL Line Generated waste meets all DOE M 435.1-1 performance objectives.

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DOE OSTI2017

Special Analysis for the Disposal of the Idaho National Laboratory U-233 Solidified Grinding Sludge and Associated Debris Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis report evaluates whether the Idaho National Laboratory (INL) Uranium-233 (233U) Solidified Grinding Sludge and Associated Debris waste stream is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the INL 233U Solidified Grinding Sludge waste meets all DOE M 435.1-1 performance objectives. The INL 233U Solidified Grinding Sludge waste stream is recommended for acceptance with the condition that the total 233U inventory shall not exceed 2.3E13 Bq.

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DOE OSTI2017

UNREVIEWED DISPOSAL QUESTION EVALUATION: Development of Inventory Screening Limits for the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This Unreviewed Disposal Question Evaluation estimates the inventory of specific radionuclides that represent negligible risk for the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Radionuclides exceeding these screening limits are candidates for entry into the performance assessment and composite analysis model. Screening limits are developed for an expanded list of radionuclides. The screening limits are estimated as the total site inventory that would cause a receptor to receive 1/1000th of the 0.1 milliseivert (mSv) air pathway or 0.25 mSv all-pathways performance objectives. The receptor is assumed to be exposed to undiluted waste for a period of one year.

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DOE OSTI2017

Special Analysis for the Disposal of Sandia National Laboratory Line Generated Waste at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada, Revision 1.0

This special analysis report evaluates whether the Sandia National Laboratory (SNL) Line Generated Waste is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the SNL Line Generated waste meets all DOE M 435.1-1 performance objectives. The SNL Line Generated waste is recommended for acceptance with the following conditions: 1. The total waste stream tritium (3H) inventory shall not exceed 2E15 Bq; 2. The total waste stream radium-226 (226Ra) inventory shall not exceed 2E8 Bq; 3. The total waste stream thorium-230 (230Th) inventory shall not exceed 3E8 Bq; 4. The total waste stream uranium-234 (234U) inventory shall not exceed 2E10 Bq.

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DOE OSTI2014

Coal Fly Ash Disposal

Coal fly ash disposed of in a landfill. To access the model referenced in the report, please visit https://www.netl.doe.gov/energy-analysis/details?id=51451F09-EB9B-48E9-A600-0663B7967050

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DOE OSTI2013

Disposal, wood product, in landfill

This process covers the disposal of generic wood furniture in a municipal landfill. To access the model referenced in the report, please visit https://www.netl.doe.gov/energy-analysis/details?id=9A82C579-6A79-493A-8B52-E6966A89A651

54 ENVIRONMENTAL SCIENCES↗
DOE OSTI2016

Special Analysis for the Disposal of the Idaho National Laboratory Contact Handled Sealed Sources Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis (SA) evaluates whether the Idaho National Laboratory (INL) Contact Handled Sealed Sources waste stream is suitable for disposal by shallow land burial at the Area 5 Radioactive Waste Management Site (RWMS) on the Nevada National Security Site (NNSS). The INL Contact Handled Sealed Sources waste stream consists of sealed radioactive sources. The INL Contact Handled Sealed Sources waste stream requires an SA to determine whether the Area 5 RWMS can accept radium-226 ( 226 Ra), tritium ( 3 H), and europium-152 ( 152 Eu) at activity concentrations exceeding the NNSS Waste Acceptance Criteria Action Levels and whether to accept four long-lived radionuclides (curium-247 [ 247 Cm], 250 Cm, californium-249 [ 249 Cf], 251 Cf) without action levels.

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DOE OSTI2017

Special Analysis for the Disposal of the Oak Ridge National Laboratory Activated Metal Waste Stream at the Area 5 Radioactive Waste Management Site, Nevada National Security Site, Nye County, Nevada

This special analysis evaluates whether the Oak Ridge National Laboratory (ORNL) Activated Metal waste stream is suitable for shallow land burial at the Area 5 Radioactive Waste Management Site on the Nevada National Security Site. Disposal of the ORNL Activated Metal waste meets all U.S. Department of Energy Manual DOE M 435.1-1, “Radioactive Waste Management Manual,” Chapter IV, Section P performance objectives. The ORNL Activated Metal waste stream is recommended for acceptance with the condition that the total radium-226 ( 226 Ra) inventory be limited to 4.4E11 Bq (12 Ci).

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DOE OSTI2019

E-Area LLWF Final Closure Cap Design – Constructability Evaluation Criteria for the Plot 8 and NR07E Disposal Areas

SRNS Design Engineering has been asked to complete a constructability evaluation of the proposed final closure cap designs for the Plot 8 (Engineered Trenches ET07, ET08, and ET09) and 643-7E NRCDA (NR07E) disposal areas located outside the original E-Area Low-Level Waste Facility (ELLWF) footprint. This memorandum presents the guidelines and criteria for the constructability evaluation. A new conceptual design for the ELLWF closure cap is not requested at this time.

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