PORFLOW Implementation of Vadose Zone Conceptual Model for Naval Reactor Component Disposal Areas in the E-Area Low Level Waste Facility Performance Assessment

Hang, T.; Hamm, L.L.

doi:10.2172/1637922

Cited by 5 publications

(14 citation statements)

References 4 publications

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“…It is estimated that 33 heavily shielded, welded carbon steel casks and over 400 thinner-walled bolted containers will be disposed at this site before closure in 2065. Table 2.1.1 gives area footprints and nominal side lengths (assuming a square area) for the NRCDA sites (Hang and Hamm, 2019). As Figure 2.1.1 shows, the NRCDA sites do not have square footprints; however, using square side dimensions to approximate the shape of the disposal sites was deemed adequate for modeling purposes.…”

Section: Naval Reactor Component Disposal Areasmentioning

confidence: 99%

“…Waste storage at NRCDA 643-7E was started prior to its designation as a disposal site and prior to waste disposal in 643-26E. Therefore, as described in documentation of the PORFLOW NRCDA model (Hang and Hamm, 2019), events at the two disposal sites follow different timelines. To facilitate software maintenance and quality assurance, it is highly desirable to have a single GoldSim model that can be used for either site.…”

Section: Nrcda Waste Characteristicsmentioning

confidence: 99%

“…Therefore, the timeline information for both disposal sites was combined into the composite timeline shown in Table 2.3.1. The PORFLOW model report (Hang and Hamm, 2019) provides more detailed information about the timelines given in Table 2.3.1; however, event timings shown in this table are enough to construct the GoldSim model.…”

Section: Nrcda Waste Characteristicsmentioning

confidence: 99%

“…Bolted containers are assumed to fail instantaneously and release all their waste inventory at once. Container failure is assumed to occur either at the time soil is mounded over the disposal area or 750 years after disposal roughly corresponding to hydraulic failure of welded casks due to weld corrosion (Hang and Hamm, 2019). Welded steel casks are assumed to contain active metal waste that slowly releases radionuclides through metal corrosion.…”

Section: Goldsim Model Descriptionmentioning

confidence: 99%

“…A PORFLOW model of infiltration and radionuclide transport through the waste region and underlying vadose zone at the Naval Reactor Component Disposal Area (NRCDA) disposal sites has been developed (Hang and Hamm, 2019). This model will be used to calculate fluxes to the water table from radionuclide releases at the NRCDA sites.…”

Section: Introductionmentioning

confidence: 99%

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Goldsim Modeling of Vadose Zone Transport for E-Area Naval Reactor Component Disposal Areas: Model Description and Benchmarking

Smith

2020

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Section: Naval Reactor Component Disposal Areasmentioning

confidence: 99%

Section: Nrcda Waste Characteristicsmentioning

confidence: 99%

Section: Nrcda Waste Characteristicsmentioning

confidence: 99%

Section: Goldsim Model Descriptionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Goldsim Modeling of Vadose Zone Transport for E-Area Naval Reactor Component Disposal Areas: Model Description and Benchmarking

Smith

2020

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Hydraulic Properties Data Package for the E-Area Soils, Cementitious Materials, and Waste Zones - Update

Nichols

Butcher

2020

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The primary objective of this report is to provide an update to the report prepared by Phifer et al. (2006) on the hydraulic property estimates for the soils, cementitious materials, and waste zones associated with the E-Area Low-Level Waste Facility (LLWF). Phifer et al. (2006) also addressed properties for the Z-Area Saltstone Disposal Facility (SDF). However, this report only addresses updates for the portions relevant to E-Area and therefore references to Z-Area have been removed. Therefore, this report supersedes (Phifer et al., 2006).These hydraulic property estimates will be used as input to deterministic, sensitivity, and uncertainty modeling conducted to support the Performance Assessments (PA) for the E-Area LLWF. The hydraulic properties provided for each of the E-Area material zones include: porosity (η), dry bulk density (ρb), particle density (ρp), saturated hydraulic conductivity (Ksat), characteristic curves (suction head, saturation, and relative permeability), and effective diffusion coefficient (De). Nominal or "best estimate" values are provided for use in the deterministic modeling, and representations of the value uncertainty are provided for use in sensitivity and uncertainty modeling efforts.

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FY2020 Savannah River Site Composite Analysis Annual Summary Review

Stagich¹

2021

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This document provides the Department of Energy (DOE) Order 435.1 and its manual, Radioactive Waste Management (DOE 2021a(DOE , 2021b required Annual Review for the Savannah River Site (SRS) Composite Analysis (CA).Progress made to-date toward addressing the secondary issue from the LFRG review of the 2010 SRS CA has focused primarily upon inventory estimate improvements. Inventory impacts dose in a linear fashion and reduces the uncertainty with the CA conclusions. Maintenance items are addressed, as funding allows, based on the relative risk associated with meeting the performance objectives. Currently, there is minimal risk in exceeding the DOE 100 mrem/yr CA primary dose limit or the DOE 30 mrem/yr dose constraint (administrative limit).Proposed activities, discoveries, new information and changes potentially affecting the 2010 SRS CA are documented in this and earlier Annual Summary reports, and a consolidated list of changes since the 2010 CA is documented in this report. The impact to the CA of changes arising from updated performance assessment (PA) baselines [i.e., Saltstone Disposal Facility (SDF), E-Area Low-Level Waste Facility (ELLWF), and F & H Tank Farm (FTF & HTF) closures] is expected to be minor for the following reasons: The primary contributors to the SRS CA dose impact at the Upper Three Runs (UTR) point of assessment (POA) are the H-Canyon and Mixed Waste Management Facility (MWMF), contributing 68% and 9%, respectively, to the dose impact at that POA. The combined contribution to the UTR dose impact from all PA's (SDF, ELLWF, FTF and HTF) is ~2% of this total.The 2010 SRS CA model validation performed indicates that the CA projected dose, while generally conservative, provides a reasonable representation of the maximum annual doses. Doses evaluated are well below the SRS established 15 mrem/yr administrative limit (Crapse et al. 2011).Based on the assessment presented within this annual review and collective engineering judgement, the conclusions of the 2010 SRS CA remain valid and there is reasonable assurance that SRS will meet the performance objectives delineated in DOE Manual 435.1-1. The 2010 SRS CA should be updated to incorporate PA changes, proposed changes to inventories and sources and model improvements accumulated since the 2010 CA. The timing will be dependent on the completion of the ongoing E-Area PA revision.

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PORFLOW Implementation of Vadose Zone Conceptual Model for Naval Reactor Component Disposal Areas in the E-Area Low Level Waste Facility Performance Assessment

Cited by 5 publications

References 4 publications

Goldsim Modeling of Vadose Zone Transport for E-Area Naval Reactor Component Disposal Areas: Model Description and Benchmarking

Goldsim Modeling of Vadose Zone Transport for E-Area Naval Reactor Component Disposal Areas: Model Description and Benchmarking

Hydraulic Properties Data Package for the E-Area Soils, Cementitious Materials, and Waste Zones - Update

FY2020 Savannah River Site Composite Analysis Annual Summary Review

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