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As requested by Solid Waste Management (SWM), this report documents the Savannah River National Laboratory's (SRNL's) evaluation of updated Naval Reactor waste container and inventory projections and proposes a Naval Reactor Component Disposal Area (NRCDA) groundwater (GW) pathway modeling approach for the next E-Area Low-Level Waste Facility (LLWF) Performance Assessment (PA).Two areas within the E-Area LLWF are used as disposal sites for reactor components from the U.S. Navy. Currently, components arrive by rail and are moved by crane to the 643-26E at-grade gravel disposal pad. Prior to operational closure, reactor components were stored and ultimately disposed in-place on the 643-7E NRCDA (Wilhite and Flach 2004). Naval Reactor (NR) waste is comprised of highly radioactive components consisting of activated corrosion-resistant metal alloy contained within welded thick steel casks, and auxiliary equipment primarily contaminated with Activated Corrosion Products (sometimes referred to as "crud" by the U.S. Navy) at low levels and contained within thinner-walled bolted containers. The 643-7E disposal pad, which contains 41 casks and has an interim soil cover, is closed to future receipts. The latest NR waste projections for the 643-26E disposal pad are substantially different from the original estimates due to a change in reactor maintenance. The original estimate was for 50 heavily shielded, welded casks and 50 thinner-walled bolted containers (primarily shield blocks). Currently, NR Programs project 33 heavily shielded, welded casks, of which 31 are already in-place on the 643-26E pad, and 381 thinnerwalled bolted containers.In addition to new waste form projections, there have been changes in facility layout and closure plans as well as PA modeling improvements. This report documents these changes as well as key NRCDA recommendations from the 2015 PA Strategic Plan (Butcher 2016). Key findings and recommendations are summarized inTable 0-1 below. SRNL-STI-2018-00633 Revision 0 vii Table 0-1. Comparison of Proposed Modeling Approach with 2008 E-Area LLWF PA. Model Feature-Aspect New Approach 2008 PA Approach Justification Number of NR Containers on 643-26E Open ended 100 cask limit Requested by SWM Type of Analysis Limits analysis -model unit curie of each rad for comparison with Performance Objectives Preliminary closure analysismodeled dose impact of projected inventory supplied by NR -scaled results for limits Requested by SWM 643-7E Perform closure analysis on final inventory from 41 containers Applied results of 643-26E model to 643-7E performance Changes in flow paths due to new aquifer model Limits Separate limits -ACP and activated metal, bolted and welded casks Single set of limits -combined all forms of inventory into a representative Knolls Atomic Power Laboratory core barrel/thermal shield cask Revision viii Revision 0 10 Table 4-2. 643-26E Projected Inventories by Waste Type Activated Metal (FY40) ACP (FY40) ISOTOPE Activity (Ci) ISOTOPE Activity (Ci)

an initial decrease, remained constant for loadings up to 50 wt-%. Small angle X-ray scattering (SAXS) showed a large decrease in the amount of lamellar structure relative to the neat PP, while wide angle X-ray scattering (WAXS) showed a high degree of crystallinity. These results are consistent with formation of a new type of layered nanocomposite, composed of crystalline PP chains oriented onto layered GNPs.

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Biodiesel is produced in the United States to D 6751, an ASTM standard. The source material in this fledgling industry in the U.S. is primarily soy oil, though other sources such as canola oil, waste oils, and greases from food and other sources are beginning to be exploited. At present, the referenced ASTM standard does not specify cloud and pour points values that are much higher for biodiesel than diesel derived from petroleum but allows them to be specified by the customer. There can be significant variation in these values, depending on the nature of the source material used to produce biodiesel, all of which meet the ASTM standards. This has the potential to create problems in applications as the quality of the biodiesel produced could vary widely. This study focused on quantitative measurements of cloud points of blends of biodiesel made from different sources. A correlation of these measurements with the saturated components was developed and was shown to correlate data reported in the literature as well.

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This document provides the Department of Energy (DOE) Order 435.1, Radioactive Waste Management (DOE 1999c) 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 these new PA baselines is expected to be minor for the following reasons: The primary contributors to the SRS CA dose impact at the UTR 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, E-Area LLWF, 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 Order 435.1. 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 completed of PA revisions.