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Vaughn, Palmer

Publications and source records attributed to Vaughn, Palmer.

Generic Disposal System Model for Granite: Potential Application to Joint Fuel Cycles Studies

The following is intended as a possible approach to support Phase 1 Task 1 of the Joint Fuel Cycles Studies collaboration between the Republic of Korea (ROK) and the US DOE Nuclear Energy Used Fuel Disposition Campaign (UFDC). In this approach UFDC is providing ROK with a brief description of our simplified granite generic disposal system (GDS) model, as it has been implemented in our Generic Performance Assessment Model (GPAM). A more detailed description of the original, stand alone, granite GDS model and GPAM appears in the UFD FY 11 report (Clayton, et. al., 2011), which was provide as an attachment to an earlier email to Task 1 ROK counterparts. Additionally, UFDC is providing the input data sets (parameter, values, descriptions and uncertainty) used to implement the stand alone granite GDS model into GPAM, as a starting point.

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗

Review of Inputs Provided to Jason Associates Corporation in Support of RWEV-REP-001, the Analysis of Postclosure Groundwater Impacts Report

Report RWEV-REP-001, Analysis of Postclosure Groundwater Impacts for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High Level Radioactive Waste at Yucca Mountain, Nye County, Nevada was issued by the DOE in 2009 and is currently being updated. Sandia National Laboratories (SNL) provided support for the original document, performing calculations and extracting data from the Yucca Mountain Performance Assessment Model that were used as inputs to the contaminant transport and dose calculations by Jason Associates Corporation, the primary developers of the DOE report. The inputs from SNL were documented in LSA-AR-037, Inputs to Jason Associates Corporation in Support of the Postclosure Repository Supplemental Environmental Impact Statement. To support the updating of the original Groundwater Impacts document, SNL has reviewed the inputs provided in LSA-AR-037 to verify that they are current and appropriate for use. The results of that assessment are documented here.

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗