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Sanborn, Scott E.

Publications and source records attributed to Sanborn, Scott E..

A summary of the Hanford single-shell tank structural analysis of record - 15526

Washington River Protection Solutions, LLC (WRPS), the US DOE Hanford Site tank contractor, developed an enhanced Single-Shell Tank Integrity Project (SSTIP) in 2009 to better understand the integrity of the single-shell tanks (SSTs). A panel of experts from industry and academia was created to recommend project activities in four main areas: structural integrity, liner degradation, leak integrity and prevention, and contamination migration. One of the panel's primary recommendations was to perform a detailed structural integrity analysis of the SSTs. WRPS and the U.S. Department of Energy, Office of River Protection commissioned the Pacific Northwest National Laboratory (PNNL) to perform this structural integrity analysis of record for the Hanford single shell tanks. This is one of seventeen panel recommendations that form the M-45-10-1 Change Package for the Hanford Federal Agreement and Compliance Order; also known as the Tri-Party Agreement. Finite element analysis was used to predict the structural response of the SSTs to the historical thermal and operating loads, plus design basis seismic loads. Bounding thermal histories were established from waste temperature records and applied to the model to include the thermal degradation of concrete modulus and strength, plus cracking due to differential thermal expansion while under in situ static loading conditions. PNNL contracted with Becht Engineering to evaluate the dynamic response of the tanks to a design basis earthquake. The degraded stiffness of the reinforced concrete was also incorporated in the seismic analysis. The combined response to static and seismic loads was then evaluated against the design requirements of the American Concrete Institute standard, ACI-349-06, for nuclear safety-related concrete structures. Specific analyses were performed for the four major tank designs.This paper presents an overview of the analysis methods used and it summarizes the major analytical findings that are common to the tanks and others that are specific to the individual tank designs. The analyses of record determined that including the bounding effects of their operating histories, each tank design currently satisfies the ACI-349-06 structural integrity design requirements. Although leak tightness is not directly addressed in the structural integrity analysis, this analysis will be a key input in the formal tank integrity assessment due in 2018. (authors)

12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE W↗

Sensitivity Studies on UNF Cladding Structural Integrity under NCT Loading

This work describes the sensitivity analyses performed on the transportation package used in the NCT initial modeling and simulation demonstration [1]. The initial demonstration predicted the structural integrity of the fuel cladding by integrating models from the fuel rod/grid slot level, the single assembly-level, and the full cask-level. A number of sensitivity analyses were performed on the models at the different levels to determine how sensitive the results were to the parameters that were varied. The results are used to coarsely group the parameters investigated into four categories of sensitivity: No Sensitivity, Low Sensitivity; Moderate Sensitivity, and High Sensitivity. The High Sensitivity analyses are described in detail below. The Moderate, Low and No Sensitivity results are briefly described.

used nuclear fuel, UNF, normal conditions of trans↗