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Status Report on Uncertainty Quantification and Sensitivity Analysis Tools in the Geologic Disposal Safety Assessment (GDSA) Framework

Swiler, Laura P.; Helton, Jon C.; Basurto, Eduardo; Brooks, Dusty M.; Mariner, Paul E.; Moore, Leslie; Mohanty, Sitakanta; Sevougian, Stephen D.; Stein, Emily

The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Fuel Cycle Technology (FCT) is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high-level nuclear waste (HLW). Two high priorities for SFWST disposal R&D are design concept development and disposal system modeling. These priorities are directly addressed in the SFWST Geologic Disposal Safety Assessment (GDSA) control account, which is charged with developing a geologic repository system modeling and analysis capability, and the associated software, GDSA Framework, for evaluating disposal system performance for nuclear waste in geologic media. GDSA Framework is supported by SFWST Campaign and its predecessor the Used Fuel Disposition (UFD) campaign.

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Progress in Deep Geologic Disposal Safety Assessment in the U.S. since 2010

Mariner, Paul E.; Connolly, Laura A.; Cunningham, Leigh; Debusschere, Bert J.; Dobson, David C.; Frederick, Jennifer M.; Hammond, Glenn E.; Jordan, Spencer H.; Laforce, Tara C.; Nole, Michael A.; Park, Heeho D.; Bays, Nathan R.; Rogers, Ralph; Seidl, D.T.; Sevougian, Stephen D.; Stein, Emily; Swift, Peter; Swiler, Laura P.; Vo, Jonathan; Wallace, Michael

The Spent Fuel and Waste Science and Technology (SFWST) Campaign of the U.S. Department of Energy (DOE) Office of Nuclear Energy (NE), Office of Spent Fuel & Waste Disposition (SFWD) is conducting research and development (R&D) on geologic disposal of spent nuclear fuel (SNF) and high-level nuclear waste (HLW). Two high priorities for SFWST disposal R&D are design concept development and disposal system modeling (DOE 2011, Table 6). These priorities are directly addressed in the SFWST Geologic Disposal Safety Assessment (GDSA) work package, which is charged with developing a disposal system modeling and analysis capability for evaluating disposal system performance for nuclear waste in geologic media.

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High fidelity surrogate modeling of fuel dissolution for probabilistic assessment of repository performance

International High-Level Radioactive Waste Management 2019, IHLRWM 2019

Mariner, Paul E.; Swiler, Laura P.; Seidl, D.T.; Debusschere, Bert J.; Vo, Johnathan; Frederick, Jennifer M.

Two surrogate models are under development to rapidly emulate the effects of the Fuel Matrix Degradation (FMD) model in GDSA Framework. One is a polynomial regression surrogate with linear and quadratic fits, and the other is a k-Nearest Neighbors regressor (kNNr) method that operates on a lookup table. Direct coupling of the FMD model to GDSA Framework is too computationally expensive. Preliminary results indicate these surrogate models will enable GDSA Framework to rapidly simulate spent fuel dissolution for each individual breached spent fuel waste package in a probabilistic repository simulation. This capability will allow uncertainties in spent fuel dissolution to be propagated and sensitivities in FMD inputs to be quantified and ranked against other inputs.

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xLPR Scenario Analysis Report

Eckert, Aubrey; Lewis, John R.; Brooks, Dusty M.; Martin, Nevin S.; Hund, Lauren; Clark, Andrew J.; Mariner, Paul E.

This report describes the methods, results, and conclusions of the analysis of 11 scenarios defined to exercise various options available in the xLPR (Extremely Low Probability of Rupture) Version 2 .0 code. The scope of the scenario analysis is three - fold: (i) exercise the various options and components comprising xLPR v2.0 and defining each scenario; (ii) develop and exercise methods for analyzing and interpreting xLPR v2.0 outputs ; and (iii) exercise the various sampling options available in xLPR v2.0. The simulation workflow template developed during the course of this effort helps to form a basis for the application of the xLPR code to problems with similar inputs and probabilistic requirements and address in a systematic manner the three points covered by the scope.

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Results 26–50 of 54
Results 26–50 of 54
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