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A Global Sensitivity Analysis of Traffic Microsimulation Input Parameters on Performance Metrics
Not Available
Code for Experiment in Publication “Sensitivity Analysis in the Presence of Intrinsic Stochasticity for Discrete Fracture Network Simulations”
Following the Open Research requirements for AGU journals, we must release the code used to perform the experiment described in our recent publication, posted at (https://arxiv.org/abs/2312.04722). This code fits a joint emulator to data from a Discrete Fracture Network (DFN) simulation, performed using the open-source software DFNworks (https://dfnworks.lanl.gov/). All code to be released implements existing methods; there are no novel algorithms nor any major innovations to existing software.
Sensitivity analysis in coupled radiation transport simulations.
Abstract not provided.
Application of Depletion Perturbation Theory for Sensitivity Analysis in the High Flux Isotope Reactor
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Thermal Optimization of UO2-Mo Fuel Using Sensitivity Analysis and Genetic Algorithms
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Dynamical Model of Drug Accumulation in Bacteria: Sensitivity Analysis and Experimentally Testable Predictions
Not Available
Cost Sensitivity Analysis for Consolidated Interim Storage of Spent Fuel: Evaluating the Effect of Economic Environment Parameters
This report evaluates how the economic environment (i.e., discount rate, inflation rate, escalation rate) can impact previously estimated differences in lifecycle costs between an integrated waste management system with an interim storage facility (ISF) and a similar system without an ISF.
Understanding CO 2 Storage Into Deep Saline Aquifers at the Shenhua Site, Ordos Basin using Simulation-based Sensitivity Analysis
No abstract provided.
Predictive Modeling of CO 2 Sequestration and Storage in Deep Saline Sandstone Reservoirs: Sensitivity Analysis of Mineral Rates in Reactive Transport
One idea for mitigating the increase in fossil- fuel generated carbon dioxide (CO 2 ) in the atmosphere is to inject CO 2 into subsurface saline sandstone reservoirs, thereby storing it in those geologic formations and out of the atmosphere.
Sensitivity Analysis and Uncertainty Quantification of the Feynman Y and Sm 2
Neutron multiplicity counting (NMC) experiments are frequently used to perform non-destructive assay (NDA) of special nuclear material (SNM) [2]. While the behavior of a critical or nearly critical system is well described by the mean count rate, which is the mean of the NMC distribution, the behavior of a highly subcritical system exhibits large fluctuation in time. Fission chains do not last long enough to overlap and thus the neutron population is relatively small with a large dispersion. The system behavior must therefore be described in terms of higher-order NMC distribution moments.
Sensitivity Analysis and Uncertainty Quantification of the Feynman Y and Sm 2
No abstract provided.
Adjoint-Based Sensitivity Analysis and Uncertainty Quantification for keff: Using the MCNP KSEN Card
No abstract provided.
Sensitivity Analysis of Contaminant Transport from Vadose Zone Sources to Groundwater
Remedy selection and implementation in the Central Plateau of the Hanford Site will be facilitated by a technically defensible description of vadose zone sources and their spatial and temporal impacts on groundwater. To this end, a case study approach is used to assess impacts to groundwater associated with uncertainties in source terms and hydraulic and sorption parameters for the B-Complex at Hanford. Several unplanned releases of wastes occurred in the tanks in the B-Complex. Several planned liquid waste discharges also occurred to cribs, trenches, tile fields, and French drains within the B-Complex, creating a significant inventory of contaminants in the vadose zone whose downward migration in the subsurface pose a potential threat to groundwater. Given the uncertainty in multiple source locations, volumes and intensities, and uncertainties in hydraulic and sorption properties, an integrated assessment of their combined effects is needed to guide characterization, support selection of appropriate remedies, and design appropriate monitoring for vadose zone source areas and the underlying aquifer.
Coupled Calculations of the Nuscale FIV Tests: Pre-test Simulations and Sensitivity Analysis
The NEAMS program aims to develop an integrated multi-physics simulation capability “pellet-to-plant” for the design and analysis of future generations of nuclear power plants. In particular, the Reactor Product Line code suite's multi-resolution hierarchy is being designed to ultimately span the full range of length and time scales present in relevant reactor design and safety analyses, as well as scale from desktop to petaflop computing platforms.