IAEA Workshop lectures on Spatial variability uncertainty analysis and sensitivity analysis
Abstract not provided.
Publications
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Jump to search filtersSOARCA project uncertainty Analysis Part I - uncertainty approach methodology
Abstract not provided.
Sandia's propositions toward a joint activity on uncertainty quantification and sensitivity analysis
Abstract not provided.
SOARCA Peach Bottom Atomic Power Station long-term station blackout uncertainty analysis MELCOR parameters and probabilistic results
Abstract not provided.
SOARCA Peach Bottom Atomic Power Station long-term station blackout uncertainty analysis MACCS2 parameters and probabilistic results
Abstract not provided.
SOARCA Peach Bottom Atomic Power Station long-term station blackout uncertainty analysis MACCS2 dose truncation sensitivity
Abstract not provided.
SOARCA Peach Bottom Atomic Power Station long-term station blackout uncertainty analysis probabilistic methodology and regression technique
Abstract not provided.
Probability of Loss of Assured Safety in Systems with Multiple Time-Dependent Failure Modes: Example Analyses with Aleatory and Epistemic Uncertainty
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Uncertainty and Sensitivity Analysis for the Early Failure Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose for the Early Failure Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose for the Nominal Scenario Class in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Uncertainty and Sensitivity Analysis for the Igneous Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose for the Igneous Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose for the Seismic Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Uncertainty and Sensitivity Analysis for the Seismic Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Representation of Aleatory Uncertainty Associated with the Seismic Ground Motion Scenario Class in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose and Associated Uncertainty and Sensitivity Analysis Results for the Human Intrusion Scenario in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Expected Dose and Associated Uncertainty and Sensitivity Analysis Results for All Scenario Classes in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Assessment of Compliance with Ground Water Protection Standards in the 2008 Performance Assessment for the Proposed High-Level Radioactive Waste Repository at Yucca Mountain Nevada
Proposed for publication in Reliability Engineering and System Safety.
Abstract not provided.
Uncertainty and sensitivity analysis in performance assessment for the proposed high-level radioactive waste repository at Yucca Mountain, Nevada
Reliability Engineering and System Safety
Extensive work has been carried out by the U.S. Department of Energy (DOE) in the development of a proposed geologic repository at Yucca Mountain (YM), Nevada, for the disposal of high-level radioactive waste. As part of this development, a detailed performance assessment (PA) for the YM repository was completed in 2008 and supported a license application by the DOE to the U.S. Nuclear Regulatory Commission (NRC) for the construction of the YM repository. The following aspects of the 2008 YM PA are described in this presentation: (i) conceptual structure and computational organization, (ii) uncertainty and sensitivity analysis techniques in use, (iii) uncertainty and sensitivity analysis for physical processes, and (iv) uncertainty and sensitivity analysis for expected dose to the reasonably maximally exposed individual (RMEI) specified the NRC's regulations for the YM repository. © 2011 Elsevier Ltd.
CPLOAS_2 user manual
Weak link (WL)/strong link (SL) systems are important parts of the overall operational design of high-consequence systems. In such designs, the SL system is very robust and is intended to permit operation of the entire system under, and only under, intended conditions. In contrast, the WL system is intended to fail in a predictable and irreversible manner under accident conditions and render the entire system inoperable before an accidental operation of the SL system. The likelihood that the WL system will fail to deactivate the entire system before the SL system fails (i.e., degrades into a configuration that could allow an accidental operation of the entire system) is referred to as probability of loss of assured safety (PLOAS). This report describes the Fortran 90 program CPLOAS_2 that implements the following representations for PLOAS for situations in which both link physical properties and link failure properties are time-dependent: (i) failure of all SLs before failure of any WL, (ii) failure of any SL before failure of any WL, (iii) failure of all SLs before failure of all WLs, and (iv) failure of any SL before failure of all WLs. The effects of aleatory uncertainty and epistemic uncertainty in the definition and numerical evaluation of PLOAS can be included in the calculations performed by CPLOAS_2.
Probability of loss of assured safety in systems with multiple time-dependent failure modes
Weak link (WL)/strong link (SL) systems are important parts of the overall operational design of high-consequence systems. In such designs, the SL system is very robust and is intended to permit operation of the entire system under, and only under, intended conditions. In contrast, the WL system is intended to fail in a predictable and irreversible manner under accident conditions and render the entire system inoperable before an accidental operation of the SL system. The likelihood that the WL system will fail to deactivate the entire system before the SL system fails (i.e., degrades into a configuration that could allow an accidental operation of the entire system) is referred to as probability of loss of assured safety (PLOAS). Representations for PLOAS for situations in which both link physical properties and link failure properties are time-dependent are derived and numerically evaluated for a variety of WL/SL configurations, including PLOAS defined by (i) failure of all SLs before failure of any WL, (ii) failure of any SL before failure of any WL, (iii) failure of all SLs before failure of all WLs, and (iv) failure of any SL before failure of all WLs. The effects of aleatory uncertainty and epistemic uncertainty in the definition and numerical evaluation of PLOAS are considered.
Uncertainty and Parameter Sensitivity Analyses for the U.S. NRC: Understanding and Verification of the Extremely Low Probability of Rupture (xLPR) in Reactor Primary System Pressure Piping
Abstract not provided.
Copy of GSxLPR Version 1.0 Computational Code Architecture and Overview Briefing
Abstract not provided.
Uncertainty and Sensitivity Analysis: From Regulatory Requirements to Conceptual Structure and Computational Implementation
Abstract not provided.
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