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Proceedings Papers

Considerations for Development of Probabilistic Assessments for Nuclear Systems and Components

Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T10A015, August 4–5, 2020

Paper No: ICONE2020-16935

DOI: https://doi.org/10.1115/ICONE2020-16935

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Topics: Defense industry, Failure, Nuclear industry, Probability, Reliability, Risk, Safety, Transparency

Journal Articles

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Jason J. Song, Paul K. Chan, Hugues W. Bonin, Mahesh Pandey

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041111.

Paper No: NERS-19-1167

DOI: https://doi.org/10.1115/1.4047162

Published Online: September 4, 2020

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Topics: Fuels, Manufacturing, Simulation, Transients (Dynamics), Temperature, Uncertainty, Pressure

Proceedings Papers

Historical Rates of Soil Side Corrosion for Use in Fitness-for-Service Evaluations of Buried Metallic Pipe

Douglas Munson, Mahesh Pandey, Mikko Jyrkama, Peter Angell

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A001, July 17–21, 2016

Paper No: PVP2016-63923

DOI: https://doi.org/10.1115/PVP2016-63923

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Topics: Corrosion, Fitness-for-service, Pipes, Soil, Metals, Texture (Materials), Probes, ASME Standards, Carbon steel, Cast iron

Proceedings Papers

A Case Study on the Normality of Monte-Carlo Simulation Results

Konstantinos Tsembelis, Seyun Eom, Nicholas Christodoulou, Mahesh Pandey, John Jin

Proc. ASME. PVP2016, Volume 1B: Codes and Standards, V01BT01A019, July 17–21, 2016

Paper No: PVP2016-63622

DOI: https://doi.org/10.1115/PVP2016-63622

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Topics: Simulation results, Pressure, Transfer functions, Computers, Creep, Defense industry, Gaussian distribution, Nonlinear systems, Nuclear industry, Probabilistic safety assessment

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Considerations for Development of Probabilistic Assessments for Nuclear Systems and Components

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Historical Rates of Soil Side Corrosion for Use in Fitness-for-Service Evaluations of Buried Metallic Pipe

A Case Study on the Normality of Monte-Carlo Simulation Results

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Considerations for Development of Probabilistic Assessments for Nuclear Systems and Components

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Historical Rates of Soil Side Corrosion for Use in Fitness-for-Service Evaluations of Buried Metallic Pipe

A Case Study on the Normality of Monte-Carlo Simulation Results

Journals

Conference Proceedings

eBooks

Resources

Opportunities

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