PSAM 16 - Paper Overview

PSAM 16 Conference Paper Overview

Welcome to the PSAM 16 Conference paper and speaker overview page.

Lead Author: Kurt Vedros Co-author(s): Robby Christian, robby.christian@inl.gov Austin Glover, amglove@sandia.gov Curtis Smith, curtis.smith@inl.gov

Probabilistic Risk Assessment of a Light Water Reactor Coupled with a High-Temperature Electrolysis Hydrogen Production Plant – Part 1: Hazards Analysis
The profitability of existing nuclear power plants (NPPs) can be enhanced by using excess thermal energy to supply industrial processes. While the decision to modify the NPP to supply thermal energy externally to the plant is an economic one, the licensing permission for the modification is based on safety. To investigate the safety acceptance for such a modification, two generic probabilistic risk assessment (PRA) models were developed in this study to evaluate the effect on safety of the addition of a heat extraction system (HES) to a light water reactor (LWR). The two PRA models are for a pressurized-water reactor (PWR) and a boiling water reactor (BWR), respectively. The introduction of a HES has the goal of providing heat that would normally be wasted to be used for new revenue generation through processes such as making hydrogen. This HES module feeds process heat to a High Temperature Electrolysis Facility (HTEF). The PRAs used in this assessment of the HES are generic, and therefore some assumptions are made to preserve generality. A Failure Mode and Effects Analysis (FMEA) was performed to identify and screen the possible hazards due to the addition of the hydrogen production system. Hydrogen cloud and high-pressure jet detonation events were studied in relation to their contribution to components/structures fragility. A sensitivity analysis was performed to investigate the effect of several HES design options and distance to the nuclear reactor complex. The results of the PRA indicate that application using the U.S. licensing approach in 10 CFR 50.59 is justified because the increase in initiating event frequencies for all design basis accidents (DBAs) is within limits. The PRA results for core damage frequency (CDF) support the use of U.S. Nuclear Regulatory Commission Regulatory Guide 1.174 as further risk information that supports a change to the plant. Further insights provided through hazard analysis and sensitivity studies suggest that the addition of an HES module, and an HTEF plant at a reasonable distance from the nuclear plant satisfies safety and licensing requirements. Note that unique site-specific information may alter these conclusions.

Probabilistic Risk Assessment of a Light Water Reactor Coupled with a High-Temperature Electrolysis Hydrogen Production Plant – Part 1: Hazards Analysis

The profitability of existing nuclear power plants (NPPs) can be enhanced by using excess thermal energy to supply industrial processes. While the decision to modify the NPP to supply thermal energy externally to the plant is an economic one, the licensing permission for the modification is based on safety. To investigate the safety acceptance for such a modification, two generic probabilistic risk assessment (PRA) models were developed in this study to evaluate the effect on safety of the addition of a heat extraction system (HES) to a light water reactor (LWR). The two PRA models are for a pressurized-water reactor (PWR) and a boiling water reactor (BWR), respectively. The introduction of a HES has the goal of providing heat that would normally be wasted to be used for new revenue generation through processes such as making hydrogen. This HES module feeds process heat to a High Temperature Electrolysis Facility (HTEF). The PRAs used in this assessment of the HES are generic, and therefore some assumptions are made to preserve generality. A Failure Mode and Effects Analysis (FMEA) was performed to identify and screen the possible hazards due to the addition of the hydrogen production system. Hydrogen cloud and high-pressure jet detonation events were studied in relation to their contribution to components/structures fragility. A sensitivity analysis was performed to investigate the effect of several HES design options and distance to the nuclear reactor complex. The results of the PRA indicate that application using the U.S. licensing approach in 10 CFR 50.59 is justified because the increase in initiating event frequencies for all design basis accidents (DBAs) is within limits. The PRA results for core damage frequency (CDF) support the use of U.S. Nuclear Regulatory Commission Regulatory Guide 1.174 as further risk information that supports a change to the plant. Further insights provided through hazard analysis and sensitivity studies suggest that the addition of an HES module, and an HTEF plant at a reasonable distance from the nuclear plant satisfies safety and licensing requirements. Note that unique site-specific information may alter these conclusions.

Paper KU224 Preview

Author and Presentation Info

Lead Author Name: Kurt Vedros (kurt.vedros@inl.gov)

Bio: Kurt is a lead risk assessment engineer with Idaho National Laboratory's Nuclear Science and Technology division's Reliability, Risk, and Resilience Sciences Group. Kurt has over 25 years of experience in reliability and risk engineering. His research areas of interest are in static and dynamic probabilistic risk assessment of advanced reactors and in support of sustainability improvements for existing nuclear power plants, power analysis-informed PRA of electrical grids, development of community chemical risk assessment techniques, Bayesian parameter estimations, and external environmental event hazards assessment. He has a Bachelor of Science in Nuclear Engineering from Idaho State University and reliability institutes from University of Arizona.

Country: ---
Company: Idaho National Laboratory
Job Title: Lead Risk Assessment Engineer

PSAM 16 Conference Paper Overview

Welcome to the PSAM 16 Conference paper and speaker overview page.

Paper KU224 Preview

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