PSAM 16 - Session T04 Overview

PSAM 16 Conference Session T04 Overview

Session Chair: Richard Boardman (richard.boardman@inl.gov)

Paper 1 RI309

Lead Author: Tyler Westover Co-author(s): Richard Boardman; Stephen Hancock

Presenter of this paper: Kurt Vedros (kurt.vedros@inl.gov)

Thermal and Electrical Coupling to Electrolysis Plants
Close coupling of nuclear and electrolysis plants requires modifications of the power transmission station to take advantage of the low-cost, clean electricity produced by nuclear plants. In addition, high-temperature electrolysis can reduce the cost of electrolysis when the steam produced by nuclear plants is used to heat and produce steam for electrolysis. RELAP and HYSYS models provided the basis for preliminary hydrogen production studies. This work supports a conceptual architectural engineering design of the thermal energy delivery systems. Understanding the thermal and electrical interfaces is essential for PRAs and ensuring the safety of plant operations and protection and stability of the power systems and reactor core.

Thermal and Electrical Coupling to Electrolysis Plants

Close coupling of nuclear and electrolysis plants requires modifications of the power transmission station to take advantage of the low-cost, clean electricity produced by nuclear plants. In addition, high-temperature electrolysis can reduce the cost of electrolysis when the steam produced by nuclear plants is used to heat and produce steam for electrolysis. RELAP and HYSYS models provided the basis for preliminary hydrogen production studies. This work supports a conceptual architectural engineering design of the thermal energy delivery systems. Understanding the thermal and electrical interfaces is essential for PRAs and ensuring the safety of plant operations and protection and stability of the power systems and reactor core.

Paper RI309 | Download the paper file. | Download the presentation PowerPoint file.

A PSAM Profile is not yet available for this author.
Presenter 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

Paper 2 KU224

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 | Download the paper file. | Download the presentation PowerPoint file.

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

Paper 3 RI313

Lead Author: Richard Boardman Co-author(s): S. Jason Remer- Sherman.Remer@inl.gov; Jack Cadogan, Tyler Westover Tyler.Westover@inl.gov, (CERTREC authors to be added)

Hydrogen Regulatory Research Review Group
The formation of the Hydrogen Regulatory Research Review Group (H3RG) is a natural out-growth of feedback and discussions from ongoing LWRS Flexible Plant Operations and Generation Stakeholder meetings. The role of the H3RG is to identify licensing considerations in support of practical nuclear fleet integration with high temperature electrolysis. This collaboration engages expertise from; DOE supported national laboratories, independent R&D organizations, electric utility licensing personnel, nuclear architect engineering firms, Advanced Reactor Demonstration Program (ARDP) applicants, and hydrogen vendor research organizations. The primary objective of the H3RG is 2022 is to identify licensing approaches (based on traditional Nuclear Regulatory Commission (NRC) requirements) to introduce hydrogen production by HTE as an alternate energy stream at nuclear facilities.

Hydrogen Regulatory Research Review Group

The formation of the Hydrogen Regulatory Research Review Group (H3RG) is a natural out-growth of feedback and discussions from ongoing LWRS Flexible Plant Operations and Generation Stakeholder meetings. The role of the H3RG is to identify licensing considerations in support of practical nuclear fleet integration with high temperature electrolysis. This collaboration engages expertise from; DOE supported national laboratories, independent R&D organizations, electric utility licensing personnel, nuclear architect engineering firms, Advanced Reactor Demonstration Program (ARDP) applicants, and hydrogen vendor research organizations. The primary objective of the H3RG is 2022 is to identify licensing approaches (based on traditional Nuclear Regulatory Commission (NRC) requirements) to introduce hydrogen production by HTE as an alternate energy stream at nuclear facilities.

Paper RI313 | | Download the presentation pdf file.

Name: Richard Boardman (Richard.Boardman@inl.gov)

Bio: Richard Boardman has a doctorate degree in Chemical Engineering. He currently leads the Light Water Reactor Sustainability pathway for development of Flexible Plant Operation and Generation. He is also the INL Lab Relationship Manger to the Hydrogen and Fuel Cell Technology Office. Since joining the Idaho National Laboratory in 1990, Dr. Boardman has led several technology and process development projects related to hydrogen production, nuclear heat integration with chemical processes, coal and biomass gasification, biopower, and pollutant control.

Country: USA
Company: Idaho National Laboratory
Job Title: Directorate Fellow

Paper 4 RI311

Lead Author: Austin Glover Co-author(s): Kurt Vedros- Kurt.Vedros@inl.gov; Austin Glover- amglove@sandia.gov; Courtney Otani- Courtney.Otani@inl.gov

Assessment of Hydrogen Plant Risks For Siting Near Nuclear Power Plants
An underlying basis for the PRA of a nuclear plant that is connected to a hydrogen plant is understanding the safety risks associated with hydrogen production, storage, and pipeline infrastructure that is located in close proximity. Sandia National Laboratory has used historical data to provide relevant accident scenarios and frequencies. In addition, potential hazards associated with local hydrogen leaks, flames, and explosion scenarios have been evaluated to determine the impact on the nuclear plant facility and related power systems and other plant targets. The outcomes for a large-scale hydrogen product within 0.5 to 1.0 kilometers has been evaluated. The minimum separation distance of the HTEF is calculated based on the target fragility criteria of 1 psi defined in Regulatory Guide 1.91.

Assessment of Hydrogen Plant Risks For Siting Near Nuclear Power Plants

An underlying basis for the PRA of a nuclear plant that is connected to a hydrogen plant is understanding the safety risks associated with hydrogen production, storage, and pipeline infrastructure that is located in close proximity. Sandia National Laboratory has used historical data to provide relevant accident scenarios and frequencies. In addition, potential hazards associated with local hydrogen leaks, flames, and explosion scenarios have been evaluated to determine the impact on the nuclear plant facility and related power systems and other plant targets. The outcomes for a large-scale hydrogen product within 0.5 to 1.0 kilometers has been evaluated. The minimum separation distance of the HTEF is calculated based on the target fragility criteria of 1 psi defined in Regulatory Guide 1.91.

Paper RI311 | Download the paper file. | Download the presentation PowerPoint file.

Name: Austin Glover (amglove@sandia.gov)

Bio: Austin Glover is a mechanical engineer at Sandia National Laboratories. He has experience in performing risk assessment of hydrogen infrastructure, nuclear power plants, and natural gas and hydrogen blending applications. Additionally, he has experience in reviewing safety codes and standards to identify gaps in application to blended gas systems.

Country: USA
Company: Sandia National Laboratories
Job Title: Mechanical Engineer