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Assessing the Impact of the Inflation Reduction Act on Nuclear Plant Power Uprate and Hydrogen Cogeneration, INL/RPT-23-7468129683501 - Power UprateThis project researched the feasibility of increasing power output by existing nuclear power plants and demonstrated expected benefits via several case studies. The research has demonstrated that 1) incentives in the Inflation Reduction Act are highly beneficial for existing operating plants to support power uprates, and 2) the added power could be used to increase and diversify plant revenue by using the new power for electricity generation, clean hydrogen generation, or a combination of both. This project researched the feasibility of increasing power output by existing nuclear power plants and demonstrated expected benefits via several case studies. The research has demonstrated that 1) incentives in the Inflation Reduction Act are highly beneficial for existing operating plants to support power uprates, and 2) the added power could be used to increase and diversify plant revenue by using the new power for electricity generation, clean hydrogen generation, or a combination of both. 11/20/2023 2:28:10 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government As a result, the process and 398https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-28T06:00:00Z
Pressurized-Water Reactor Core Design Demonstration with Genetic Algorithm Based Multi-Objective Plant Fuel Reload Optimization Platform, INL/RPT-23-7449828804402 - Plant Fuel Reload OptimizationThis report summarizes development and demonstration activities of the Plant Reload Optimization (PRLO) platform which aims to provide optimized core design solution during fuel reloading by using artificial intelligence technology. During FY23, the project focused on the improvement of the platform by implying multiobjective and multiphysics problem solver to handle large size of objectives and constraints and its demonstration. The platform is now fully capable to produce optimized nuclear reactor core design along with the system safety and fuel performance analysis results which are required for the licensing during fuel reloading. This report summarizes development and demonstration activities of the Plant Reload Optimization (PRLO) platform which aims to provide optimized core design solution during fuel reloading by using artificial intelligence technology. During FY23, the project focused on the improvement of the platform by implying multiobjective and multiphysics problem solver to handle large size of objectives and constraints and its demonstration. The platform is now fully capable to produce optimized nuclear reactor core design along with the system safety and fuel performance analysis results which are required for the licensing during fuel reloading. 9/13/2023 10:23:21 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government 127https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-14T06:00:00Z
Development of Genetic Algorithm Based Multi-Objective Plant Reload Optimization Platform, INL/RPT-23-716671156102 - Plant Fuel Reload OptimizationThe purpose of this report is to develop and demonstrate artificial intelligence (i.e., Genetic Algorithm) based nuclear reactor fuel reloading optimization platform by integrating the non-dominated sorting genetic algorithm II (NSGA-II). This allowed solving the multi-objective optimization framework for realistic plant reload optimization problem with improved termination criteria, constraints handling and active subspaces. Demonstrations were performed with verification test and benchmark case. The purpose of this report is to develop and demonstrate artificial intelligence (i.e., Genetic Algorithm) based nuclear reactor fuel reloading optimization platform by integrating the non-dominated sorting genetic algorithm II (NSGA-II). This allowed solving the multi-objective optimization framework for realistic plant reload optimization problem with improved termination criteria, constraints handling and active subspaces. Demonstrations were performed with verification test and benchmark case. 3/27/2023 3:53:00 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government It is challenging to create a 203https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-03-27T06:00:00Z
Development of Plant Reload Optimization Platform Capabilities for Core Design and Fuel Performance Analysis, INL/RPT-22-7038226918402 - Plant Fuel Reload OptimizationThe Plant Reload Optimization Platform development project aims to build a reactor core design tool that includes reactor safety and fuel performance analyses, and also uses artificial intelligence to support optimization of core design solutions.The Plant Reload Optimization Platform development project aims to build a reactor core design tool that includes reactor safety and fuel performance analyses, and also uses artificial intelligence to support optimization of core design solutions.12/14/2022 2:46:26 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The LWRS Program promotes a wide 221https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-12-31T07:00:00Z
Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis, INL/RPT-22-686285348902 - Plant Fuel Reload OptimizationDevelopment and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis.Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis.8/22/2022 9:13:14 PMINL/RPT-22-68628 Light Water Reactor Sustainability Program Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis August 259https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-08-22T06:00:00Z
Demonstration of the Plant Fuel Reload Process Optimization for an Operating PWR, INL/EXT-21-6454923476902 - Plant Fuel Reload OptimizationThis report summarizes the research outcomes in FY-2021, which the project progressed from the planning and methodology development phase to the early demonstration phase.This report summarizes the research outcomes in FY-2021, which the project progressed from the planning and methodology development phase to the early demonstration phase.9/29/2021 4:12:16 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The LWRS Program is promoting a 421https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-09-30T06:00:00Z
RISA Plant Reload Process Optimization: Development of design basis accident methods for plant reload license optimization, INL/EXT-20-5961419954402 - Plant Fuel Reload OptimizationRISA Plant Reload Process Optimization: Development of design basis accident methods for plant reload license optimization, INL/EXT-20-59614RISA Plant Reload Process Optimization: Development of design basis accident methods for plant reload license optimization, INL/EXT-20-596149/1/2020 2:01:12 AMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Safety is a key parameter to all 415https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-08-09T06:00:00Z
Application of Margin-Based Methods to Assess System Health, INL/RPT-22-7036127455403 - Risk-Informed Plant Health and Asset ManagementHealth management of complex systems such as nuclear power plants is an essential task to guarantee system reliability. This task can be greatly enhanced by constantly monitoring asset status/performances, and processing such data (through anomaly detection, diagnostic, and prognostic computational algorithms) to identify asset degradation trends and faulty states.Health management of complex systems such as nuclear power plants is an essential task to guarantee system reliability. This task can be greatly enhanced by constantly monitoring asset status/performances, and processing such data (through anomaly detection, diagnostic, and prognostic computational algorithms) to identify asset degradation trends and faulty states.12/16/2022 1:56:48 AMINL/RPT-22-70361 Light Water Reactor Sustainability Program Application of Margin-Based Methods to Assess System Health December 2022 U.S. Department of Energy Office of Nuclear 167https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-12-15T07:00:00Z
Bridging Equipment Reliability Data and Robust Decisions in a Plant Operation Context, INL/RPT-22-6767018601303 - Risk-Informed Plant Health and Asset ManagementThis report shows the latest improvements on the three main research areas that the risk-informed asset management project is focusing on: equipment reliability data analytics, system reliability modeling, and plant resource optimization methods. It is discussed in the report how the methods developed in these areas can support predictive maintenance strategies by identifying the most critical components and setting an optimal maintenance schedule based on plant economic and operational constraints.This report shows the latest improvements on the three main research areas that the risk-informed asset management project is focusing on: equipment reliability data analytics, system reliability modeling, and plant resource optimization methods. It is discussed in the report how the methods developed in these areas can support predictive maintenance strategies by identifying the most critical components and setting an optimal maintenance schedule based on plant economic and operational constraints.9/7/2022 1:55:39 PMINL-RPT-22-67670 Light Water Reactor Sustainability Program Bridging Equipment Reliability Data and Robust Decisions in a Plant Operation Context June 2022 U.S. Department of 175https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-06-07T06:00:00Z
Industry Use Cases for Risk-Informed System Health and Asset Management, INL/EXT-21-6437723474603 - Risk-Informed Plant Health and Asset ManagementIndustry Use Cases for Risk-Informed System Health and Asset Management, INL-EXT-21-64377Industry Use Cases for Risk-Informed System Health and Asset Management, INL-EXT-21-643779/29/2021 11:54:49 PMINL-EXT-21-64377 Light Water Reactor Sustainability Program Industry Use Cases for Risk-Informed System Health and Asset Management September 2021 U.S. Department of Energy 399https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-09-29T06:00:00Z
Development and Release of the Methods and Tools for Risk-Informed Asset Management, INL/EXT-21-6325515263503 - Risk-Informed Plant Health and Asset ManagementDevelopment and Release of the Methods and Tools for Risk-Informed Asset Management, INL/EXT-21-63255Development and Release of the Methods and Tools for Risk-Informed Asset Management, INL/EXT-21-632558/25/2021 2:48:40 PMINL/EXT-21-63255 Light Water Reactor Sustainability Program Development and Release of the Methods and Tools for Risk-Informed Asset Management July 2021 U.S. Department of 405https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-07-26T06:00:00Z
Development and Application of a Risk Analysis Toolkit for Plant Resources Optimization, INL/EXT-20-5994220047403 - Risk-Informed Plant Health and Asset ManagementDevelopment and Application of a Risk Analysis Toolkit for Plant Resources Optimization, INL/EXT-20-5994Development and Application of a Risk Analysis Toolkit for Plant Resources Optimization, INL/EXT-20-599410/1/2020 1:12:06 AMINL/EXT-20-59942 Light Water Reactor Sustainability Program Development and Application of a Risk Analysis Toolkit for Plant Resources Optimization September 2020 U.S. 543https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Integration of Data Analytics with Plant System Health Program, INL/EXT-20-5992820047603 - Risk-Informed Plant Health and Asset ManagementIntegration of Data Analytics with Plant System Health Program, INL-EXT-20-59928Integration of Data Analytics with Plant System Health Program, INL-EXT-20-599289/29/2020 10:57:36 PMINL/EXT-20-59928 Light Water Reactor Sustainability Program Integration of Data Analytics with Plant System Health Program September 2020 U.S. Department of Energy Office 615https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Combined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement, INL/EXT-19-558195552403 - Risk-Informed Plant Health and Asset ManagementCombined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement, INL-EXT-19-55819Combined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement, INL-EXT-19-5581910/1/2019 3:49:39 AMINL-EXT-19-55819 Light Water Reactor Sustainability Program Combined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement September 427https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-09-21T06:00:00Z
Plant Integral Risk-informed System Health Program, INL/EXT-19-558085543603 - Risk-Informed Plant Health and Asset ManagementPlant Integral Risk-informed System Health Program, INL-EXT-19-55808Plant Integral Risk-informed System Health Program, INL-EXT-19-5580810/1/2019 8:01:50 AMINL-EXT-19-55808 Light Water Reactor Sustainability Program Plant Integral Risk-informed System Health Program September 2019 U.S. Department of Energy Office of Nuclear Energy 1023https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-09-20T06:00:00Z
CRAFT An Integrated Risk Analysis Tool and its Application in an Industry Use Case, INL/EXT-18-514425552503 - Risk-Informed Plant Health and Asset ManagementCost Risk Analysis Framework (CRAFT) An Integrated Risk Analysis Tool and its Application in an Industry Use Case, INL/EXT-18-51442Cost Risk Analysis Framework (CRAFT) An Integrated Risk Analysis Tool and its Application in an Industry Use Case, INL/EXT-18-5144210/1/2018 3:13:15 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government D. Mandelli, C. Wang, S. Staples 231https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2018-09-26T06:00:00Z
Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-398515541003 - Risk-Informed Plant Health and Asset ManagementData Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-39851Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-3985110/6/2016 2:09:54 PMINL/EXT-16-39851 Light Water Reactor Sustainability Program Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit September 2016 DOE Office of 266https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2016-09-01T06:00:00Z
Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, INL/EXT-15-359335591303 - Risk-Informed Plant Health and Asset ManagementImproved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, INL-EXT-15-35933Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, INL-EXT-15-3593310/5/2015 4:51:24 PMINL/EXT-15-35933 Revision 0 Light Water Reactor Sustainability Program Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit August 2015 DOE 247https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2015-08-01T06:00:00Z
Technical Language Processing of Nuclear Power Plants Equipment Reliability Data16012203 - Risk-Informed Plant Health and Asset managementNuclear power plants produce a large amount of equipment reliability data during their regular maintenance operations. Using this data, this newly-developed methodology first cleans up this information and then uses customized technical natural language processing, a type of machine learning, to identify the physical asset, like a pump or motor, a specific phenomenon happening in that asset, like a cracked valve, and what the likely effects will be.Nuclear power plants produce a large amount of equipment reliability data during their regular maintenance operations. Using this data, this newly-developed methodology first cleans up this information and then uses customized technical natural language processing, a type of machine learning, to identify the physical asset, like a pump or motor, a specific phenomenon happening in that asset, like a cracked valve, and what the likely effects will be.5/15/2024 8:08:47 PMhttps://doi.org/ 10.3390/en17071785 Academic Editor: Dan Gabriel Cacuci Received: 1 February 2024 Revised: 19 March 2024 Accepted: 1 April 2024 Published: 8 April 2024 Copyright 10https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2024-05-15T06:00:00Z
Development of Analysis Methods that Integrate Numeric and Textual Equipment Reliability Data, INL/RPT-23-7453011097503 - Risk-Informed Plant Health and Asset managementIn this report we show in detail how the integration and reasoning from numeric and textual ER data elements is performed. First, we present the developed library of MBSE models that focus on common NPP systems and assets. Then we show the development of computational methods designed to process and analyze numeric and textual ER data elements simultaneously.In this report we show in detail how the integration and reasoning from numeric and textual ER data elements is performed. First, we present the developed library of MBSE models that focus on common NPP systems and assets. Then we show the development of computational methods designed to process and analyze numeric and textual ER data elements simultaneously.9/16/2023 5:31:06 AMINL/RPT-23-74530 Light Water Reactor Sustainability Program Development of Analysis Methods that Integrate Numeric and Textual Equipment Reliability Data September 2023 U.S. 116https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-05T06:00:00Z
An Integrated Framework for Risk Assessment of Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology Refinement and Exploration, INL/RPT-23-7441228868004 - Integrated Risk Assessment for Digital Instrumentation and ControlIn FY 2023, this project focused on enhancing software common cause failure (CCF) modeling and risk assessment methods for digital instrumentation and control (DI&C) systems. The goal is to strengthen the methodology for assessing safety-related DI&C systems. The proposed framework and methods have been refined through feedback from industrial partners and previous technical peer reviews. A modification to the CCF approach within the proposed framework improves its ability to model and evaluate software CCFs in diverse DI&C systems.In FY 2023, this project focused on enhancing software common cause failure (CCF) modeling and risk assessment methods for digital instrumentation and control (DI&C) systems. The goal is to strengthen the methodology for assessing safety-related DI&C systems. The proposed framework and methods have been refined through feedback from industrial partners and previous technical peer reviews. A modification to the CCF approach within the proposed framework improves its ability to model and evaluate software CCFs in diverse DI&C systems.9/14/2023 9:51:58 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Han Bao 1 , Tate Shorthill 2 154https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-15T06:00:00Z
Summary of Technical Peer Review on the Risk Assessment Framework proposed in Report INL/RPT-22-68656 for Digital Instrumentation and Control Systems, INL/RPT-23-7169929297204 - Integrated Risk Assessment for Digital Instrumentation and ControlThe objective of this technical peer review is to obtain representative feedback on the proposed framework to improve the technical qualities of its methodology and readiness for deployment to the industry. Feedback may identify potential areas for improvement and further development. The subject-matter experts were invited to review the latest project report documenting the methodology developed in the project and provide evaluations of the technical qualities of the proposed framework and relevant methods.The objective of this technical peer review is to obtain representative feedback on the proposed framework to improve the technical qualities of its methodology and readiness for deployment to the industry. Feedback may identify potential areas for improvement and further development. The subject-matter experts were invited to review the latest project report documenting the methodology developed in the project and provide evaluations of the technical qualities of the proposed framework and relevant methods.4/13/2023 2:50:27 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Han Bao 1 , Tate Shorthill 2 168https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-04-27T06:00:00Z
Risk Analysis of Various Design Architectures for High Safety-Significant Safety-Related Digital Instrumentation and Control Systems of Nuclear Power Plants During Accident Scenarios, INL/RPT-22-7005623525204 - Integrated Risk Assessment for Digital Instrumentation and ControlIn FY 2019, the RISA Pathway initiated a project to develop a risk assessment strategy for delivering a technical basis to support effective and secure DI&C technologies for digital upgrades/designsIn FY 2019, the RISA Pathway initiated a project to develop a risk assessment strategy for delivering a technical basis to support effective and secure DI&C technologies for digital upgrades/designs1/24/2023 4:07:05 AMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Han Bao 1 , Sai Zhang 1 , Robert 157https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-11-24T07:00:00Z
An Integrated Framework for Risk Assessment of High Safety-Significant Safety-Related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration, INL/RPT-22-686565348704 - Integrated Risk Assessment for Digital Instrumentation and ControlAn Integrated Framework for Risk Assessment of High Safety-significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration.An Integrated Framework for Risk Assessment of High Safety-significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration.1/24/2023 8:01:03 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Han Bao 1 , Tate Shorthill 2 339https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-09-20T06:00:00Z
Quantitative Risk Analysis of High Safety significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants using IRADIC Technology, INL/EXT-21-6403923156404 - Integrated Risk Assessment for Digital Instrumentation and ControlQuantitative Risk Analysis of High Safety significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants using IRADIC Technology, INL/EXT-21-64039Quantitative Risk Analysis of High Safety significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants using IRADIC Technology, INL/EXT-21-640398/31/2021 3:22:07 AMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Han Bao 1 , Tate Shorthill 2 469https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-08-31T06:00:00Z
Redundancy-guided System-theoretic Hazard and Reliability Analysis of Safety related Digital Instrumentation and Control Systems in Nuclear Power Plants, INL/EXT-20-5955019953704 - Integrated Risk Assessment for Digital Instrumentation and ControlRedundancy-guided System-theoretic Hazard and Reliability Analysis of Safety related Digital Instrumentation and Control Systems in Nuclear Power Plants, INL/EXT-20-59550Redundancy-guided System-theoretic Hazard and Reliability Analysis of Safety related Digital Instrumentation and Control Systems in Nuclear Power Plants, INL/EXT-20-595508/26/2020 9:04:58 PMHan Bao, Tate Shorthill, Hongbin Zhang U.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. 779https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-08-15T06:00:00Z
An Integrated Risk Assessment Process for Digital Instrumentation and Control Upgrades of Nuclear Power Plants, INL/EXT-19-552195577004 - Integrated Risk Assessment for Digital Instrumentation and ControlAn Integrated Risk Assessment Process for Digital Instrumentation and Control Upgrades of Nuclear Power Plants, INL/EXT-19-55219An Integrated Risk Assessment Process for Digital Instrumentation and Control Upgrades of Nuclear Power Plants, INL/EXT-19-552198/29/2019 6:33:21 PMINL/EXT-19-55219 Light Water Reactor Sustainability Program An Integrated Risk Assessment Process for Digital Instrumentation and Control Upgrades of Nuclear Power Plants Han 637https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-08-01T06:00:00Z
Methods and Feature Enhancements for Industry Use of EMRALD, INL/RPT-23-7444728006805 - Dynamic Risk AssessmentEMRALD is a dynamic PRA tool developed by the Idaho National Laboratory. It is an open-source tool that has been used for many research projects along with more recent academic and industry projects. To expand for more industry use and analysis, a strong validation framework and test cases needed to be developed. Also, additional features needed to be added to enable some scenarios and ease of use. This report goes over the initial validation framework setup and testcase as well as the software modification from this project.EMRALD is a dynamic PRA tool developed by the Idaho National Laboratory. It is an open-source tool that has been used for many research projects along with more recent academic and industry projects. To expand for more industry use and analysis, a strong validation framework and test cases needed to be developed. Also, additional features needed to be added to enable some scenarios and ease of use. This report goes over the initial validation framework setup and testcase as well as the software modification from this project.9/6/2023 10:17:45 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government It is an open-source tool that 131https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-06T06:00:00Z
Dynamic and Classical PRA Coupling using EMRALD and SAPHIRE, INL/RPT-22-7042427454805 - Dynamic Risk AssessmentBoth classical and dynamic probabilistic risk assessment tools are valuable for different kinds of analysis. Typically, one or the other is used depending on the scenario and the limitations of the tool. Often, the results of one are used as a parameter in the other. This research looks at the possible methods for combining classical and dynamic analyses by coupling EMRALD and SAPHIRE. This was initial exploratory research to evaluate methods and determine how the tools could be coupled.Both classical and dynamic probabilistic risk assessment tools are valuable for different kinds of analysis. Typically, one or the other is used depending on the scenario and the limitations of the tool. Often, the results of one are used as a parameter in the other. This research looks at the possible methods for combining classical and dynamic analyses by coupling EMRALD and SAPHIRE. This was initial exploratory research to evaluate methods and determine how the tools could be coupled.12/15/2022 11:38:54 PMINL/RPT-22-70424 Revision 0 Light Water Reactor Sustainability Program Dynamic and Classical PRA Coupling using EMRALD and SAPHIRE December 2022 U.S. Department of Energy Office 176https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-12-15T07:00:00Z
Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-6433322138505 - Dynamic Risk AssessmentIntegration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-643339/8/2021 5:20:28 PMINL/EXT-21-64333 Revision 0 Light Water Reactor Sustainability Program Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework August 2021 214https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-08-16T06:00:00Z
Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-5989122125905 - Dynamic Risk AssessmentMethodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-598919/30/2020 9:58:38 PMINL/EXT-20-59891 Light Water Reactor Sustainability Program Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling September 2020 139https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-09-04T06:00:00Z
Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-5951022138205 - Dynamic Risk AssessmentIntegration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-595108/27/2020 1:15:47 AMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Labor costs continue to rise in 212https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-08-04T06:00:00Z
Status of Adaptive Surrogates within the RAVEN Framework, INL/EXT-17-4343826929905 - Dynamic Risk AssessmentThe RAVEN code has been under development at the Idaho National Laboratory since 2012. Its main goal is to create a multi-purpose platform for the deploying of all the capabilities needed for Probabilistic Risk Assessment, uncertainty quantification, data mining analysis and optimization studies.The RAVEN code has been under development at the Idaho National Laboratory since 2012. Its main goal is to create a multi-purpose platform for the deploying of all the capabilities needed for Probabilistic Risk Assessment, uncertainty quantification, data mining analysis and optimization studies.11/6/2017 9:29:14 PMINL/EXT-17-43438 Light Water Reactor Sustainability Program Status of Adaptive Surrogates within the RAVEN framework Andrea Alfonsi, Congjian Wang, Joshua Cogliati, Diego 82https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2017-09-20T06:00:00Z
A Simulation Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, INL/EXT-17-4092822140005 - Dynamic Risk AssessmentA Simulation-Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, RIL 2022-03 INL/EXT-17 40928A Simulation-Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, RIL 2022-03 INL/EXT-17 409284/29/2022 4:04:31 PMResearch Information Letter Office of Nuclear Regulatory Research This report was prepared as Idaho National Laboratory Report 115https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2017-02-22T07:00:00Z
System Reliability Analysis Capability and Surrogate Model Application in RAVEN, INL/EXT-16-3724326930005 - Dynamic Risk AssessmentThis report describes the effort performed to improve the analysis capabilities of the RAVEN code. These efforts include improving the reliability (or “limit”) surface search of the RAVEN code and exploring new opportunities in usage of surrogate models by extending the current RAVEN capabilities to multi-physics surrogate models construction for high-dimensionality problems.This report describes the effort performed to improve the analysis capabilities of the RAVEN code. These efforts include improving the reliability (or “limit”) surface search of the RAVEN code and exploring new opportunities in usage of surrogate models by extending the current RAVEN capabilities to multi-physics surrogate models construction for high-dimensionality problems.7/27/2017 8:30:18 PMINL/EXT-16-37243 Light Water Reactor Sustainability Program System Reliability Analysis Capability and Surrogate Model Application in RAVEN Cristian Rabiti, Andrea Alfonsi 102https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2015-11-13T07:00:00Z
Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-3249126930205 - Dynamic Risk AssessmentAdvanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-324918/17/2015 8:43:08 PM7KH,1/LVD86'HSDUWPHQWRI(QHUJ\1DWLRQDO/DERUDWRU\ RSHUDWHGE\%DWWHOOH(QHUJ\$OOLDQFH ,1/(;7 Advanced Probabilistic Risk Analysis Using RAVEN and RELAP-7 115https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2014-06-26T06:00:00Z
Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN, INL/EXT-13-3020326930305 - Dynamic Risk AssessmentThe existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impact of these two factors on the safety of the plant, the RISMC project aims to provide insight to decision-makers through a series of simulations of the plant dynamics for different initial conditions.The existing fleet of nuclear power plants is in the process of extending its lifetime and increasing the power generated from these plants via power uprates. In order to evaluate the impact of these two factors on the safety of the plant, the RISMC project aims to provide insight to decision-makers through a series of simulations of the plant dynamics for different initial conditions.12/20/2013 4:26:24 PMThe INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-13-30203 Light Water Reactor Sustainability Program Support and Modeling 142https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2013-09-20T06:00:00Z
Reactor analysis and virtual control environment (RAVEN) FY12, INL/EXT-12-2735126930405 - Dynamic Risk AssessmentRAVEN is a complex software tool that has functionality spanning from being the RELAP-7 user interface, to using RELAP-7 to perform Risk Informed Safety Characterization (RISMC), and to controlling RELAP-7 calculation execution.RAVEN is a complex software tool that has functionality spanning from being the RELAP-7 user interface, to using RELAP-7 to perform Risk Informed Safety Characterization (RISMC), and to controlling RELAP-7 calculation execution.10/8/2012 9:42:12 PMThe INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-12-27351 Reactor Analysis and Virtual Control Environment (RAVEN) FY12 111https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2012-09-02T06:00:00Z
Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup for PWRs, INL/RPT-24-772036068506 - Enhanced Resilient Plant SystemsThis report documents research and development conducted in support of deploying accident-tolerant fuels. Specifically, the performance of chromium coating during a beyond design basis accident was investigated. An 18-month reference core was considered, and the performance of cases with and without chromium coating was compared. An extended cycle length of 24-month was then considered with the chromium coating to determine whether the benefit of using the chromium coating was more or less significant than the increased fission product inventory when considering fission product release. The results show there is a significant reduction in the oxidation, leading to a reduction in the heat released, which results in the reduction of the overall core damage.This report documents research and development conducted in support of deploying accident-tolerant fuels. Specifically, the performance of chromium coating during a beyond design basis accident was investigated. An 18-month reference core was considered, and the performance of cases with and without chromium coating was compared. An extended cycle length of 24-month was then considered with the chromium coating to determine whether the benefit of using the chromium coating was more or less significant than the increased fission product inventory when considering fission product release. The results show there is a significant reduction in the oxidation, leading to a reduction in the heat released, which results in the reduction of the overall core damage.3/26/2024 10:28:34 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government This program is promoting a wide 116https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2024-03-27T06:00:00Z
Safety Analysis of FeCrAl Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup for PWR, INL/RPT-23-7473127088606 - Enhanced Resilient Plant SystemsAs part of this pathway, the Enhanced Resilient Plant project refers to an NPP where safety is improved by implementing various measures, such as accident-tolerant fuels, diverse and flexible coping strategies, enhancements to plant components and systems, incorporation of augmented or new passive cooling systems, and utilization of advanced battery technologies. As part of this pathway, the Enhanced Resilient Plant project refers to an NPP where safety is improved by implementing various measures, such as accident-tolerant fuels, diverse and flexible coping strategies, enhancements to plant components and systems, incorporation of augmented or new passive cooling systems, and utilization of advanced battery technologies. 10/12/2023 10:32:48 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government This program is promoting a wide 106https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-09-27T06:00:00Z
Assessment of Modeling and Simulation Technical Gaps in Safety Analysis of High-Burnup Accident-Tolerant Fuels, INL/RPT-23-7084426044806 - Enhanced Resilient Plant SystemsMany U.S. utilities are targeting implementation of ATFs instead of traditional fuel in the near future since ATFs offer benefits in terms of improved performance and cost savings. The robust properties of ATF make it possible to extend the refueling cycle from 18 to 24 months in addition to the opportunity to use less of fuel.Many U.S. utilities are targeting implementation of ATFs instead of traditional fuel in the near future since ATFs offer benefits in terms of improved performance and cost savings. The robust properties of ATF make it possible to extend the refueling cycle from 18 to 24 months in addition to the opportunity to use less of fuel.1/30/2023 3:26:43 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The LWRS Program is promoting a 395https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2023-01-30T07:00:00Z
Safety Analysis for Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup, INL/RPT-22--6858127333706 - Enhanced Resilient Plant SystemsThe ERP R&D efforts in fiscal year (FY) 2022 focused on safety analyses of ATFs with increased enrichment and extended burnup to provide scientific knowledge of the ATF fuel performance, failure mechanisms, and resulting from fuel failure source terms during a severe accident, INL/RPT-22--68581The ERP R&D efforts in fiscal year (FY) 2022 focused on safety analyses of ATFs with increased enrichment and extended burnup to provide scientific knowledge of the ATF fuel performance, failure mechanisms, and resulting from fuel failure source terms during a severe accident, INL/RPT-22--685813/9/2023 3:45:50 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The LWRS Program is promoting a 109https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2022-08-14T06:00:00Z
Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-6454623475806 - Enhanced Resilient Plant SystemsRisk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-64546Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-645469/29/2021 6:47:28 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The purpose of the RISA Pathway 459https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2021-09-28T06:00:00Z
Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-5990620524206 - Enhanced Resilient Plant SystemsRisk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-59906Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-599064/13/2021 7:16:42 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The purpose of the RISA Pathway 203https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-09-29T06:00:00Z
Development of RELAP5-3D Modeling of RCIC System, INL/EXT-20-5981920047706 - Enhanced Resilient Plant SystemsDevelopment of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System, INL/EXT-20-59819Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System, INL/EXT-20-598199/29/2020 11:58:47 PMINL/EXT-20-59819 Light Water Reactor Sustainability Program Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System September 2020 U.S. 537https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2020-09-21T06:00:00Z
Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-562155541706 - Enhanced Resilient Plant SystemsEvaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-56215Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-5621510/30/2019 7:16:46 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Zhegang Ma 1 , Cliff Davis 1 457https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-10-17T06:00:00Z
Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-558885542106 - Enhanced Resilient Plant SystemsFuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-55888Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-558889/30/2019 6:50:04 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government Hongbin Zhang 1 , Cole Blakely 1 921https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-09-20T06:00:00Z
Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling, INL/EXT-19-535565537206 - Enhanced Resilient Plant SystemsRisk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling, INL/EXT-19-53556Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling, INL/EXT-19-535568/29/2019 5:17:59 PMU.S. Department of Energy Office of Nuclear Energy This information was prepared as an account of work sponsored by an agency of the U.S. Government The purpose of the RISA Pathway 550https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2019-08-29T06:00:00Z
Industry Application ECCS/LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model, INL/EXT-17-424615542506 - Enhanced Resilient Plant SystemsIndustry Application ECCS/LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model, INL/EXT-17-42461Industry Application ECCS/LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of LOTUS-Baseline Coupled Analysis of the South Texas Plant Model, INL/EXT-17-424617/5/2017 9:31:54 PMINL/EXT-17-42461 Light Water Reactor Sustainability Program Industry Application ECCS / LOCA Integrated Cladding/Emergency Core Cooling System Performance: Demonstration of 232https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2017-06-18T06:00:00Z
Industry Application Emergency Core Cooling System Cladding Accept Criteria Problem Statement, INL/EXT-15-350735591106 - Enhanced Resilient Plant SystemsIndustry Application Emergency Core Cooling System Cladding Acceptance Criteria Problem Statement, INL/EXT-15-35073Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Problem Statement, INL/EXT-15-350734/30/2015 6:38:33 PMCesare Frepoli, Joseph P Yurko, Gregg Swindlehurst, Hongbin Zhang, Haihua Zhao, Paul D Bayless This information was prepared as an 57https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf2015-05-01T06:00:00Z