Development of Genetic Algorithm Based Multi-Objective Plant Reload Optimization Platform, INL/RPT-23-71667 | 11561 | | 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. | 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 PM | 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. Government It is challenging to create a | 2 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Application of Margin-Based Methods to Assess System Health, INL/RPT-22-70361 | 274554 | | 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. | 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 AM | INL/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 | 6 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
FRI3D Fire Simulation Options and Verification Tasks, INL/RPT-23-70843 | 265342 | | The Fire Risk Investigation in 3D (FRI3D) software was developed at the Idaho National Laboratory under the Risk-Informs System Analysis pathway under the Light Water Reactor Sustainability Program. This software combines the multiple tools used by industry for fire modeling with the plant risk analysis and 3D spatial information. | The Fire Risk Investigation in 3D (FRI3D) software was developed at the Idaho National Laboratory under the Risk-Informs System Analysis pathway under the Light Water Reactor Sustainability Program. This software combines the multiple tools used by industry for fire modeling with the plant risk analysis and 3D spatial information. | | 1/31/2023 3:00:41 PM | INL/RPT-23-70843 Revision 0 Light Water Reactor Sustainability Program FRI3D Fire Simulation Options and Verification Tasks January 2023 U.S. Department of Energy Office of | 45 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Dynamic and Classical PRA Coupling using EMRALD and SAPHIRE, INL/RPT-22-70424 | 274548 | | 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. A short background of SAPHIRE and its solving methods is provided, along with information on EMRALD to help understand the correlation between the two types of modeling. | 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. A short background of SAPHIRE and its solving methods is provided, along with information on EMRALD to help understand the correlation between the two types of modeling. | | 12/15/2022 11:38:54 PM | INL/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 | 6 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Industry Level Feasibility of LiDAR Data into FRI3D, INL/RPT-22-67714 | 247141 | | Industry Level Feasibility of LiDAR Data into Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) | Industry Level Feasibility of LiDAR Data into Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) | | 6/30/2022 4:11:54 PM | INL/RPT-22-67714 Light Water Reactor Sustainability Program Industry Level Feasibility of LiDAR Data into Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) June 2022 U.S. | 39 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-64546 | 234758 | | Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-64546 | Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-64546 | | 9/29/2021 6:47:28 PM | 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. Government The purpose of the RISA Pathway | 289 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-64214 | 221378 | | Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-64214 | Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-64214 | | 9/8/2021 9:36:04 PM | INL/EXT-21-64214 Revision 0 Light Water Reactor Sustainability Program Guidance Document for Using Dynamic Force-on-Force Tools September 2021 U.S. Department of Energy Office of | 89 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Industry Level Integrated FRI3D, INL/EXT-21-64079 | 231565 | | Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D), INL/EXT-21-6407 | Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D), INL/EXT-21-6407 | | 8/31/2021 10:47:33 PM | INL/EXT-21-604079 Light Water Reactor Sustainability Program Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D) August 2021 U.S. Department of | 240 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-59906 | 205242 | | Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-59906 | Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-59906 | | 4/13/2021 7:16:42 PM | 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. Government The purpose of the RISA Pathway | 92 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
FRI3D Tool and Methods Demonstration for Enhanced Fire Modeling, INL/EXT-20-59506 | 207591 | | Fire Risk Investigation in 3D (FRI3D) Tool and Methods Demonstration for Enhanced Fire Modeling, INL/EXT-20-59506 | Fire Risk Investigation in 3D (FRI3D) Tool and Methods Demonstration for Enhanced Fire Modeling, INL/EXT-20-59506 | | 9/22/2020 4:12:47 PM | Fire Risk Investigation in 3D (FRI3D) Software and Process for Integrated Fire Modeling This information was prepared as an account of work sponsored by an agency of the U.S. | 775 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |