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 | | |
Assessment of Modeling and Simulation Technical Gaps in Safety Analysis of High-Burnup Accident-Tolerant Fuels, INL/RPT-23-70844 | 260448 | | 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. | 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 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 LWRS Program is promoting a | 31 | 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 | | |
Safety Analysis for Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup, INL/RPT-22--68581 | 273337 | | The 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--68581 | The 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--68581 | | 3/9/2023 3:45:50 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 LWRS Program is promoting a | 11 | 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 | | |
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 | | |
Development of RELAP5-3D Modeling of RCIC System, INL/EXT-20-59819 | 200477 | | Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System, INL/EXT-20-59819, H. Zhang, C. Blakley, September 2020. | Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System, INL/EXT-20-59819, H. Zhang, C. Blakley, September 2020. | | 9/29/2020 11:58:47 PM | INL/EXT-20-59819 Light Water Reactor Sustainability Program Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System September 2020 U.S. | 358 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-56215 | 55417 | | Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-56215 | Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-56215 | | 10/30/2019 7:16:46 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 Zhegang Ma 1 , Cliff Davis 1 | 322 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |
Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-55888 | 55421 | | Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-55888 | Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-55888 | | 9/30/2019 6:50:04 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 Hongbin Zhang 1 , Cole Blakely 1 | 590 | https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspx | pdf | False | pdf | | |