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​​​​​​​​​​​​​​​​​​​​Enhanced Resilient Plant Systems


Goal

To develop methods for using risk and cost-benefit analyses that combine plant-resiliency technologies to enhance the economic, operational, and safety of light-water nuclear power reactors.

The plant-resiliency enhancement technologies considered in this project include accident-tolerant fuel (ATF) with fuel-burnup extension and increased enrichment, flexible mitigation strategies, new battery technologies and passive cooling for pressurized and boiling-water reactor designs

Outcome​

Researchers will produce a set of safety analyses based on combinations of plant-resiliency enhancement technologies to demonstrate approaches to safety margin management. The increase in safety margins will provide a basis for decision-makers to determine what enhancement strategies are most beneficial in terms of safety, operational flexibility, and plant economics.

Planned Major Accomplishments

  • ​2023—finalize analyses of various non-ELAP (extended loss of AC power) scenarios with various plant enhancements credited for mitigation. Develop industry guidance on how to credit plant enhancements for plant risk reduction. Complete and document risk-assessment methodology for ATF with higher enrichment and extended burnup.​

  • 2024—complete a pilot project to provide information that may be used by the industry to support their efforts in accident-tolerant fuel licensing that includes necessary safety analyses required for ATF regulatory approval.

Related Reports

 

 

Development of Genetic Algorithm Based Multi-Objective Plant Reload Optimization Platform, INL/RPT-23-7166711561The 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 2https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Assessment of Modeling and Simulation Technical Gaps in Safety Analysis of High-Burnup Accident-Tolerant Fuels, INL/RPT-23-70844260448Many 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 31https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Dynamic and Classical PRA Coupling using EMRALD and SAPHIRE, INL/RPT-22-70424274548Both 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 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 6https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Safety Analysis for Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup, INL/RPT-22--68581273337The 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 11https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Risk-Informed Analysis for Enhanced Resilient Nuclear Power Plant with Initiatives including ATF, FLEX, and Advanced Battery Technology, INL/EXT-21-64546234758Risk-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 289https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-64214221378Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-64214Guidance Document for Using Dynamic Force-on- Force Tools, INL/EXT-21-642149/8/2021 9:36:04 PMINL/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 89https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Risk-Informed ATF and FLEX Analysis for an Enhanced Resilient BWR Under Design-Basis and Beyond-Design-Basis Accidents, INL/EXT-20-59906205242Risk-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 92https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Development of RELAP5-3D Modeling of RCIC System, INL/EXT-20-59819200477Development 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 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. 358https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Evaluation of the Benefits of ATF, FLEX, and Passive Cooling System for an Enhanced Resilient PWR Model, INL/EXT-19-5621555417Evaluation 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 322https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf
Fuel Rod Burst Potential Evaluation under LOCA Conditions for an Existing Plant with Extended Burnup Exceeding the Current Limit by 20%, INL/EXT-19-5588855421Fuel 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 590https://lwrs.inl.gov/RiskInformed Safety Margin Characterization/Forms/AllItems.aspxpdfFalsepdf

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​​ enhanced resilient plant.jpg
Concept o​f Enhanced Resilient Plant