Risk-Informed Systems Analysis - Reports
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Assessing the Impact of the Inflation Reduction Act on Nuclear Plant Power Uprate and Hydrogen Cogeneration, INL/RPT-23-74681 | 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. | Download | 9/28/2023 |
| Tools And Methods to Analyze Plant Outage Schedules and Assist Schedulers in Improving Outage Resilience, INL/EXT-24-80380 | The project explored how power uprates can be achieved by boosting reactor thermal power output and optimizing reactor core design, while ensuring the safety and economic viability of NPPs. Specifically, it will focus on demonstrating the technical and economic feasibility of power uprates in a PWR using low 5-10% enrichment uranium (LEU+) high burnup (HBU) fuel combined with ATF concepts. The project focused on building foundational models and conducting multi-physics performance and safety analyses to support the power uprate. | Download | 09/24/2024 |
| Technical and Economic Considerations for Uprate of Existing Nuclear Reactors with Cogeneration, INL/EXT-24-78810 | This project conducted assessment of additional revenue source of oxygen which is a byproduct of electrolysis-based hydrogen generation. Oxygen is required in many industrial processes and nuclear plants can support this demand through already considered hydrogen generation coupled with nuclear power. The project also evaluated feasibility of using power added though uprates for Direct Air Capture (DAC) process for capturing CO2 which could be sequestered underground or sold to industries using CO2 for their processes. The report also looked into regional potential for nuclear-hydrogen colocation and cogeneration. | Download | 07/01/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Pressurized-Water Reactor Core Design Demonstration with Genetic Algorithm Based Multi-Objective Plant Fuel Reload Optimization Platform, INL/RPT-23-74498 | 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. | Download | 9/12/2023 |
| A Full-scale Demonstration of Pressurized Water Reactor Core Design Optimization using Multi-Cycle Optimization Methodology, INL/RPT-24-80449 | In this fiscal year, the PRLO framework, in which the Risk Analysis Virtual Environment (RAVEN) plays a pivotal role, has been upgraded to include optimization capabilities for n-th cycle and consecutive cycles for a PWR. As part of this enhancement, the RAVEN-SIMULATE3 interface was expanded to handle fuel label maps in addition to just fuel types, enabling the optimization process to account for fuel assemblies from previous cycles. | Download | 9/13/2024 |
| Development of Genetic Algorithm Based Multi-Objective Plant Reload Optimization Platform, INL/RPT-23-71667 | 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. | Download | 3/27/2023 |
| Development of Plant Reload Optimization Platform Capabilities for Core Design and Fuel Performance Analysis, INL/RPT-22-70382 | 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. | Download | 12/31/2022 |
| Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis, INL/RPT-22-68628 | Development and Demonstration of a Risk-Informed Approach to the Regulatory Required Fuel Reload Safety Analysis. | Download | 8/22/2022 |
| Demonstration of the Plant Fuel Reload Process Optimization for an Operating PWR, INL/EXT-21-64549 | 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. | Download | 9/30/2021 |
| RISA Plant Reload Process Optimization: Development of design basis accident methods for plant reload license optimization, INL/EXT-20-59614 | RISA Plant Reload Process Optimization: Development of design basis accident methods for plant reload license optimization, INL/EXT-20-59614 | Download | 8/9/2020 |
| Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER 3.0) User Guide, INL/RPT-24-80110 | The HUNTER software was finalized into a releasable executable software application, coupled to the existing software called the Rancor Microworld Simulator. Rancor-HUNTER provides a built-in simulator to allow the virtual HUNTER operator to simulate human performance across nuclear power plant scenarios. The user guide provides features and background on both Rancor and HUNTER, as well as documentation of a demonstration scenario. | Download | 09/15/2024 |
| A Full-scale Demonstration of Pressurized Water Reactor Core Design Optimization using Multi-Cycle Optimization Methodology, INL/RPT-24-80449 | In this fiscal year, the PRLO framework, in which the Risk Analysis Virtual Environment (RAVEN) plays a pivotal role, has been upgraded to include optimization capabilities for n-th cycle and consecutive cycles for a PWR. As part of this enhancement, the RAVEN-SIMULATE3 interface was expanded to handle fuel label maps in addition to just fuel types, enabling the optimization process to account for fuel assemblies from previous cycles. | Download | 09/13/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Development of Analysis Methods that Integrate Numeric and Textual Equipment Reliability Data, INL/RPT-23-74530 | 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. | Download | 09/05/2023 |
| Application of Margin-Based Methods to Assess System Health, INL/RPT-22-70361 | 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. | Download | 12/15/2022 |
| Bridging Equipment Reliability Data and Robust Decisions in a Plant Operation Context, INL/RPT-22-67670 | 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. | Download | 06/07/2022 |
| Industry Use Cases for Risk-Informed System Health and Asset Management, INL/EXT-21-64377 | Industry Use Cases for Risk-Informed System Health and Asset Management, INL-EXT-21-64377 | Download | 09/29/2021 |
| Development and Release of the Methods and Tools for Risk-Informed Asset Management, INL/EXT-21-63255 | Development and Release of the Methods and Tools for Risk-Informed Asset Management, INL/EXT-21-63255 | Download | 07/26/2021 |
| Development and Application of a Risk Analysis Toolkit for Plant Resources Optimization, INL/EXT-20-59942 | Development and Application of a Risk Analysis Toolkit for Plant Resources Optimization, INL/EXT-20-5994 | Download | 09/21/2020 |
| Integration of Data Analytics with Plant System Health Program, INL/EXT-20-59928 | Integration of Data Analytics with Plant System Health Program, INL-EXT-20-59928 | Download | 09/21/2020 |
| Combined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement, INL/EXT-19-55819 | Combined Data Analytics and Risk Analysis Tool for Long Term Capital SSC Refurbishment and Replacement, INL-EXT-19-55819 | Download | 09/21/2019 |
| Plant Integral Risk-informed System Health Program, INL/EXT-19-55808 | Plant Integral Risk-informed System Health Program, INL-EXT-19-55808 | Download | 09/20/2019 |
| CRAFT An Integrated Risk Analysis Tool and its Application in an Industry Use Case, INL/EXT-18-51442 | Cost Risk Analysis Framework (CRAFT) An Integrated Risk Analysis Tool and its Application in an Industry Use Case, INL/EXT-18-51442 | Download | 09/26/2018 |
| Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-39851 | Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit, INL/EXT-16-39851 | Download | 09/01/2016 |
| Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, INL/EXT-15-35933 | Improved Sampling Algorithms in the Risk-Informed Safety Margin Characterization Toolkit, INL-EXT-15-35933 | Download | 08/01/2015 |
| Technical Language Processing of Nuclear Power Plants Equipment Reliability Data | 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. | Download | 05/15/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| An Integrated Framework for Risk Assessment of Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology Refinement and Exploration, INL/RPT-23-74412 | 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. This project also investigated new methodologies for assessing human system interfaces, conducting dynamic probabilistic risk analyses on CCF evaluation, and evaluating the reliability of potential machine learning models integrated into DI&C systems. These efforts aim to provide a more comprehensive assessment of various safety-related DI&C design architectures. | Download | 9/15/2023 |
| 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-23-71699 | 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. | Download | 4/27/2023 |
| 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-22-70056 | In 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/designs | Download | 11/24/2022 |
| 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-22-68656 | An Integrated Framework for Risk Assessment of High Safety-significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration. | Download | 9/20/2022 |
| Quantitative Risk Analysis of High Safety significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants using IRADIC Technology, INL/EXT-21-64039 | Quantitative Risk Analysis of High Safety significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants using IRADIC Technology, INL/EXT-21-64039 | Download | 8/31/2021 |
| Redundancy-guided System-theoretic Hazard and Reliability Analysis of Safety related Digital Instrumentation and Control Systems in Nuclear Power Plants, INL/EXT-20-59550 | Redundancy-guided System-theoretic Hazard and Reliability Analysis of Safety related Digital Instrumentation and Control Systems in Nuclear Power Plants, INL/EXT-20-59550 | Download | 8/15/2020 |
| An Integrated Framework for Risk Assessment of Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology Advancement and Application, INL/RPT-24-80888 | FY24 activities for the DOE LWRS Program’s RISA Pathway and DI&C Risk Assessment project aimed to optimize safety margins and minimize uncertainties. The goal was to achieve economic efficiencies while maintaining high safety levels by providing a scientific basis and developing technologies to reduce operating costs. | Download | 09/20/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Methods and Feature Enhancements for Industry Use of EMRALD, INL/RPT-23-74447 | 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. | Download | 9/6/2023 |
| Dynamic and Classical PRA Coupling using EMRALD and SAPHIRE, INL/RPT-22-70424 | 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. | Download | 12/15/2022 |
| Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333 | Integration of Physical Security Simulation Software Applications in a Dynamic Risk Framework, INL/EXT-21-64333 | Download | 8/16/2021 |
| Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891 | Methodology and Application of Physical Security Effectiveness Based on Dynamic Force-on-Force Modeling, INL/EXT-20-59891 | Download | 9/4/2020 |
| Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510 | Integration of FLEX Equipment and Operator Actions in Plant Force-On-Force Models with Dynamic Risk Assessment, INL/EXT-20-59510 | Download | 8/4/2020 |
| Status of Adaptive Surrogates within the RAVEN Framework, INL/EXT-17-43438 | 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. | Download | 9/20/2017 |
| A Simulation Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, INL/EXT-17-40928 | A Simulation-Based Dynamic Analysis Approach for Modeling Total Plant Response to Flooding Events, RIL 2022-03 INL/EXT-17 40928 | Download | 2/22/2017 |
| System Reliability Analysis Capability and Surrogate Model Application in RAVEN, INL/EXT-16-37243 | 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. | Download | 11/13/2015 |
| Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491 | Advanced probabilistic risk analysis using RAVEN and RELAP-7, INL/EXT-14-32491 | Download | 6/26/2014 |
| Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN, INL/EXT-13-30203 | 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. | Download | 9/20/2013 |
| Reactor analysis and virtual control environment (RAVEN) FY12, INL/EXT-12-27351 | 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. | Download | 9/2/2012 |
| Upgrade of EMRALD to a Modern JavaScript-based Framework, INL/RPT-24-78713 | Event Modeling Risk Assessment using Linked Diagrams (EMRALD) is a software tool developed at Idaho National Laboratory for researching the capabilities of dynamic probabilistic risk assessment. It provides a simple interface to represent complex interactions often seen when developing dynamic models. This report goes over the work performed as part of the Risk-Informed Systems Analysis Pathway under the Light Water Reactor Sustainability program to upgrade the EMRALD software. | Download | 06/27/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Safety Analysis of FeCrAl Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup for PWR, INL/RPT-23-74731 | 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. | Download | 9/27/2023 |
| Automated Knowledge Extraction from Plant Records to Support Predictive Maintenance, INL/RPT-24-78817 | This report summarizes the activities performed within the advanced modeling and data analytics project during Fiscal Year 2024 in collaboration with a nuclear power utility. Our work activities focused on a fairly unique task: the analysis and integration of ER data in all its forms, numeric and textual. | Download | 07/01/2024 |
| Assessment of Modeling and Simulation Technical Gaps in Safety Analysis of High-Burnup Accident-Tolerant Fuels, INL/RPT-23-70844 | 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. | Download | 1/30/2023 |
| Safety Analysis for Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup, 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 | Download | 8/14/2022 |
| 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 | Download | 9/28/2021 |
| 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 | Download | 9/29/2020 |
| Development of RELAP5-3D Modeling of RCIC System, INL/EXT-20-59819 | Development of RELAP5-3D Modeling of Reactor Core Isolation Cooling (RCIC) System, INL/EXT-20-59819, H. Zhang, C. Blakley, September 2020. | Download | 9/21/2020 |
| 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 | Download | 10/17/2019 |
| 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 | Download | 9/20/2019 |
| Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling, INL/EXT-19-53556 | Risk-Informed Analysis for an Enhanced Resilient PWR with ATF, FLEX, and Passive Cooling, INL/EXT-19-53556 | Download | 8/29/2019 |
| 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-17-42461 | 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-17-42461 | Download | 6/18/2017 |
| Industry Application Emergency Core Cooling System Cladding Accept Criteria Problem Statement, INL/EXT-15-35073 | Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Problem Statement, INL/EXT-15-35073 | Download | 5/1/2015 |
| Accident Tolerant Fuel Analysis, INL/EXT-14-33200 | Accident Tolerant Fuel Analysis, INL/EXT-14-33200 | Download | 9/1/2014 |
| Tools And Methods to Analyze Plant Outage Schedules and Assist Schedulers in Improving Outage Resilience, INL/EXT-24-80380 | This report provides details on how plant resources (time and crews) can be allocated such that delays are minimized. In this respect, two classes of methods have been developed: one that focuses on the time resource and how variability in the time to complete outage tasks may impact outage delays, and one that minimizes the risk of outage delays by integrating available resources to assess when daily activities should be performed. | Download | 09/09/2024 |
| Safety Analysis of Chromium-Coated Accident-Tolerant Fuels with Increased Enrichment and Extended Burnup for PWRs, INL/RPT-24-77203 | 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. | Download | 3/27/2024 |
| Use of Time Distributions to Predict Operator Procedure Performance in Dynamic Human Reliability Analysis, INL/RPT-24-78875 | The current analysis was performed to investigate time distributions for task primitives, which are the minimum task unit of analysis used in dynamic HRA modeling. Using the time distribution data, the elapsed time for human actions in an extended loss of AC power (ELAP) scenario is then investigated. Time data and prediction are essential for modeling procedure performance. | Download | 06/27/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| EMRALD-HUNTER: An Embedded Dynamic Human Reliability Analysis Module for Probabilistic Risk Assessment, INL/RPT-23-72783 | EMRALD is a software package for dynamic probabilistic risk assessment, while HUNTER is a tool for modeling human reliability analysis. The integration of these tools, known as EMRALD-HUNTER, enables streamlined risk modeling for both plant systems and human operator reliability, incorporating human reliability analysis into dynamic probabilistic risk assessment models. | Download | 5/31/2023 |
| Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) Demonstration: Part 2, Model Runs of Operational Scenarios, INL/RPT-22-70076 | The purpose of this report is to demonstrate two additional operational scenarios modeled in HUNTER: startup and loss of feedwater. The report also documents additional features in HUNTER accomplished through coupling it with the Rancor Microworld Simulator. | Download | 11/15/2022 |
| HUNTER Demonstration: Part 1, Empirical Data Collection of Operational Scenarios, INL/RPT-22-69167 | Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) Demonstration: Part 1, Empirical Data Collection of Operational Scenarios. | Download | 9/15/2022 |
| Software Implementation and Demonstration of the HUNTER, INL/RPT-22-66564 | Software Implementation and Demonstration of the Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER) | Download | 3/31/2022 |
| An Adaptable Software Toolkit for Dynamic Human Reliability Analysis: Progress Toward HUNTER 2, INL/EXT-21-64525 | The report concludes with a discussion of future activities. One area of considerable focus is ensuring additional scenarios are modeled to support emerging industry needs for human reliability analysis | Download | 9/30/2021 |
| Integration of Human Reliability Analysis Models into the Simulation-Based Framework, INL/EXT-16-39015 | Integration of Human Reliability Analysis Models into the Simulation-Based Framework, INL/EXT-16-39015 | Download | 6/1/2016 |
| Proof-of-Concept Demonstrations for Computation-Based Human Reliability Analysis: Modeling Operator Performance During Flooding Scenarios, INL/EXT-15-36741 | Proof-of-Concept Demonstrations for Computation-Based Human Reliability Analysis: Modeling Operator Performance During Flooding Scenarios, INL-EXT-15-36741 | Download | 9/1/2015 |
| A Research Roadmap for Computation-Based Human Reliability Analysis, INL/EXT-15-36051 | A Research Roadmap for Computation-Based Human Reliability Analysis, INL-EXT-15-36051 | Download | 7/1/2015 |
| Simulation and Non-Simulation Based Human Reliability Analysis Approaches, INL/EXT-14-33903 | Simulation and Non-Simulation Based Human Reliability Analysis Approaches, INL-EXT-14-33903 | Download | 9/1/2014 |
| Use of Time Distributions to Predict Operator Procedure Performance in Dynamic Human Reliability Analysis, INL/RPT-24-78875 | The current analysis was performed to investigate time distributions for task primitives, which are the minimum task unit of analysis used in dynamic HRA modeling. Using the time distribution data, the elapsed time for human actions in an extended loss of AC power (ELAP) scenario is then investigated. Time data and prediction are essential for modeling procedure performance. | Download | 07/01/2024 |
| Human Unimodel for Nuclear Technology to Enhance Reliability (HUNTER 3.0) User Guide, INL/RPT-24-80110 | The HUNTER software was finalized into a releasable executable software application, coupled to the existing software called the Rancor Microworld Simulator. Rancor-HUNTER provides a built-in simulator to allow the virtual HUNTER operator to simulate human performance across nuclear power plant scenarios. The user guide provides features and background on both Rancor and HUNTER, as well as documentation of a demonstration scenario. | Download | 9/15/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Novel Approaches and Technologies for Aging Management, INL/RPT-23-74593 | This report describes R&D within the Risk-informed System Analysis pathway that was focused on risk-informed and performance-based approaches for aging management of buried piping, specifically managing selective leaching degradation phenomena. Selective leaching is a commonly occurring aging and degradation mechanism in buried pipes at nuclear power plants. To better understand the extent of selective leaching and its effect on the health of buried components, the licensees currently rely on visual inspections and destructive examinations which require extraction of multiple buried components, e.g., pipes. This research explored technological solutions that may replace or supplement existing inefficient, costly, and labor-intensive methods used in aging management. | Download | 9/26/2023 |
| Simplified Cost-Benefit Analysis of Subsequent License Renewal, INL/RPT-23-03359 | This report provides areas where the cost, time, and resource efforts may be reduced with additional analytical evaluation, model changes, inspection technique changes, and a review of past inspection results. | Download | 5/31/2023 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Tools and Methods for Optimization of Nuclear Plant Outages, INL/RPT-23-74439 | This research focused on the initial development and demonstration of tools and methods supporting outage activities to manage activities effectively with the goal to minimize outage time. | Download | 9/8/2023 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| FRI3D Industry Adoption and Verification Tasks, INL/RPT-23-74213 | This report outlines several updates and additions that were made to help meet industry needs before it can be fully transferred to an industry partner for commercial use. Examples include software verification features and a library of commercially used fire sources. This report also goes over work for industry adoption, including a fire analys is pilot study done for a nuclear power plant modification. This pilot study showed a time comparison between using FRI3D and current methods used by fire analysis experts and an evaluation from the experts on the potential for use by industry. | Download | 8/28/2023 |
| FRI3D Fire Simulation Options and Verification Tasks, INL/RPT-23-70843 | 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. | Download | 1/31/2023 |
| Industry Level Integrated FRI3D, INL/EXT-21-64079 | Industry Level Integrated Fire Modeling Using Fire Risk Investigation in 3D (FRI3D), INL/EXT-21-6407 | Download | 8/15/2021 |
| 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 | Download | 8/22/2020 |
| Risk Importance Ranking of Fire Data Parameters to Enhance Fire PRA Model Realism, INL/EXT-20-00212 | Risk Importance Ranking of Fire Data Parameters to Enhance Fire PRA Model Realism, INL/EXT-20-00212 | Download | 5/11/2020 |
| Industry Fire Modeling Enhancement Tools and Methods, INL/EXT-19-54414 | Industry Fire Modeling Enhancement Tools and Methods, INL/EXT-19-54414 | Download | 6/18/2019 |
| RISA Dynamic Fire PRA Roadmap, INL/EXT-18-44926 | Risk-Informed Systems Analysis (RISA) Dynamic Fire PRA Roadmap, INL/EXT-18-44926 | Download | 3/27/2018 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Industry Level Feasibility of LiDAR Data into FRI3D, INL/RPT-22-67714 | This report presents Idaho National Lab’s work with Environmental Intellect (Ei) covering two main efforts. First, to reduce the effort of “tagging” data in large 3D models. By using both existing plant database information and artificial intelligence (AI) to find and read equipment labels. This research explores the ability to provide a simple way for the user to tag items and verify plant data, capturing both the speed of AI and human verification. | Download | 7/25/2022 |
| Investigating Application of LiDAR for Nuclear Power Plants, INL/EXT-21-64452 | Investigating Application of LiDAR for Nuclear Power Plants, INL/EXT-21-64452 | Download | 9/27/2021 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2021 Extended Period of Performance – Final Report, SAND2021-781 | Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2021 Extended Period of Performance – Final Report, SAND2021-781 | Download | 7/1/2021 |
| Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2020 – Progress Report, SAND2020-9368 | Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2020 – Progress Report, SAND2020-9368 | Download | 9/21/2020 |
| Terry Turbopump Expanded Operating Band Modeling and Full-Scale Test Development Efforts in Fiscal Year 2019 – Progress Report, SAND2019-13423 | Terry Turbopump Expanded Operating Band Modeling and Full-Scale Test Development Efforts in Fiscal Year 2019 – Progress Report, SAND2019-13423 | Download | 10/10/2019 |
| Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, INL/EXT-18-51442 | Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, SAND2018-12965 | Download | 1/5/2019 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2021 Extended Period of Performance – Final Report, SAND2021-781 | Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2021 Extended Period of Performance – Final Report, SAND2021-781 | Download | 7/1/2021 |
| Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2020 – Progress Report, SAND2020-9368 | Terry Turbopump Expanded Operating Band Modeling and Simulation Efforts in Fiscal Year 2020 – Progress Report, SAND2020-9368 | Download | 9/21/2020 |
| Terry Turbopump Expanded Operating Band Modeling and Full-Scale Test Development Efforts in Fiscal Year 2019 – Progress Report, SAND2019-13423 | Terry Turbopump Expanded Operating Band Modeling and Full-Scale Test Development Efforts in Fiscal Year 2019 – Progress Report, SAND2019-13423 | Download | 10/10/2019 |
| Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, INL/EXT-18-51442 | Terry Turbopump Expanded Operating Band Full-Scale Integral Long-Term Low-Pressure Experiments – Preliminary Test Plan, SAND2018-12965 | Download | 1/5/2019 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Risk-Informed Initiating Events Accident Response, INL/RPT-22-68669 | Opportunities exist to make plants’ regulatory compliance processes more efficient which can be done by decreasing reliance on deterministic and prescriptive approaches and expansion of the use of risk-informed and performance-based approaches to demonstrate reactor safety. In this report, we researched possibilities of economic benefits potentially available from the application of concepts associated with a modernized regulatory framework developed for advanced reactors to the existing light water reactors. As the result, we have identified multiple areas of existing plant operations where modernization of compliance activities can offer substantial economic benefits. Additional research is needed to demonstrate these expected benefits using case studies conducted in collaboration with utilities. | Download | 8/30/2022 |
| RISA Pathway Industry Application Pilot Demonstration Projects – Edition 2019, INL/EXT-19-54449 | Risk-Informed Systems Analysis (RISA) Pathway Industry Application Pilot Demonstration Projects – Edition 2019, INL/EXT-19-54449 | Download | 6/18/2019 |
| A Strategic Approach to Employ Risk-Informed Methods to Enable Margin Recovery of Nuclear Power Plants Operating Margins, INL/EXT-18-51491 | A Strategic Approach to Employ Risk-Informed Methods to Enable Margin Recovery of Nuclear Power Plants Operating Margins, INL/EXT-18-51491 | Download | 9/20/2018 |
| RISA Industry Use Case Analysis, INL/EXT-18-51012 | RISA Industry Use Case Analysis, INL/EXT-18-51012 | Download | 8/26/2018 |
| Risk-Informed Analysis of Commercial Nuclear Reactors: the RISMC Approach and 10CFR50.69, INL/LTD-17-43208 | Risk-Informed Analysis of Commercial Nuclear Reactors: the RISMC Approach and 10CFR50.69, INL/LTD-17-43208 | Download | 9/20/2017 |
| Nuclear Power Plant Mechanical Component Flooding Fragility Experiments FY-2017 Report, INL/EXT-17-43439 | Nuclear Power Plant Mechanical Component Flooding Fragility Experiments FY-2017 Report, INL/EXT-17-43439 | Download | 9/18/2017 |
| Advanced Seismic Probabilistic Risk Assessment Methodology: Development of Beta 1.0 MASTODON Toolset, INL/EXT-17-43148 | Advanced Seismic Probabilistic Risk Assessment Methodology: Development of Beta 1.0 MASTODON Toolset, INL/EXT-17-43148 | Download | 8/18/2017 |
| Nuclear Power Plant Mechanical Component Flooding Fragility Experiments Status, INL/EXT-17-42728 | Nuclear Power Plant Mechanical Component Flooding Fragility Experiments Status, INL/EXT-17-42728 | Download | 7/28/2017 |
| Risk-Informed External Hazards Analysis for Seismic and Flooding Phenomena for a Generic PWR , NL/EXT-17-42666 | Risk-Informed External Hazards Analysis for Seismic and Flooding Phenomena for a Generic PWR, INL/EXT-17-42666 | Download | 7/28/2017 |
| Smoothed-particle Hydrodynamics, INL/EXT-16-40614 | Smoothed-particle Hydrodynamics based Wind Representation, INL/EXT-16-40614 | Download | 12/19/2016 |
| Flooding Fragility Experiments and Prediction, INL/EXT-16-39963 | Flooding Fragility Experiments and Prediction, INL/EXT-16-39963 | Download | 9/1/2016 |
| Loss of Coolant Accident Emergency Core Collant System Evaluation of Risk-informed Margins Management Strategies for a Representative Pressurized Water Reactor, INL/EXT-16-39805 | Loss of Coolant Accident Emergency Core Coolant System Evaluation of Risk-informed Margins Management Strategies for a Representative Pressurized Water Reactor, INL/EXT-16-39805 | Download | 9/1/2016 |
| Multi-Hazard Advanced Seismic Probabilistic Risk Assessment Tools and Applications, INL/EXT-16-4005 | Multi-Hazard Advanced Seismic Probabilistic Risk Assessment Tools and Applications, INL/EXT-16-4005 | Download | 9/1/2016 |
| RELAP-7 Software Verification and Validation Plan, INL/EXT-16-40015 | RELAP-7 Software Verification and Validation Plan, INL/EXT-16-40015 | Download | 9/1/2016 |
| Demonstration of External Hazards Analysis, INL/EXT-16-39353 | Demonstration of External Hazards Analysis, INL/EXT-16-39353 | Download | 7/1/2016 |
| Large Scale Laminar Box Test Plan, INL/EXT-16-39479 | Large Scale Laminar Box Test Plan, INL/EXT-16-39479 | Download | 7/1/2016 |
| Plan to Verify and Validate Multi-Hazard Risk-Informed Margin Management Methods and Tools, INL/EXT-16-39195 | Plan to Verify and Validate Multi-Hazard Risk-Informed Margin Management Methods and Tools, INL/EXT-16-39195 | Download | 7/1/2016 |
| Status of the Flooding Fragility Testing Development, INL/EXT-16-39115 | Status of the Flooding Fragility Testing Development, INL/EXT-16-39115 | Download | 6/1/2016 |
| R&D Plan for RISMC Industry Application #1: ECCS/LOCA Cladding Acceptance Criteria, INL/EXT-16-38231 | R&D Plan for RISMC Industry Application #1: ECCS/LOCA Cladding Acceptance Criteria, INL/EXT-16-38231 | Download | 4/1/2016 |
| RISMC Toolkit and Methodology Research and Development Plan for External Hazards Analysis, INL/EXT-16-38089 | RISMC Toolkit and Methodology Research and Development Plan for External Hazards Analysis, INL/EXT-16-38089 | Download | 3/1/2016 |
| Development Plan for the External Hazards Experimental Group, INL/EXT-16-38328 | Development Plan for the External Hazards Experimental Group, INL/EXT-16-38328 | Download | 3/1/2016 |
| System Reliability Analysis Capability and Surrogate Model Application in RAVEN, INL/EXT-16-37243 | System Reliability Analysis Capability and Surrogate Model Application in RAVEN, INL/EXT-16-37243 | Download | 11/30/2015 |
| Initial Probabilistic Evaluation of Reactor Pressure Vessel Fracture with Grizzly and RAVEN, INL/EXT-15-37121 | Fracture with Grizzly and RAVEN, B. Spencer, W. Hoffman, S. Sen, C. Rabiti, T. Dickson, R. Bass, INL/EXT-15-37121 | Download | 10/17/2015 |
| Flooding Capability for River-based Scenarios, INL/EXT-15-37901 | Flooding Capability for River-based Scenarios, INL/EXT-15-37901 | Download | 10/2/2015 |
| Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration, INL/EXT-15-36541 | Industry Application Emergency Core Cooling System Cladding Acceptance Criteria Early Demonstration, INL-EXT-15-36541 | Download | 9/1/2015 |
| Reduced Order Model Implementation in the Risk-Informed Safety Margin Characterization Toolkit INL/EXT-15-36649 | Reduced Order Model Implementation in the Risk-Informed Safety Margin Characterization Toolkit, INL-EXT-15-36649 | Download | 9/1/2015 |
| Advanced Seismic Fragility Modeling using Nonlinear Soil-Structure Interaction Analysis, INL/EXT-15-36735 | Advanced Seismic Fragility Modeling using Nonlinear Soil-Structure Interaction Analysis, INL-EXT-15-36735 | Download | 9/1/2015 |
| Progress on the Industry Application External Hazard Analyses Early Demonstration, INL/EXT-15-36749 | Progress on the Industry Application External Hazard Analyses Early Demonstration, INL-EXT-15-36749 | Download | 9/1/2015 |
| Dynamic Event Tree Advancements and Control Logic Improvements, INL/EXT-15-36758 | Dynamic Event Tree Advancements and Control Logic Improvements, INL-EXT-15-36758 | Download | 9/1/2015 |
| 3D Simulation of External Flooding for the RISMC Pathway, INL/EXT-15-36773 | 3D Simulation of External Flooding Events for the RISMC Pathway, INL-EXT-15-36773 | Download | 9/1/2015 |
| Demonstration of Coupled Multievent Scenario at a Nuclear Power Plant, INL/EXT-15-36801 | Demonstration of Coupled Multievent Scenario at a Nuclear Power Plant, INL-EXT-15-36801 | Download | 9/1/2015 |
| Industry Application External Hazard Analyses Problem Statement, INL/EXT-15-36101 | Industry Application External Hazard Analyses Problem Statement, INL-EXT-15-36101 | Download | 7/1/2015 |
| Advanced Seismic Soil Structure Modeling, INL/EXT-15-35687 | Advanced Seismic Soil Structure Modeling, INL/EXT-15-35687 | Download | 6/1/2015 |
| Light Water Reactor Sustainability Program Seismic Data Gathering and Validation, INL/EXT-15-34425 | Light Water Reactor Sustainability Program Seismic Data Gathering and Validation, INL/EXT-15-34425 | Download | 2/1/2015 |
| Risk-Informed Safety Margin Characterization Methods Development Work, INL/EXT-14-33191 | This report presents several analyses that demonstrate the value of the RISMC approach in order to assess risk associated with nuclear power plants (NPPs). We focus on simulation-based PRA which, in contrast to classical PRA, heavily employs system simulator codes. First, we compare, these two types of analyses, classical and RISMC, for a Boiling Water Reactor (BWR) Station Black Out (SBO) initiating event. | Download | 9/20/2014 |
| Case Study for Enhanced Accident Tolerance Design Changes, INL/EXT-14-32355 | Case Study for Enhanced Accident Tolerance Design Changes, S. Prescott, INL/EXT-14-32355 | Download | 9/1/2014 |
| Refined Boiling Water Reactor Station Blackout Simulation with RELAP-7, INL/EXT-14-33162 | Refined Boiling Water Reactor Station Blackout Simulation with RELAP-7, INL/EXT-14-33162 | Download | 9/1/2014 |
| RISMC Advanced Safety Analysis Project Plan FY2015–FY2019, INL/EXT-14-33186 | RISMC Advanced Safety Analysis Project Plan FY2015–FY2019, INL-EXT-14-33186 | Download | 9/1/2014 |
| Risk-Informed Safety Margin Characterization Methods Development Work, INL/EXT-14-33191 | Risk-Informed Safety Margin Characterization Methods Development Work, INL/EXT-14-33191 | Download | 9/1/2014 |
| Demonstration of NonLinear Seismic Soil Structure Interaction and Applicability to New System Fragility Seismic Curves, INL/EXT-14-33222 | Demonstration of NonLinear Seismic Soil Structure Interaction and Applicability to New System Fragility Seismic Curves, INL/EXT-14-33222 | Download | 9/1/2014 |
| Advanced Seismic Probabilistic Risk Assessment Demonstration Project Plan, INL/EXT-14-33302 | Advanced Seismic Probabilistic Risk Assessment Demonstration Project Plan, INL/EXT-14-33302 | Download | 9/1/2014 |
| Prototype Consequence Modeling Tool Based Upon the Hybrid Single Particle Lagrangian Integrated Trajectory (HYSPLIT) Software | Prototype Consequence Modeling Tool Based Upon the Hybrid Single Particle Lagrangian Integrated Trajectory (HYSPLIT) Software, C. Pope, B. Byambadorj, C. Hill, E. Lum, B. Nield, and J. Swanson, Idaho State University, September 2014. | Download | 9/1/2014 |
| Enhanced Severe Transient Analysis for Prevention Technical Program Plan, INL/EXT-14- 33228 | Enhanced Severe Transient Analysis for Prevention Technical Program Plan, INL/EXT-33228 | Download | 9/1/2014 |
| Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit, INL/EXT-14-32906 | Analysis of Pressurized Water Reactor Station Blackout Caused by External Flooding Using the RISMC Toolkit, INL/EXT-14-32906 | Download | 8/1/2014 |
| Survey of Models for Concrete Degradation, INL/EXT-14-32925 | Survey of Models for Concrete Degradation, INL/EXT-14-32925 | Download | 8/1/2014 |
| Light Water Reactor Sustainability Program Case Study for Enhanced Accident Tolerance Design Changes, INL/EXT-14-32355 | Light Water Reactor Sustainability Program Case Study for Enhanced Accident Tolerance Design Changes, INL/EXT-14-32355 | Download | 6/1/2014 |
| Report on Prevention Analysis Trial Method and Case Study Improvements, M3LW-12IN0702012 | Report on Prevention Analysis Trial Method and Case Study Improvements, D. Blanchard and R. Youngblood, M3LW-12IN0702012 | Download | 4/1/2012 |
| Physics-Based Stress Corrosion Cracking Component Reliability Model Cast in an R7-Compatible Cumulative Damage Framework, PNNL-20596 | Physics-Based Stress Corrosion Cracking Component Reliability Model Cast in an R7-Compatible Cumulative Damage Framework, PNNL- 20596 | Download | 7/1/2011 |
| Tools And Methods to Analyze Plant Outage Schedules and Assist Schedulers in Improving Outage Resilience, INL/EXT-24-80380 | The project explored how power uprates can be achieved by boosting reactor thermal power output and optimizing reactor core design, while ensuring the safety and economic viability of NPPs. Specifically, it will focus on demonstrating the technical and economic feasibility of power uprates in a PWR using low 5-10% enrichment uranium (LEU+) high burnup (HBU) fuel combined with ATF concepts. The project focused on building foundational models and conducting multi-physics performance and safety analyses to support the power uprate. | Download | 09/26/2024 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Risk-Informed Multi-Physics BEPU: Demonstration of LOCA Scenario-Based Reflood Phenomena, INL/EXT-21-64450 | Risk-Informed Multi-Physics Best-Estimate Plus Uncertainties (BEPU): Demonstration of LOCA Scenario-Based Reflood Phenomena, INL/EXT-21-64450 | Download | 9/30/2021 |
| Risk-informed multi-physics best-estimate plus uncertainties (BEPU) application development of RELAP5-3D perturbation model, INL/EXT-20-59594 | Risk-informed multi-physics best-estimate plus uncertainties (BEPU) application development of RELAP5-3D perturbation model, INL/EXT-20-59594 | Download | 8/31/2020 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| Technical Maturity Assessment of MOOSE-Based Tools: MASTODON, BISON and Grizzly, INL/EXT-21-64451 | Technical Maturity Assessment of MOOSE-Based Tools: MASTODON, BISON and Grizzly, INL/EXT-21-64451 | Download | 9/30/2021 |
| Assessment of Verification and Validation Status – EMRALD and HUNTER, INL/EXT-20-59904 | Assessment of Verification and Validation Status – EMRALD and HUNTER, INL/EXT-20-59904 | Download | 9/21/2020 |
| Assessment of verification and validation status – RELAP5-3D and RAVEN, INL/EXT-19-56151 | Assessment of verification and validation status – RELAP5-3D and RAVEN, INL/EXT-19-56151 | Download | 10/1/2019 |
| Advanced Validation Risk-Informed Approach for the Flooding Tool Based Upon Smooth Particle Hydrodynamics – Validation and Development Status of NEUTRINO, INL/EXT-18-44976 | Advanced Validation Risk-Informed Approach for the Flooding Tool Based Upon Smooth Particle Hydrodynamics – Validation and Development Status of NEUTRINO, INL/EXT-18-44976 | Download | 3/18/2018 |
| RELAP-7 Software Verification and Validation Plan RTM Update and Code Verification Strategy, INL/EXT-17-43199 | RELAP-7 Software Verification and Validation Plan Requirements Traceability Matrix (RTM) Update and Code Verification Strategy, INL/EXT-17-43199 | Download | 9/20/2017 |
| Report Title | Brief Narrative | Link | Date |
|---|---|---|---|
| The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta, ANL-18/22 | The CORQUENCH Code for Modeling of Ex-Vessel Corium Coolability under Top Flooding Conditions Code Manual – Version4.1-beta, ANL-18/22 | Download | 8/6/2018 |
| Preliminary Study on the Suitability of a Second-Order Reconstructed Discontinuous Galerkin Method for RELAP-7 Thermal-Hydraulic Modeling, INL/EXT-17-43108 | Preliminary Study on the Suitability of a Second-Order Reconstructed Discontinuous Galerkin Method for RELAP-7 Thermal-Hydraulic Modeling, INL/EXT-17-43108 | Download | 9/20/2017 |
| Status of Adaptive Surrogates within the RAVEN Framework, INL/EXT-17-43438 | Status of Adaptive Surrogates within the RAVEN Framework, INL/EXT-17-43438 | Download | 9/20/2017 |
| Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427 | Enhancements to Engineering-scale Reactor Pressure Vessel Fracture Capabilities in Grizzly, INL/EXT-17-43427 | Download | 9/18/2017 |
| RELAP-7 Closure Verification Part 1: Vertical Pre-CHF Closures | RELAP-7 Closure Verification Part 1: Vertical Pre-CHF Closures | Download | 9/18/2017 |
| Modeling of Cu Precipitate Contributions to Reactor Pressure Vessel Steel Microstructure Evolution and Embrittlement, INL/EXT-17-43110 | Modeling of Cu Precipitate Contributions to Reactor Pressure Vessel Steel Microstructure Evolution and Embrittlement, INL/EXT-17-43110 | Download | 8/18/2017 |
| Software Requirements Specification for RELAP-7, INL/EXT-17-41891 | Software Requirements Specification for RELAP-7, INL/EXT-17-41891 | Download | 4/28/2017 |
| RELAP-7 Closure Correlations, INL/EXT-17-41653 | RELAP-7 Closure Correlations, INL/EXT-17-41653 | Download | 4/18/2017 |
| RELAP-7 Closure Model Verification and Benchmarking Plan | RELAP-7 Closure Model Verification and Benchmarking Plan | Download | 3/18/2017 |
| Additional Model Datasets and Results to Accelerate the Verification and Validation of RELAP-7, INL/EXT-16-40577 | Additional Model Datasets and Results to Accelerate the Verification and Validation of RELAP-7, INL/EXT-16-40577 | Download | 11/14/2016 |
| Enhancements of the RAVEN Code in FY16, INL/EXT-16-40094 | Enhancements of the RAVEN code in FY16, INL/EXT-16-40094 | Download | 9/1/2016 |
| Lower Length Scale Model Development for Embrittlement of Reactor Pressure Vessel Steel, INL/EXT-16-40011 | Lower Length Scale Model Development for Embrittlement of Reactor Pressure Vessel Steel, INL/EXT-16-40011 | Download | 9/1/2016 |
| Probabilistic Fracture Mechanics of Reactor Pressure Vessels with Populations of Flaws, INL/EXT-16-40050, | Probabilistic Fracture Mechanics of Reactor Pressure Vessels with Populations of Flaws, INL/EXT-16-4005 | Download | 9/1/2016 |
| RELAP-7 Theory Manual, INL/EXT-14-31366 | RELAP-7 Theory Manual, INL/EXT-14-3136. | Download | 6/1/2016 |
| Development of Three-Field Poromechanics Capability in MOOSE, INL/EXT-16-3893 | Development of Three-Field Poromechanics Capability in MOOSE, M. Sivaselvan, N. Oliveto, A. Whittaker, INL/EXT-16-38931 | Download | 4/1/2016 |
| RELAP-7 Pressurizer Component Development Updates, INL/EXT-16-38185 | RELAP-7 Pressurizer Component Development Updates, INL/EXT-16-38185 | Download | 3/1/2016 |
| Grizzly Usage and Theory Manual, INL/EXT-16-38310 | Grizzly Usage and Theory Manual, INL/EXT-16-38310 | Download | 3/1/2016 |
| RAVEN User Manual, INL/EXT-15-34123 | RAVEN User Manual, INL/EXT-15-34123, Revision 4, C. Rabiti, A. Alfonsi, J. Cogliati, D. Mandelli, R. Kinoshita, S. Sen, C. Wang, February 2016. | Download | 2/1/2016 |
| RAVEN Beta 1.0 Release, INL/EXT-16-37953 | RAVEN Beta 1.0 Release, INL/EXT-16-37953 | Download | 2/1/2016 |
| Grizzly Model of Multi-Species Reactive Diffusion, Moisture/Heat Transfer, and Alkali-Silica Reaction in Concrete, INL/EXT-15-36425 | Grizzly Model of Multi-Species Reactive Diffusion, Moisture/Heat Transfer, and Alkali-Silica Reaction in Concrete, INL-EXT-15-36425 | Download | 9/1/2015 |
| RAVEN Quality Assurance Activities, INL/EXT-15-36656 | RAVEN Quality Assurance Activities, INL-EXT-15-36656 | Download | 9/1/2015 |
| Fracture Capabilities in Grizzly with the Extended Finite Element Method (X-FEM), INL/EXT-15-36752 | Fracture Capabilities in Grizzly with the eXtended Finite Element Method (X-FEM), INL-EXT-36752 | Download | 9/1/2015 |
| Mesoscale Modeling of Solute Precipitation and Radiation Damage, INL/EXT-15-36754 | Mesoscale modeling of solute precipitation and radiation damage, INL-EXT-15-36754 | Download | 9/1/2015 |
| RELAP-7 Development Updates, INL/EXT-15-36763 | RELAP-7 Development Updates, INL-EXT-36763 | Download | 9/1/2015 |
| RELAP-7 Progress Report: FY-2015 Optimization Activities Summary, INL/EXT-15-36771 | RELAP-7 Progress Report: FY-2015 Optimization Activities Summary, INL-EXT-15-36771 | Download | 9/1/2015 |
| Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly, INL/EXT-15-34786 | Crystal Plasticity Model of Reactor Pressure Vessel Embrittlement in Grizzly, INL/EXT-15-34786 | Download | 7/1/2015 |
| Improving Limit Surface Search Algorithms in RAVEN Using Acceleration Schemes, INL/EXT-15-36100 | Improving Limit Surface Search Algorithms in RAVEN Using Acceleration Schemes. A. Alfonsi, C. Rabiti, D. Mandelli, J. Cogliati, S. Sen, C. Smith, INL-EXT-15-36100, July 2015. | Download | 7/1/2015 |
| Reactor Pressure Vessel Fracture Analysis Capabilities in Grizzly, INL/EXT-15-34736 | Reactor Pressure Vessel Fracture Analysis Capabilities in Grizzly, INL-EXT-15-34736 | Download | 3/1/2015 |
| RAVEN User Manual, INL/EXT-15-34123 | RAVEN User Manual, INL/EXT-15-34123 | Download | 3/1/2015 |
| RELAP-7 Theory Manual, INL/EXT-14-31366 | RELAP-7 Theory Manual, INL/EXT-14-31366 | Download | 12/1/2014 |
| RELAP-7 User Guide, INL/EXT-14-33977 | RELAP-7 User Guide, INL/EXT-14-33977 | Download | 12/1/2014 |
| Developing Fully Coupled Subchannel Model in RELAP-7, INL/EXT-14-33102 | Developing Fully Coupled Subchannel Model in RELAP-7, INL/EXT-14-33102 | Download | 9/1/2014 |
| RELAP-7 Software Verification and Validation Plan, INL/EXT-14-33201 | RELAP-7 Software Verification and Validation Plan, INL/EXT-14-33201 | Download | 9/1/2014 |
| Grizzly Status Report, INL/EXT-14-33251 | Grizzly Status Report, INL/EXT-14-33251 | Download | 9/1/2014 |
| 3D J-Integral Capability in Grizzly, INL/EXT-14-33257 | 3D J-Integral Capability in Grizzly, INL/EXT-14-33257 | Download | 9/1/2014 |
| RELAP-7 Numerical Stabilization: Entropy Viscosity Method, INL/EXT-14-32352 | RELAP-7 Numerical Stabilization: Entropy Viscosity Method, INL/EXT-14-32352 | Download | 6/1/2014 |
| Grizzly Year-End Progress Report, INL/EXT-13-30316 | Grizzly Year-End Progress Report, INL/EXT-13-30316 | Download | 9/1/2013 |
| Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN INL/EXT-13-30203 | Support and Modeling for the Boiling Water Reactor Station Black Out Case Study Using RELAP and RAVEN, INL/EXT-13-30203 | Download | 9/1/2013 |
| Modeling of Late Blooming Phases and Precipitation Kinetics in Aging Reactor Pressure Vessel (RPV) Steels, INL/EXT-13-30267 | Modeling of Late Blooming Phases and Precipitation Kinetics in Aging Reactor Pressure Vessel (RPV) Steels, INL/EXT-13-30267 | Download | 9/1/2013 |
| Technical Approach and Results from the Fuels Pathway | Technical Approach and Results from the Fuels Pathway | Download | 9/1/2013 |
| RELAP-7 Simulation Resolving an SBO Scenario on a Simplified Geometry of a BWR, INL/EXT-13-29887 | RELAP-7 Simulation Resolving an SBO Scenario on a Simplified Geometry of a BWR, INL/EXT-13-29887 | Download | 8/1/2013 |
| Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management, INL/EXT-13-30019 | Technical Basis Guide Describing How to Perform Safety Margin Configuration Risk Management, INL/EXT-13-30019 | Download | 8/1/2013 |
| RELAP-7: Demonstrating the Integration of Two-phase Flow Components for an Ideal BWR Loop, INL/EXT-13-29514 | RELAP-7: Demonstrating the Integration of Two-phase Flow Components for an Ideal BWR Loop, INL/EXT-13-29514 | Download | 6/1/2013 |
| Implementation of Changes to the EONY Model to Account for Extended Service Conditions and Late Blooming Phases for Reactor Pressure Vessel Steels | Implementation of Changes to the EONY Model to Account for Extended Service Conditions and Late Blooming Phases for Reactor Pressure Vessel Steels | Download | 5/1/2013 |
| RELAP-7: Demonstrating Seven-Equation, Two-Phase Flow Simulation in a Single-Pipe, Two-Phase Reactor Core and Steam Separator/Dryer, INL/EXT-13-28750 | RELAP-7: Demonstrating Seven-Equation, Two-Phase Flow Simulation in a Single-Pipe, Two-Phase Reactor Core and Steam Separator/Dryer, INL/EXT-13-28750 | Download | 4/1/2013 |
| A Proof of Concept: Grizzly, the LWRS Program Materials Aging and Degradation Pathway Main Simulation Tool | A Proof of Concept: Grizzly, the LWRS Program Materials Aging and Degradation Pathway Main Simulation Tool | Download | 9/1/2012 |
| Risk Informed Safety Margin Characterization (RISMC), Advanced Test Reactor Demonstration Case Study, INL/EXT-12-27015 | Risk Informed Safety Margin Characterization (RISMC), Advanced Test Reactor Demonstration Case Study, INL/EXT-12-27015 | Download | 8/1/2012 |
