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Category:Meeting Briefing Package/Handouts
MONTHYEARML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24292A0652024-10-18018 October 2024 Evolving the Legacy of DOE/EH-0545 in the DOE Handbook 1220 ML24292A0612024-10-18018 October 2024 The Power Journey - a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24284A1152024-10-11011 October 2024 S9 Panel ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 January 2024 Integrated Safety, Security, and Safeguards Ffr Research Project ML23342A1642023-12-0808 December 2023 Networking and Information Technology Research and Development Program Software Productivity Sustainability and Quality (Spsq) NRC - Sushil Birla December 14, 2023 ML23292A0922023-10-30030 October 2023 Advanced Sensor and Instrumentation - NRC Research Status Update ML23298A0312023-10-26026 October 2023 Advanced Fuel Cycle Storage and Transportation Research ML23324A2702023-10-24024 October 2023 Session - Key Takeaways ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23275A0022023-10-0505 October 2023 Domain Modeling & Domain Engineering an Enabler for Correct-by-Construction Design ML23272A0332023-09-29029 September 2023 Identifying Hazards in a System Design ML23264A0212023-09-28028 September 2023 Addressing Hazards from Common Causes in Engineering Di&C Systems Without Diverse Designs - State-of-the-Art ML23264A0252023-09-20020 September 2023 September 20, 2023 - Dent Presentation - John Mckirgan - Research Activities in Support of Digital Engineering in Nuclear Technology ML23256A0102023-09-18018 September 2023 State-of-the-art Approaches to Reduce the Potential for CCF in I&C Systems Conditions to Avoid the Need for Diversity in Design ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (RIPB) Standards ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23242A1182023-09-0707 September 2023 Research Challenges and Opportunities in the Safety Assurance of Nuclear Reactors ML23248A2142023-09-0606 September 2023 Reactor Safety: Regulatory Objectives & Framework ML23242A0032023-08-31031 August 2023 Reactor Protection System for the Virtual Ford Nuclear Reactor Designed-in Assurance ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation ML23130A0042023-05-11011 May 2023 Challenges in Assuring Safety of Nuclear Reactor Protection Systems - One Perspective ML23067A3402023-03-0707 March 2023 Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology ML22322A0432022-11-18018 November 2022 Regulatory Research on the Aging Management of Structures, Systems and Components in Nuclear Power Plants for Second License Renewal, Presentation Slides 2024-09-27
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24313A1662024-11-13013 November 2024 NRC Metals Research Supporting Long-Term Operation Update for Lwrs Stakeholders Meeting November 13, 2024 ML24306A0122024-10-29029 October 2024 The Power Journey a Cursory Account of the Recent History of Power Spectral Density Functions in Seismic Input Motion Development ML24299A1612024-10-25025 October 2024 Advanced Sensors and Instrumentation Characterizing Nuclear Cybersecurity Using Ai/Ml (Presentation) ML24284A1152024-10-11011 October 2024 S9 Panel ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24282A9632024-10-0303 October 2024 S8P1-Sircar-Wang - NRC LBSM80 Workshop ML24276A0012024-10-0202 October 2024 Regulatory Implications of Advanced Technologies for Component Condition Monitoring in Nuclear Energy Systems ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24271A1332024-09-27027 September 2024 Xlpr - Looking to 20 Years of Continuous Development and Applications ML24254A2682024-09-16016 September 2024 Research Information Letter (Ril) 2024-12, Part II on 2023 NRC AMT Workshop ML24172A2962024-06-25025 June 2024 11 - NRC Support to Standards Orgs and Preparations for Future Reactors, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24172A2952024-06-25025 June 2024 10 - Overview of NRC Materials Research Supporting Long-Term Operation, NRC Presentation Slides, Industry / NRC Materials Programs Technical Information Exchange Public Meeting June 25-27, 2024 ML24162A2772024-06-10010 June 2024 Favpro Release Public Meeting Slides ML24137A0872024-05-14014 May 2024 Regulatory Considerations for Digital Twins for Nuclear Energy Systems - Presentation ML24115A0652024-04-23023 April 2024 Correct-by-Construction Reactor Protection Systems-PowerPoint Presentation RIL 2024-01, NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01)2024-03-31031 March 2024 NRC 3S Workshop Proceedings, Dec 5-6, 2023 (Ril 2024-01) ML24075A1902024-03-31031 March 2024 Nondestructive Examination Research at NRC 3-8-24 ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24081A1102024-03-18018 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems - Final ML24075A0272024-03-15015 March 2024 Some Issues in the Assurability of Safety Critical Digital Systems ML24064A2122024-03-0606 March 2024 Artificial Intelligence and Machine Learning in Nondestructive Examination and In-service Inspection Activities ML24016A1762024-01-16016 January 2024 Integrated Safety, Security, and Safeguards Ffr Research Project ML23342A1642023-12-0808 December 2023 Networking and Information Technology Research and Development Program Software Productivity Sustainability and Quality (Spsq) NRC - Sushil Birla December 14, 2023 ML23292A0922023-10-30030 October 2023 Advanced Sensor and Instrumentation - NRC Research Status Update ML23298A0312023-10-26026 October 2023 Advanced Fuel Cycle Storage and Transportation Research ML23324A2702023-10-24024 October 2023 Session - Key Takeaways ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23275A0022023-10-0505 October 2023 Domain Modeling & Domain Engineering an Enabler for Correct-by-Construction Design ML23272A0332023-09-29029 September 2023 Identifying Hazards in a System Design ML23264A0212023-09-28028 September 2023 Addressing Hazards from Common Causes in Engineering Di&C Systems Without Diverse Designs - State-of-the-Art ML23264A0252023-09-20020 September 2023 September 20, 2023 - Dent Presentation - John Mckirgan - Research Activities in Support of Digital Engineering in Nuclear Technology ML23262A9842023-09-19019 September 2023 MPA Seminar 2023 - Evaluation of Molten Salt Compatibility with Structural Alloys ML23256A0102023-09-18018 September 2023 State-of-the-art Approaches to Reduce the Potential for CCF in I&C Systems Conditions to Avoid the Need for Diversity in Design ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (RIPB) Standards ML23242A1182023-09-0707 September 2023 Research Challenges and Opportunities in the Safety Assurance of Nuclear Reactors ML23248A2142023-09-0606 September 2023 Reactor Safety: Regulatory Objectives & Framework ML23242A0032023-08-31031 August 2023 Reactor Protection System for the Virtual Ford Nuclear Reactor Designed-in Assurance ML23206A1592023-07-27027 July 2023 Identifying Hazards from Engineering Digital I&C Systems: State of the Art ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23187A4862023-07-0606 July 2023 Nrc’S Digital I&C Research for Application in Nuclear Power Plants – Status Update Presentation at Npic&Hmit 2023 ML23187A4762023-07-0606 July 2023 Advanced Sensors and Instrumentation –Nrc Research Status Update Presentation at Npic&Hmit 2023 ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1772023-06-15015 June 2023 28 - NRC - Fatigue Data Sharing 2024-09-27
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Global Sensitivity Analysis of xLPR using Metamodeling (Machine Learning) xLPR User Group Meeting August 18, 2021 1
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Background===
As part of applying xLPR to production analyses and to further validate the model, sensitivity analyses were conducted Sensitivity studies can be used to assess the impacts of uncertain parameters and analysis assumptions on the results Sensitivity analysis is a useful tool for identifying important uncertain model inputs that explain a large degree of the uncertainty in a quantity of interest Reasons to perform a sensitivity analysis:
Identify inputs that warrant greatest level of scrutiny, validation, and further sensitivity analysis Identify inputs that are key to the results Model validation Improve understanding of model behavior Reduction of model complexity (e.g., set unimportant inputs to constant values)
Inform advanced Monte Carlo sampling strategies (e.g., importance sampling)
Available techniques (see TLR-RES/DE/CIB-2021-11; ML21133A485):
One-at-a-time Local partial derivatives (e.g., Adjoint Modeling)
Variance-based (e.g., Sobol method)
Linear regression Metamodels 2
Sensitivity Analysis using Metamodels
- Can handle correlated inputs
- Accurately reflects non-monotonicity, non-linearity, and interactions
- Importance measures reflect the whole input space
- Several machine learning models automatically generate sensitivity metrics and down-select input variables based on information gained as part of the model fitting process
- Fitted model can be used in place of the original model to compute quantitative sensitivity measures at lower computational cost
- Focus of this presentation: using built-in sensitivity metrics generated during fitting 3
Metamodeling Analysis Workflow Run the probabilistic code and collect results Implement metamodeling code
- Import results from probabilistic code runs
- Transform results to prepare for input to metamodel fitting (e.g., accounting for spatially sampled variables)
- Fit the metamodel, including parameter optimization using cross-validation
- Extract and report input importance metrics Evaluate
- Examine goodness of fit metrics
- Compare importance ranking results from alternate metamodels
- Compare importance ranking results across different outputs of interest Iterate
- Collect more inputs
- Analyze different outputs
- Run different discrete configurations of the probabilistic code
- Use different metamodels / different metamodel parameters 4
Model Implementation Python 3.6 using Scikit Learn Package*
Machine learning models implemented:
Gradient Boosting Decision Trees Random Forest Decision Trees Linear Support Vector Machines All models used are classifiers (as opposed to regressors) because the outcomes are binary (yes/no). Regressor models would be used for scalar outputs.
All models include metrics for feature selection / feature importance Initial work focused on subset of 60 inputs:
Inputs that are expected to have high importance Distributed inputs Constant inputs uniformly distributed from 0.8 to 1.2 times constant value Outputs analyzed:
Occurrence leak Occurrence rupture (with and without inservice inspection (ISI))
- Scikit-learn: Machine Learning in Python, Pedregosa et al., JMLR 12, pp. 2825-2830, 2011 5
Spatially Distributed Inputs / Outputs Pipe section split into 19 subunits that can potentially crack Some inputs sampled on a subunit basis Some outputs also available on a subunit basis Aggregation methodology for subunit inputs / outputs
- Pipe subunit inputs and outputs: Analyze each pipe subunit and crack direction separately and average feature importance metrics
- Pipe subunit inputs and global outputs:
Average input across all pipe subunits (and crack types) and perform single analysis to determine feature importance
- This method may cause underreporting of importance metrics in comparison to alternative methods 6
Results: Leak Output Output: Leak (through wall crack) in any pipe subunit Analyzed using Gradient Boosted Trees Classifier (GBC)
Allows comparison between averaging subunit inputs and averaging subunit analysis outputs Top importance parameters for averaged subunit inputs:
Primary water stress-corrosion cracking (PWSCC) initiation parameters PWSCC growth parameters Operating Temp./Pressure Pipe outside diameter /
Thickness Welding Residual Stresses (WRS) - Hoop Pipe yield strength 7
Results: Rupture Output 8
Rupture full model output (not subunit basis)
Analyzed using all three machine learning classification algorithms Best prediction accuracy and CV score using Gradient Boosted Trees Classifier General agreement between all three fitted models Top importance parameters consistent with leak parameters PWSCC initiation Axial WRS ranked above Hoop (opposite of leak)
Changes in Importance Rankings Importance factor results may be compared between different scenarios/cases to show changes in the relative ordering of inputs Useful for:
Comparison between alternate metamodeling approaches Determining differences in sensitivity between different outputs of interest Comparing runs with different model settings (e.g., different ISI intervals) 9 Most important inputs consistently drive result Scatter indicates low confidence in relative ranking (in the noise)
Conclusions Key findings Relative comparisons (e.g., Axial vs. Circ, Rupture with/without ISI) are very useful for sanity checking the model Relatively high confidence in the identification of highest-impact inputs but low confidence in ordering of low-impact inputs General challenges Input distributions need to be selected carefully to get informative results A default real-world analysis input set is probably not sufficient Special consideration needed for inputs that are not continuous variables (e.g., settings flags) xLPR-specific challenges Prediction of simulation-wide outcomes using subunit-level sampled values Consideration of all inputs would be time-intensive (labor to extract sampled values and simulation time to adequately cover full input space)
Potential future improvements Include more inputs in the machine learning model Examine other outputs of interest (e.g., leak rate jump indicator)
Examine alternate configurations that cant be covered automatically using input distributions Use more advanced methods to improve on the relative rank importance metric (e.g., variance decomposition) 10