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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 ML24065A0092024-03-31031 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 ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides 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 ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities 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
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) 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 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 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 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 ML24065A0092024-03-31031 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 ML24089A1562024-03-29029 March 2024 NRC Support to Standards Orgs and Preparations for Future Reactors ML24089A1582024-03-29029 March 2024 New & Advanced Reactor: Codes & Standards - Slides 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 ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2702023-10-24024 October 2023 Session - Key Takeaways 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 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 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 ML23187A4762023-07-0606 July 2023 Advanced Sensors and Instrumentation –Nrc Research Status Update Presentation at Npic&Hmit 2023 ML23187A4862023-07-0606 July 2023 Nrc’S Digital I&C Research for Application in Nuclear Power Plants – 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 ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation 2024-09-27
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Text
Global Sensitivity Analysis of xLPR using Metamodeling (Machine Learning) xLPR User Group Meeting August 18, 2021 1
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
- Examine goodness of fit metrics
- Compare importance ranking results from alternate metamodels
- Compare importance ranking results across different outputs of interest
- 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*
- 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
- 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
- Rupture full model output (not subunit basis)
- 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) 8
Changes in Importance Rankings
- Importance factor results may be compared between different Most important inputs scenarios/cases to consistently drive result show changes in the relative ordering of inputs
- Comparison between alternate metamodeling approaches Scatter indicates low
- Determining differences confidence in relative in sensitivity between ranking (in the noise) different outputs of interest
- Comparing runs with different model settings (e.g., different ISI intervals) 9
Conclusions
- 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
- 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)
- 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