|
|
Line 16: |
Line 16: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:}} | | {{#Wiki_filter:Leak-Before-Break Studies NRC Phase 1 LBB Report/ Plans for LBB Phase 2 and EPRI Report August 18, 2021 1 |
| | |
| | Introduction |
| | - Application of xLPR to a real-life problem: Impact of primary water stress-corrosion cracking (PWSCC) on a Reactor Vessel Outlet Nozzle (RVON) for a Westinghouse 4-loop Nuclear Power Plant |
| | - Largest number of same weld type with Alloy 82/182 within leak-before-break (LBB)-approved line segments in the U.S. nuclear fleet |
| | - Coordinated effort by NRC/RES and EPRI via a memorandum of understanding, with the following goals: |
| | : 1. Develop a defensible strategy of xLPR use for risk-informed decision making |
| | : 2. Initiate the first phase of a system-level analysis considering a loop or a whole unit |
| | : 3. Test different Quantities of Interest (QoIs) as criteria for decision-making |
| | - Program to be followed by a second phase considering other weld locations and combination of results at the system level 2 |
| | |
| | Problem considered |
| | * Reactor Vessel Outlet Nozzle (RVON) for a generic Westinghouse 4-loop pressurized-water reactor |
| | - 34 inches diameter (0.869 m) |
| | - 2.6 inches thickness (0.0663 m) |
| | - Temperature : 320.5°C |
| | - Pressure 15.41 MPa |
| | - Focus on circumferential cracks (axial cracks considered in sensitivity run) |
| | - Simulation time : 80 years (timestep : 1 month) |
| | - Large number of uncertain inputs (e.g., |
| | welding residual stresses (WRS), crack initiation parameters, crack growth parameters) 3 |
| | |
| | Quantities of Interest |
| | * Probability of rupture with leak rate detection |
| | * Probability of Leak Rate Jump: going from less than 10 gpm to more than 50 gpm in one timestep |
| | * Probabilistic LBB ratio (critical crack size over detectable leakage crack size) |
| | - Similar to the deterministic ratio in NRC Standard Review Plan Section 3.6.3 |
| | - Estimated for each realization leading to a distribution of the LBB ratio |
| | * Distribution of time from detectable through wall crack to rupture |
| | * Outputs in blue are directly estimated in xLPR - other outcomes need postprocessing but can be done easily in Excel 4 |
| | |
| | Probabilistic Approach |
| | - Considered acceptance threshold is 10-6 occurrence per reactor year. |
| | - Equivalent to probability of occurrence of 8 x 10-5 over 80 years |
| | - Sample size considered between 70,000 and 100,000 should lead to respectively 5 to 8 events on average, if the probability is higher than the threshold |
| | - Analysis conditional on having a crack at time 0 use sample size of 5,000 since probability of having crack over 80 years is in the 10-3 range |
| | - Large amount of data saved, so a single probabilistic run was not practical |
| | - 7 replicates of 10,000 to 15,000 sample size, each with different random seeds, were run and combined |
| | - Crack leak rate, inner length, outer length, and critical ratio extracted to estimate the composite QoIs 5 |
| | |
| | Reference results (1/2) |
| | - Probability of leak rate jump and rupture with leak rate detection too low to occur over 100,000 realizations |
| | - Good on a regulatory standpoint since it shows the risk is below the acceptable range. Not ideal on a scientific standpoint as there is no quantification of the risk |
| | - Rather, alternate QoIs are presented (P(1st crack), |
| | P(1st leak) and P(rupture) without inspection or leak rate detection) 6 |
| | |
| | Reference results (2/2) |
| | * Composite QoIs give results for different criteria (for instance 1 gpm and 10 gpm leak rate detection limits) |
| | * Results are conditional on having pipe rupture and do not reflect this probability 10 gpm 10 gpm 1 gpm 1 gpm Time between detectable LBB ratio leak rate and rupture 7 |
| | |
| | Sensitivity Case: Impact of WRS Profile (1/2) |
| | * New WRS mean profile with similar uncertainty applied |
| | * Larger mean at insider diameter leads to higher probability of 1st crack |
| | * Lower minimum reduces probabilities of 1st leak and rupture relative to the reference value Still, no ruptures with leak rate detection or leak rate jump events 8 |
| | |
| | Sensitivity Case: Impact of WRS Profile (2/2) |
| | * Stronger impact on LBB ratio and LBB time lapse than for the reference case |
| | * Use of multiple metrics gives more insights on scenario differences and increases confidence in the results 9 |
| | |
| | Sensitivity Case: Impact of Temperature |
| | * Change in operating Still, no ruptures with leak rate detection or leak rate jump events temperature (deterministic value) from 320.8°C to 330°C |
| | * Considered large change since the same temperature is applied through the whole 80-year simulation time |
| | * Temperature affects initiation and growth, thus impact in all three metrics presented 10 |
| | |
| | Conclusions and Perspectives |
| | * This study helped identify bugs and enhancements for xLPR (they will be fixed in Version 2.2) but overall, the code is ready to be used for regulatory decisionmaking |
| | * Beyond the already available outputs, composite QoIs can be defined and calculated in post-processing without too much effort |
| | * This study helped identify advantages and drawbacks for each QoI considered and showed the benefit of using multiple metrics |
| | * This first analysis serves as a good basis to extend the process to other weld types (pressurizer surge line, reactor coolant pump ) and estimate risk at the system level 11}} |
|
---|
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
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Leak-Before-Break Studies NRC Phase 1 LBB Report/ Plans for LBB Phase 2 and EPRI Report August 18, 2021 1
Introduction
- Application of xLPR to a real-life problem: Impact of primary water stress-corrosion cracking (PWSCC) on a Reactor Vessel Outlet Nozzle (RVON) for a Westinghouse 4-loop Nuclear Power Plant
- Largest number of same weld type with Alloy 82/182 within leak-before-break (LBB)-approved line segments in the U.S. nuclear fleet
- Coordinated effort by NRC/RES and EPRI via a memorandum of understanding, with the following goals:
- 1. Develop a defensible strategy of xLPR use for risk-informed decision making
- 2. Initiate the first phase of a system-level analysis considering a loop or a whole unit
- 3. Test different Quantities of Interest (QoIs) as criteria for decision-making
- Program to be followed by a second phase considering other weld locations and combination of results at the system level 2
Problem considered
- Reactor Vessel Outlet Nozzle (RVON) for a generic Westinghouse 4-loop pressurized-water reactor
- 34 inches diameter (0.869 m)
- 2.6 inches thickness (0.0663 m)
- Temperature : 320.5°C
- Pressure 15.41 MPa
- Focus on circumferential cracks (axial cracks considered in sensitivity run)
- Simulation time : 80 years (timestep : 1 month)
- Large number of uncertain inputs (e.g.,
welding residual stresses (WRS), crack initiation parameters, crack growth parameters) 3
Quantities of Interest
- Probability of rupture with leak rate detection
- Probability of Leak Rate Jump: going from less than 10 gpm to more than 50 gpm in one timestep
- Probabilistic LBB ratio (critical crack size over detectable leakage crack size)
- Similar to the deterministic ratio in NRC Standard Review Plan Section 3.6.3
- Estimated for each realization leading to a distribution of the LBB ratio
- Distribution of time from detectable through wall crack to rupture
- Outputs in blue are directly estimated in xLPR - other outcomes need postprocessing but can be done easily in Excel 4
Probabilistic Approach
- Considered acceptance threshold is 10-6 occurrence per reactor year.
- Equivalent to probability of occurrence of 8 x 10-5 over 80 years
- Sample size considered between 70,000 and 100,000 should lead to respectively 5 to 8 events on average, if the probability is higher than the threshold
- Analysis conditional on having a crack at time 0 use sample size of 5,000 since probability of having crack over 80 years is in the 10-3 range
- Large amount of data saved, so a single probabilistic run was not practical
- 7 replicates of 10,000 to 15,000 sample size, each with different random seeds, were run and combined
- Crack leak rate, inner length, outer length, and critical ratio extracted to estimate the composite QoIs 5
Reference results (1/2)
- Probability of leak rate jump and rupture with leak rate detection too low to occur over 100,000 realizations
- Good on a regulatory standpoint since it shows the risk is below the acceptable range. Not ideal on a scientific standpoint as there is no quantification of the risk
- Rather, alternate QoIs are presented (P(1st crack),
P(1st leak) and P(rupture) without inspection or leak rate detection) 6
Reference results (2/2)
- Composite QoIs give results for different criteria (for instance 1 gpm and 10 gpm leak rate detection limits)
- Results are conditional on having pipe rupture and do not reflect this probability 10 gpm 10 gpm 1 gpm 1 gpm Time between detectable LBB ratio leak rate and rupture 7
Sensitivity Case: Impact of WRS Profile (1/2)
- New WRS mean profile with similar uncertainty applied
- Larger mean at insider diameter leads to higher probability of 1st crack
- Lower minimum reduces probabilities of 1st leak and rupture relative to the reference value Still, no ruptures with leak rate detection or leak rate jump events 8
Sensitivity Case: Impact of WRS Profile (2/2)
- Stronger impact on LBB ratio and LBB time lapse than for the reference case
- Use of multiple metrics gives more insights on scenario differences and increases confidence in the results 9
Sensitivity Case: Impact of Temperature
- Change in operating Still, no ruptures with leak rate detection or leak rate jump events temperature (deterministic value) from 320.8°C to 330°C
- Considered large change since the same temperature is applied through the whole 80-year simulation time
- Temperature affects initiation and growth, thus impact in all three metrics presented 10
Conclusions and Perspectives
- This study helped identify bugs and enhancements for xLPR (they will be fixed in Version 2.2) but overall, the code is ready to be used for regulatory decisionmaking
- Beyond the already available outputs, composite QoIs can be defined and calculated in post-processing without too much effort
- This study helped identify advantages and drawbacks for each QoI considered and showed the benefit of using multiple metrics
- This first analysis serves as a good basis to extend the process to other weld types (pressurizer surge line, reactor coolant pump ) and estimate risk at the system level 11