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Category:Meeting Briefing Package/Handouts
MONTHYEARML24016A1762024-01-16016 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 ML23251A0572023-09-13013 September 2023 Session 1 - Importance of Standards, Opportunities for Participation and Collaboration ML23251A0582023-09-13013 September 2023 Session 2 - International Initiatives on Codes and Standards ML23251A0592023-09-13013 September 2023 Session 3 - Development of Risk-Informed and Performance-Based (Ripb) Standards ML23251A0602023-09-13013 September 2023 Session 4 - Development of Standards for Artificial Intelligence Systems 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 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 ML22280A1122022-10-0707 October 2022 Session 3 - Rapid Qualification of AMT Components - Is It Rocket Science? ML22266A2682022-09-28028 September 2022 Session 6 - Recent and Planned Developments and Updates in Codes and Standards Part 2 ML22266A2662022-09-28028 September 2022 Session 4 - Regulatory Initiatives for Streamlining Code & Standards Endorsement ML22174A3232022-06-27027 June 2022 NRC Presentation: Harvesting, an Overview and Historical Perspective ML22143A8292022-05-25025 May 2022 11 - 2022-05 NRC-Industry Meeting - Raynaud - Favor Update ML22143A8362022-05-25025 May 2022 18 - 2022 NRC-Industry Mtls Exchange Mtg - NRC Xlpr Presentation ML22143A8422022-05-25025 May 2022 27 - Zorita Ril ML22139A1372022-05-20020 May 2022 Presentation Slides for ACRS May 20, 2022 Meeting - ASME Sec XI Div. 2 ML22132A2992022-05-17017 May 2022 Staff Presentation for May 17, 2022 Public Meeting ML22102A1062022-04-0101 April 2022 ARPA-E Presentation-04-01-22-FINAL Research Activities in Nuclear Innovation and Regulation ML22060A0052022-03-0101 March 2022 Dt Public Meeting - NRC Slides ML21319A3902021-10-29029 October 2021 ASTM-E08-04 - Wrs Workshop - NRC Slides ML21230A3602021-08-18018 August 2021 NRC-EPRI Capstone Reports ML21230A3662021-08-18018 August 2021 Xlpr Seminar_Applications_Code Case N-770 ML21230A3642021-08-18018 August 2021 Xlpr Metamodeling ML21230A3632021-08-18018 August 2021 Xlpr Maintenance ML21230A3612021-08-18018 August 2021 Xlpr LOCA Frequencies Presentation for Xlpr User Group ML21230A3572021-08-18018 August 2021 LBB Studies V4 ML21230A3562021-08-18018 August 2021 International Pfm Code Benchmark ML21230A3582021-08-18018 August 2021 Lessons Learned - Xlpr Run Optimization ML21217A2602021-08-10010 August 2021 11 - NRC - Ni-Alloy Crack Growth ML21217A3042021-08-0909 August 2021 06 - NRC - Pfm Regulatory Guide Update - August 10-11, 2021 Industry/Nrc Materials Programs Technical Information Exchange ML21200A0722021-07-20020 July 2021 ACRS July 20 - Overview of ASME Section III Division 5 and NRC Review and Potential Endorsement.Pdf ML21173A1762021-06-22022 June 2021 Presentation to ACRS - Scheduled for June 25th 2021 in Pdf ML21011A2462021-03-0808 March 2021 RIC 2021 Digital Exhibit: Engagement with Codes & Standards Organizations 2024-01-16
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MONTHYEARML24016A1762024-01-16016 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 ML23251A0602023-09-13013 September 2023 Session 4 - Development of Standards for Artificial Intelligence Systems 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 NRCs 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 ML23146A0952023-06-14014 June 2023 11 - NRC - Favpro ML23146A1022023-06-14014 June 2023 18 - NRC - Xlpr Update ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities ML23060A1432023-03-16016 March 2023 Lund - TH23 - v6 ML23067A3242023-03-0707 March 2023 Presentation - Code Case N-894 Alternative Rules for Repair of Classes 1, 2, and 3 Austenitic Stainless Steel Piping with Thermal Fatigue Cracking ML23067A3402023-03-0707 March 2023 Presentation, N-853-1 Proposed Revision Technical Exchange with Electric Power Research Institute Welding and Repair Technology ML23019A1502023-01-19019 January 2023 Public Q&A and Closing ML23019A1672023-01-19019 January 2023 Review of 06/14/2022 Meeting ML23019A1562023-01-19019 January 2023 NRC Use Cases for LOCA Frequency Estimates ML23019A1692023-01-19019 January 2023 Walk-In and Agenda for Meeting with the EPRI to Discuss Use of the Extremely Low Probability of Rupture Code for LOCA Frequency Estimates ML22321A0212022-12-0202 December 2022 Alloy 690/52/152 Thermal Aging: NRC Plans and Activities 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 ML22174A3232022-06-27027 June 2022 NRC Presentation: Harvesting, an Overview and Historical Perspective ML22143A8422022-05-25025 May 2022 27 - Zorita Ril ML22143A8292022-05-25025 May 2022 11 - 2022-05 NRC-Industry Meeting - Raynaud - Favor Update ML22143A8362022-05-25025 May 2022 18 - 2022 NRC-Industry Mtls Exchange Mtg - NRC Xlpr Presentation ML22139A1372022-05-20020 May 2022 Presentation Slides for ACRS May 20, 2022 Meeting - ASME Sec XI Div. 2 ML22132A2992022-05-17017 May 2022 Staff Presentation for May 17, 2022 Public Meeting ML22102A1062022-04-0101 April 2022 ARPA-E Presentation-04-01-22-FINAL Research Activities in Nuclear Innovation and Regulation ML22060A0052022-03-0101 March 2022 Dt Public Meeting - NRC Slides ML21319A3902021-10-29029 October 2021 ASTM-E08-04 - Wrs Workshop - NRC Slides ML21230A3632021-08-18018 August 2021 Xlpr Maintenance ML21230A3662021-08-18018 August 2021 Xlpr Seminar_Applications_Code Case N-770 2024-01-16
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Overview of Component Integrity Research Activities Industry/NRC Materials Programs Technical Information Exchange May 23, 2018 Component Integrity Branch Division of Engineering Office of Nuclear Regulatory Research 1
1
Research Areas
- Raj Iyengar, Branch Chief, Component Integrity Branch
- Robert Tregoning, Senior Level Advisor
- Reactor Pressure Vessel Integrity - Mark Kirk
- Piping Integrity Patrick Raynaud/Sara Lyons
- Probabilistic Fracture Mechanics - Patrick Raynaud/Matt Homiack
- Nondestructive Examination - Carol Nove
- Advanced Nonlight Water Reactors (ANLWR) - Raj Iyengar/Matt Gordon/Sara Lyons
- ASME Section XI Coordination & 50.55a Regulatory Guide Rulemaking - Michael Benson/Bruce Lin 2
2
RPV Integrity
- Objective:
- Confirm the continued operating integrity of the RPV (including the SLR period)
- Assess the accuracy of formulae that predict future embrittlement states for vessel materials
- Driver: User need from NRR; Assistance request from NRO; RAR from NRR for training; Support of RGGIB in periodic RG reviews (e.g., RG 1.99)
- Collaboration: JAEA, JNRA
- RPV Embrittlement
- Assessment of shallow flaw effects on RPV integrity
- Prediction of fluence beyond the beltline
- REAP maintenance and addition of new surveillance data
- Codes & Standards: ASME Section XI; ASTM
- Finalization of PTS regulatory guide (RG 1.230) and technical basis document (NUREG 2163) 3 3
Accomplishment Highlight:
Late Blooming Phases
- Possible Concern: Possible rapid embrittlement in lowcopper steels with high nickel & manganese. Mechanism not accounted for by USNRC predictions.
- RES Review: Comprehensive literature review & surveillance data assessment demonstrate LBPs are not of concern for US RPVs.
- Level of Ni > 1% postulated for LBP occurrence
- Steel alloys / conditions of possible concern largely absent from USA fleet
- Evidence of delayed accelerated embrittlement is lacking
- Current Status: Ongoing research (DOE, intl.) to better understand LBPs. New data suggests no sudden late embrittlement and much smaller T values for USA steels.
08/15/2017 RPV Integrity l RES FO Brief 4 4
RPV Integrity Accomplishments and Path Forward
- TLR on RPV fluence evaluation methodology for beyond the active core region
- Independent review of NuScale Power Pressure and Temperature Limits (PTL) Methodology report for NRO
- Support NRO for NuScale application review
- Continue codes and standards support (ASTM E10; ASME CC N830 revision) 5 5
Piping Integrity
- Objective: Develop/Enhance analytical methods and tools to assess structural integrity of reactor piping systems
- Driver: NRR User Need Request
- Collaboration: EPRI, NEA/CSNI
- Development of modeling guidelines for assessment of weld residual stress (WRS) effects in assessment of component integrity
- Assessment of research and industry experience in peening of reactor components
- Participation in ASME Boiler and Pressure Vessel Code,Section XI
- Coordination of ASME BPV Code Case Regulatory Guides to incorporate by reference into 10 CFR 50.55a
- Evaluation of Extended Finite Element Method (xFEM) for applicability in crack growth (PWSCC) analyses 6
Ongoing Activity:
Applying xFEM Techniques to PWSCC Growth
- Application of Extended Finite Element Method (xFEM) to predict PWSCC crack growth in 3D component geometries.
- Uses idealized crack shape and growth model (semielliptical)
- Assumes planar (2D) crack growth
- Uses 2D WRS profile for crack growth which is path dependent and user defined
- Meshindependent analysis of flaws
- SIF calculation of multiple cracks shapes without major changes to model
- 3D crack growth without remeshing
- Participation in international effort on benchmarking of xFEM capabilities.
(OECDCSNI) 7
Piping Integrity Accomplishments and Path Forward
- Draft NUREG on WRS validation
- Section XI Standards Committee and Executive Committee participation
- Issued draft Regulatory Guides for ASME Code Cases, 20092013 and 2015 editions to incorporate by reference into 10 CFR 50.55a
- Issue final reports on WRS validation
- Develop and implement research plan for validation xFEMA analysis for PWSCC predictions
- Continue ASME Section XI engagement
- Prepare draft Regulatory Guides for ASME Code Cases for 2017 Edition of the Boiler and Pressure Vessel Code 8
8
Probabilistic Component Integrity
- Objective: Develop probabilistic methods to ensure structural integrity of piping systems
- Driver: NRR User Need Request
- Collaboration: EPRI, JNRA, JAEA, SSM, CNSC
- Support NRR in the acceptance and application of xLPR v2
- Development of Probabilistic Fracture Mechanics Regulatory Guide
- Continue effort on V&V of FAVOR code, maintenance, applications, development, and modernization 9
9
Probabilistic Component Integrity Accomplishments and Path Forward
- xLPR verification and validation testing
- xLPR code theory and handson training provided to NRC staff
- xLPR PWSCC initiation model parameter development, confirmatory analyses, and validation
- Completed draft report on Increasing Confidence in PFM Analyses
- Initiated work on FAVOR V&V, maintenance, and applications
- Support NRR regulatory acceptability review for xLPR
- Complete efforts to ensure public release of xLPR
- Initiate studies on leakbeforebreak applications with xLPR
- Develop PFM Draft Regulatory Guide, with NUREG technical basis document and PFM pilot studies to test guidance
- Bring FAVOR up to modern standards, adapt FAVOR to solve evolving reactor pressure vessel issues 10 10
Non-Destructive Examination
- Objective: Evaluate effectiveness and reliability of NDE techniques
- Driver: NRR User Need Request
- Collaboration: EPRI, DOE, International
- Completion of comprehensive summary of NDE research on CASS and assessment of stateoftheart in inspecting welds in CASS materials
- Assessment of industrys CASS round robin (rigorous, statistically based)
- Provide technical basis for conducting, interpreting, and applying the results of ultrasonic testing (UT) Modeling
- Assess the effects of incomplete examination coverage
- Assessment of human factors issues in NDE
- Support codes & standards activities (ASME - Section XI)
- Assessment of inspection systems for storage casks 11 11
ANLWR Materials and Component Integrity
- Objective: Assess the performance needs and issues for structural materials to be used in advanced nonLWRs (ANLWRs); Support the development of a regulatory framework for materialsrelated issues for ANLWRs
- Driver: NRC Vision and Strategy on ANLWRs
- Strategy 2: Acquire/develop sufficient computer codes and tools to perform nonLWR regulatory reviews
- Strategy 4: Facilitate industry codes and standards needed to support the nonLWR life cycle
- Identification of regulatory gaps for sodium fast reactors and molten salt reactors, building on the past efforts for hightemperature gas reactors
- Assessment of materials/component integrity issues for molten salt reactors (MSR)
- Operational experience compendia for materials/component integrity issues for sodium fast reactors (SFR) and hightemperature gas reactors (HTGR)
- Participation in ASME Codes and Standards Sections III and XI activities 12 12
ANLWR Materials Accomplishments
- Technical gap assessment for materials/component integrity for molten salt reactors - ORNL Draft report summary:
- Limited high-temperature creep data at the highest possible core outlet temperatures
- Limited data on salt purity effects on coolant compatibility and performance
- Limited data and mechanistic understanding on irradiation degradation effects
- Operational experience compendia for sodium fast reactors (SFRs) and high-temperature gas reactors (HTGR) - EWC-Commercial Over 100 OpE sources have been identified and reviewed for SFRs
[Phenix, SuperPhenix, FFTF, EBR-II] and HTGRs [Fort St Vrain, Peach Bottom, AVR and THTR-300]
- Weld design and quality are critical for SFRs
- Design flaws seem to dominate HTGRs, resulting in unexpectedly high temperatures, moisture and oxygen ingress, and trapped pebbles Separate bilateral engagements with Office of Nuclear Regulation, UK; IRSN- France; and JAEA and JNRZ - Japan 13 13
ANLWR Materials Accomplishments and Path Forward
- Support knowledge and data enhancement of environmental effects on reactor components (internals, piping, welds, coatings) at high temperatures. (corrosion, radiation effects)
- Develop/Enhance computational codes for component integrity applicable to ANLWRs
- Explore opportunities to obtain information, data, and assessment tools through domestic and international collaboration
- Conduct research activities to develop technical bases to resolve major materials related issues 14 14