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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 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 ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data 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 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 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 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 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 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 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 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 ML23152A1802023-06-14014 June 2023 13 - NRC - Materials Harvesting Activities 2024-09-27
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
Overview of Component Integrity Research ActivitiesIndustry/NRC Materials Programs Technical Information Exchange 1 1May23,2018ComponentIntegrityBranch DivisionofEngineeringOfficeofNuclearRegulatoryResearch Research Areas
- PointsofContact-RajIyengar,BranchChief,ComponentIntegrityBranch-RobertTregoning,SeniorLevelAdvisor*ResearchAreas-ReactorPressureVesselIntegrity-MarkKirk-PipingIntegrityPatrickRaynaud/SaraLyons-ProbabilisticFractureMechanics-PatrickRaynaud/MattHomiack-NondestructiveExamination-CarolNove-AdvancedNonlightWaterReactors(ANLWR)-RajIyengar/MattGordon/SaraLyons-ASMESectionXICoordination&50.55aRegulatoryGuideRulemaking-MichaelBenson/BruceLin 2 2 RPV Integrity
- Overview-Objective:*ConfirmthecontinuedoperatingintegrityoftheRPV(includingtheSLRperiod)*Assesstheaccuracyofformulaethatpredictfutureembrittlementstatesforvesselmaterials-Driver:UserneedfromNRR;AssistancerequestfromNRO;RARfromNRRfortraining;SupportofRGGIBinperiodicRGreviews(e.g.,RG1.99)-Collaboration:JAEA,JNRA*Ongoingactivities
-RPVEmbrittlement
- AssessmentofshallowflaweffectsonRPVintegrity*Predictionoffluencebeyondthebelt line*REAPmaintenanceandadditionofnewsurveillancedata-Codes&Standards:ASMESectionXI;ASTM-FinalizationofPTSregulatoryguide(RG1.230)andtechnicalbasisdocument(NUREG2163)3 3 08/15/2017RPVIntegritylRESFOBrief4 Accomplishment Highlight:Late Blooming Phases
- PossibleConcern:Possiblerapidembrittlementinlowcoppersteelswithhighnickel&manganese.MechanismnotaccountedforbyUSNRCpredictions.
- RESReview:Comprehensiveliteraturereview&surveillancedataassessmentdemonstrateLBPsarenot ofconcernforUSRPVs.-LevelofNi>1%postulatedforLBPoccurrence
-Steelalloys/conditionsofpossibleconcernlargelyabsentfromUSAfleet-Evidenceofdelayedacceleratedembrittlementislacking*CurrentStatus:Ongoingresearch(DOE,intl.)tobetterunderstandLBPs.Newdatasuggestsno"sudden"lateembrittlementandmuchsmallerTvaluesforUSAsteels.4 RPV Integrity Accomplishments and Path Forward
-TLRonRPVfluenceevaluationmethodologyforbeyondtheactivecoreregion-IndependentreviewofNuScalePowerPressureandTemperatureLimits(PTL)MethodologyreportforNRO*PathForward-SupportNROforNuScaleapplicationreview-Continuecodesandstandardssupport(ASTME10;ASMECCN830revision)5 5 Piping Integrity
- Overview-Objective:Develop/Enhanceanalyticalmethodsandtoolstoassessstructuralintegrityofreactorpipingsystems-Driver:NRRUserNeedRequest-Collaboration:EPRI,NEA/CSNI*Ongoingactivities
-Developmentofmodelingguidelinesforassessmentofweldresidualstress(WRS)effectsinassessmentofcomponentintegrity-Assessmentofresearchandindustryexperienceinpeeningofreactorcomponents
-ParticipationinASMEBoilerandPressureVesselCode,SectionXI-CoordinationofASMEBPVCodeCaseRegulatoryGuidestoincorporatebyreferenceinto10CFR50.55a-EvaluationofExtendedFiniteElementMethod(xFEM)forapplicabilityincrackgrowth(PWSCC)analyses 6 7OngoingActivity: ApplyingxFEMTechniquestoPWSCCGrowth*ApplicationofExtendedFiniteElementMethod(xFEM)topredictPWSCCcrackgrowthin3Dcomponentgeometries.
- ConventionalFEM:-Usesidealizedcrackshapeandgrowthmodel(semielliptical)
-Assumesplanar(2D)crackgrowth-Uses2DWRSprofileforcrackgrowthwhichispathdependentanduserdefined*xFEM:-Meshindependentanalysisofflaws-SIFcalculationofmultiplecracksshapeswithoutmajorchangestomodel-3Dcrackgrowthwithoutre meshing*ParticipationininternationaleffortonbenchmarkingofxFEMcapabilities.(OECD CSNI)
Piping Integrity Accomplishments and Path Forward
-DraftNUREGonWRSvalidation
-SectionXIStandardsCommitteeandExecutiveCommitteeparticipation
-IssueddraftRegulatoryGuidesforASMECodeCases,2009 2013and2015editionstoincorporatebyreferenceinto10CFR50.55a*PathForward-IssuefinalreportsonWRSvalidation-DevelopandimplementresearchplanforvalidationxFEM AanalysisforPWSCCpredictions
-ContinueASMESectionXIengagement
-PreparedraftRegulatoryGuidesforASMECodeCasesfor2017EditionoftheBoilerandPressureVesselCode 8 8 Probabilistic Component Integrity
- Overview-Objective:Developprobabilisticmethodstoensurestructuralintegrityofpipingsystems-Driver:NRRUserNeedRequest-Collaboration:EPRI,JNRA,JAEA,SSM,CNSC*Ongoingactivities
-SupportNRRintheacceptanceandapplicationofxLPRv2-DevelopmentofProbabilisticFractureMechanicsRegulatoryGuide-ContinueeffortonV&VofFAVORcode,maintenance,applications,development,andmodernization 9 9 Probabilistic Component Integrity Accomplishments and Path Forward
-xLPRverificationandvalidationtesting-xLPRcodetheoryandhands ontrainingprovidedtoNRCstaff-xLPRPWSCCinitiationmodelparameterdevelopment,confirmatoryanalyses,andvalidation
-Completeddraftreporton"IncreasingConfidenceinPFMAnalyses"-InitiatedworkonFAVORV&V,maintenance,andapplications
- PathForward-SupportNRRregulatoryacceptabilityreviewforxLPR-CompleteeffortstoensurepublicreleaseofxLPR-InitiatestudiesonleakbeforebreakapplicationswithxLPR-DevelopPFMDraftRegulatoryGuide,withNUREGtechnicalbasisdocumentandPFMpilotstudiestotestguidance-BringFAVORuptomodernstandards,adaptFAVORtosolveevolvingreactorpressurevesselissues 10 10 Non-Destructive Examination
- Overview-Objective:EvaluateeffectivenessandreliabilityofNDEtechniques
-Driver:NRRUserNeedRequest-Collaboration:EPRI,DOE,International
-CompletionofcomprehensivesummaryofNDEresearchonCASSandassessmentofstate of the artininspectingweldsinCASSmaterials-Assessmentofindustry'sCASSroundrobin(rigorous,statistically based)-Providetechnicalbasisforconducting,interpreting,andapplyingtheresultsofultrasonictesting(UT)Modeling-Assesstheeffectsofincompleteexaminationcoverage-AssessmentofhumanfactorsissuesinNDE-Supportcodes&standardsactivities(ASME-SectionXI)-Assessmentofinspectionsystemsforstoragecasks 11 11 ANLWR Materials and Component Integrity
- Overview-Objective:AssesstheperformanceneedsandissuesforstructuralmaterialstobeusedinadvancednonLWRs(ANLWRs);SupportthedevelopmentofaregulatoryframeworkformaterialsrelatedissuesforANLWRs-Driver:NRCVisionandStrategyonANLWRs*Strategy2:Acquire/developsufficientcomputercodesandtoolstoperformnonLWRregulatoryreviews*Strategy4:FacilitateindustrycodesandstandardsneededtosupportthenonLWRlifecycle*Ongoingactivities
-Identificationofregulatorygapsforsodiumfastreactorsandmoltensaltreactors,buildingonthepasteffortsforhightemperaturegasreactors-Assessmentofmaterials/componentintegrityissuesformoltensaltreactors(MSR)-Operationalexperiencecompendiaformaterials/componentintegrityissuesforsodiumfastreactors(SFR)andhightemperaturegasreactors(HTGR)-ParticipationinASMECodesandStandardsSectionsIIIandXIactivities 12 12 ANLWR Materials Accomplishments
- Technical gap assessment for materials/component integrity for molten salt reactors -ORNLDraft 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-
CommercialOver 100 OpEsources 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*Thermal fatigue is much more significant in SFRs than LWRs
- Design flaws seem to dominate HT GRs, resulting in unexpectedly high temperatures, moisture and oxygen ingress, and "trapped" pebblesSeparate bilateral engagements with Office of Nuclear Regulation, UK; IRSN-France; and JAEA and JNRZ -Japan 13 13 ANLWR Materials Accomplishmentsand Path Forward
- Supportknowledgeanddataenhancementofenvironmentaleffectsonreactorcomponents(internals,piping,welds,coatings)athightemperatures.(corrosion,radiationeffects)*Develop/EnhancecomputationalcodesforcomponentintegrityapplicabletoANLWRs*Exploreopportunitiestoobtaininformation,data,andassessmenttoolsthroughdomesticandinternationalcollaboration
- Conductresearchactivitiestodeveloptechnicalbasestoresolvemajormaterialsrelatedissues 14 14