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MONTHYEARML24267A2452024-09-23023 September 2024 Session 3- Stakeholder Engagement - Advance Act of 2024, Section 401 ML24261B9742024-09-17017 September 2024 Master Slide Deck - Advanced Reactor Stakeholder Meeting - 2024-09-18 ML24248A2152024-09-0404 September 2024 Adapting Successful Hazard Analysis Approaches to New Hazards at the Nuclear Regulatory Commission ML24241A2342024-08-28028 August 2024 Bdh LIP Aug 29 2024 (002) - Final ML24218A1922024-07-30030 July 2024 NRC Presentation for 7-30-24 Public Meeting RG 1.247 Finalization Plan ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0202024-07-23023 July 2024 5 - RG 1.59 - Appendix K - Consideration for Applying Guidance to Advanced Reactor and Small Modular Reactors - Stakeholders Meeting 07/24/2024 ML24205A0192024-07-23023 July 2024 6-Licensing and Deployment Considerations for Noak Micro-Reactors - AR Stakeholders Meeting July 24 2024 ML24192A1272024-07-10010 July 2024 Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR ML24193A0772024-07-0909 July 2024 Nice ASME NQA-1 International Working Group (Iwg) - Emea (Europe, Middle East, & Africa) Iwg Trip Report Part 21 Presentation ML24190A1462024-07-0808 July 2024 Arcop Ws 4 Ppt - Public ML24173A1532024-06-27027 June 2024 20 - EPRI-NRC Cooperative Research Project: PWSCC Crack Initiation Characterization of Alloys 600/182 and Alloys 690/52/152-2024 Overview and Status ML24172A3052024-06-27027 June 2024 NRC- Perspective on ASME Code Efforts ML24172A3062024-06-27027 June 2024 Risk-Informing Materials Issues Risk Insights for Materials Issues NRC Perspective ML24163A0422024-06-11011 June 2024 Arcop Ws 3 Exercise Participant Handout ML24163A0412024-06-11011 June 2024 Arcop Ws 3 Exercise NRC Facilitator Handout ML24017A2992024-05-29029 May 2024 Public Meeting with the Nuclear Energy Institue (NEI) Regulatory Issue Task Force Presentation Slides, May 29, 2024 ML24144A1832024-05-23023 May 2024 Advanced Reactor Stakeholder Meeting 2024-05-23 ML24143A0802024-05-22022 May 2024 Arcap ISG Documents and Ticap Guidance Final Documents ML24142A5512024-05-21021 May 2024 Path Forward - Arsm Slides for 5-23-24 ML24142A5492024-05-21021 May 2024 Adv Rx Stakeholders - Risk Metrics Workshop - Rev 2 ML24141A1552024-05-20020 May 2024 NRC Slides Micro-Reactor Licensing May 23 2024 Advanced Reactor Stakeholder Meeting ML24123A2172024-05-15015 May 2024 Research Test Rx Construction Workshop Date 5.15.25 - Public ML24131A0142024-05-14014 May 2024 NRC Slides Micro-Reactor Licensing 5_14_24 Public Meeting ML24129A0752024-05-0808 May 2024 Arcop Work Shop 3 May 7 Version ML24122C6322024-05-0101 May 2024 ROP Bi-Monthly Meeting Slides on IP93100 Revision Update ML24052A2232024-03-14014 March 2024 Regulatory Information Conference (RIC) 2024 - Digital Exhibit - the NRC Is Advanced Reactor Ready! ML24030A6732024-03-13013 March 2024 RIC 2024 Krepel Presentation Adapting to a Changing Landscape ML24149A1492024-03-12012 March 2024 Enclosure 1 - 36th Annual RIC Presentation - Opening Remarks & Fulfilling the Mission Today and Tomorrow - Miranda Ross ML24067A2572024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Rtaylor Chair Opening Remarks ML24040A1832024-03-12012 March 2024 RIC 2024 T4 Slides - Vhuckabay Spent Fuel Reprocessing: Past, Present, and Future ML24067A2582024-03-12012 March 2024 RIC-2024 W14 Slides - NRC Ncoovert and Jgreives Future of Construction Oversight ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24030A0092024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2/14/2024 ML24043A1812024-02-14014 February 2024 Lessons Learned Report Slides Public Meeting on 2-14-24 Rev1 ML23338A2792023-11-30030 November 2023 Technology-Inclusive, Risk-Informed, and Performance-Based Licensing Approaches ML23306A1262023-11-0707 November 2023 Terrapower Public Outreach Meeting Wyoming Final (1) ML23298A1342023-10-27027 October 2023 DG-4034 (RG 4-7 Rev 4) Presentation on Population-Related Siting Oct 27 2023 ML23270B9282023-09-28028 September 2023 50.72 Aug 9 2023 Public Meeting Slides ML23256A0012023-09-20020 September 2023 Generic Issues Program Presentation - ROP Public Meeting ML23250A1292023-09-11011 September 2023 NRC Staff Presentation on the NRC Draft White Paper on Licensing and Deployment Considerations for Factory-Fabricated Micro-Reactors ML23219A1382023-08-0707 August 2023 50.72 Rulemaking Update ML23200A3372023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Josh Borromeo on Non-power Production and Utilization Facilities and Advanced Reactors Licensing ML23200A3392023-06-21021 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Travis Tate on Non-power Production and Utilization Facilities Oversight ML23200A3422023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Secy Option Paper for Enhanced Security of Special Nuclear Material ML23200A3432023-06-19019 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Beth Reed on Physical Security Event Notification and Suspicious Activity Reporting Rule ML23184A1282023-06-0707 June 2023 Advanced Reactors ML23122A1372023-05-0202 May 2023 NDE of AMT NRC Presentation ML23101A1232023-04-18018 April 2023 Staff Presentation on PRA Used to Implement Lmp in Support of Non-LWR Construction Permit Applications Under 10 CFR Part 50 2024-09-04
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Long Term Operation NRCs Current Research on Concrete U.S. Nuclear Regulatory Commission Office of Nuclear Regulatory Research Division of Engineering January 21, 2021
Outline Regulatory Research for Long-Term Operation (LTO)
Radiation Effects on Structures
- NRCs Confirmatory Research
- NRC-DOE-EPRI Joint Research Activities
- Harvesting Opportunities for Irradiated Concrete
- Other External Collaborations
Regulatory Research for LTO RES Mission To provide technical advice, tools, and information for meeting the NRCs mission, including resolving safety and security issues, making regulatory decisions, and promulgating regulations and guidance.
Objectives
- Provide technical bases for generic guidance (vs. plant-specific)
- Inform future revisions to SLR guidance (e.g., Interim Staff Guidance developments)
- Continue focus on aging management for systems, structures and components into LTO 3
NRCs Confirmatory Research (1/3)
Research Drivers
- NUREG/CR-7153 (EMDA Report) Vol 4, Aging of Concrete and Civil Structures, identifies radiation effects on concrete as low-knowledge but high significance
- Knowledge has improved but further research 2 can help address future technical issues and uncertainties
- Structures exposed to radiation are inaccessible for inspection.
- Be Ready for advanced/newer technologies and regulatory implications 4
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NRCs Confirmatory Research (2/3)
NRCs Confirmatory Research Activities
- State of knowledge on radiation-induced concrete degradation and its implications on NPP structures, Argonne National Laboratory (ANL), Report February 2020 (NUREG/CR to be published)
- Review and feedback on selected EPRI reports (2017-2018)
- Radiation evaluation methodology for concrete structures, Oak Ridge National Laboratory (ORNL), Report in June 2020, NUREG/CR to be published
- Development of theoretical models to predict properties of radiation damaged concrete, ANL and the University of Colorado, Report in December 2020
- In-house assessment of damage extension and structural capacity (2019 - 2023) 5
NRCs Confirmatory Research (3/3)
NRCs Confirmatory Research Activities Perform limited testing, modeling and numerical simulations of irradiated concrete behavior (including concrete-steel bonding) and develop methodology for structural evaluation at ORNL (2019 - 2023)
- Develop and conduct an experimental scoping study at LVR-15, Czech Republic to characterize the effects of irradiation on the bond properties of steel rebar in concrete
- Develop and validate a modeling methodology to assess the effects of irradiation on reinforced concrete biological shields in light water reactors
- Study size effect and develop a upscaling modeling strategy to verify applicability and significance of small-scale accelerated experimental data at the structural level
- Investigate rate effect (JEEP-II vs. LVR-15) 6
NRC-DOE-EPRI Joint Research Future focus areas
- Modeling of concrete damage mechanisms Confinement effects, steel-concrete bonding, cyclic loads, rate effects, scale effects (small specimen to structural scale), creep effects.
- Opportunities for harvesting and testing of concrete samples from decommissioned nuclear power plants for confirmation of regulatory research
- Methods for inspection/monitoring for the bio-shield and reactor vessel support structures 7
Harvesting Opportunities for Irradiated Concrete
- Ex-plant irradiated concrete is extremely valuable for confirmatory testing and for reducing uncertainties (concrete has been exposed to actual in-service plant operating conditions)
- Opportunity for harvesting irradiated concrete from the San Onofre Nuclear Generating Station (SONGS) has re-emerged
- NRC, ORNL, and EPRI technical coordination and planning for harvesting and research has started 8
External Collaborations
- Memoranda of Understanding with DOE and EPRI
- Bilateral and multilateral agreements
- International Committee on Irradiated Concrete
- Strategic international partnerships
- France, Japan, Canada
- IGALL, SALTO, TSO
- VERCORS
- ASCET 3
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Summary
- NRC/RES will continue collaboration with DOE and EPRI on concrete research to reduce regulatory uncertainty.
- Leveraging stakeholders helps facilitate regulatory research supporting safety during LTO.
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