M230330: Slides/Supporting Presentation Material - D. Pickett - Briefing on Nuclear Regulatory Research ProgramML23083B366 |
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03/30/2023 |
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NRC/OCM |
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ML23067A027 |
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M230330 |
Download: ML23083B366 (7) |
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Category:Commission Meeting Slides
MONTHYEARML24019A1312024-01-19019 January 2024 M240125: Staff Slides - Joint Meeting of the Federal Energy Regulatory Commission (FERC) and the Nuclear Regulatory Commission (NRC) (Part 1) ML24017A1442024-01-17017 January 2024 M240123: Staff Slides - Briefing on International Activities ML24012A1552024-01-12012 January 2024 M240118: Slides - J. Lubinski - Strategic Programmatic Overview of the Decommissioning and Low-Level Waste and Nuclear Materials Users Business Lines ML23342A1502023-12-0808 December 2023 M231214: Slides - Briefing on Equal Employment Opportunity, Affirmative Employment, and Small Business ML23341A0092023-12-0707 December 2023 M231212: Slides - R. Augi - Discussion of the Administration'S Short- and Long-Term Domestic Uranium Fuel Strategy ML23341A0082023-12-0707 December 2023 M231212: Slides - K. Wendtland - Discussion of the Administration'S Short- and Long-Term Domestic Uranium Fuel Strategy ML23340A0152023-12-0606 December 2023 M231212: Slides - R. 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Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0662023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - T. Chapman - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0652023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - S. Schilthelm - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0642023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - N. Mcmurray - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0632023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - E. Lyman - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23130A0622023-05-16016 May 2023 M230516: Slides/Supporting Presentation Material - D. True - Update on 10 C.F.R. Part 53 Licensing and Regulation of Advanced Nuclear Reactors ML23103A1422023-04-20020 April 2023 M230420: Slides/Supporting Presentation - Strategic Programmatic Overview of the Fuel Facilities and the Spent Fuel Storage and Transportation Business Lines ML23083B3682023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - V. Rouyer - Briefing on Nuclear Regulatory Research Program ML23083B3642023-03-30030 March 2023 M230330: Agenda - Briefing on Nuclear Regulatory Research Program ML23083B3662023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - D. Pickett - Briefing on Nuclear Regulatory Research Program ML23083B3672023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - J. Shafer - Briefing on Nuclear Regulatory Research Program ML23083B3652023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - Z. Mohaghegh - Briefing on Nuclear Regulatory Research Program ML23083B9442023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - S. Chengelis - Briefing on Nuclear Regulatory Research Program ML23083B3632023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - M. Goff - Briefing on Nuclear Regulatory Research Program ML23083B3692023-03-30030 March 2023 M230330: Slides/Supporting Presentation Material - Staff Slides - Briefing on Nuclear Regulatory Research Program ML23032A3922023-02-0909 February 2023 M230209: Slides/Supporting Presentation Material - NRC Staff - Advanced Reactor Licensing Under 10 C.F.R. Parts 50 and 52 ML23023A0642023-01-26026 January 2023 M230126: Slides/Supporting Presentation Material - Staff Slides - Strategic Programmatic Overview of the Decommissioning and Low-Level Waste and Nuclear Materials Users Business Lines ML23018A0552023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - NRC Staff - Overview of Accident Tolerant Fuel Activities ML23018A0542023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - E. Lyman - Overview of Accident Tolerant Fuel Activities ML23018A0532023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - J. Bradfute - Overview of Accident Tolerant Fuel Activities ML23018A0522023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - R. Augi - Overview of Accident Tolerant Fuel Activities ML23018A0512023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - B. Adams - Overview of Accident Tolerant Fuel Activities ML23018A0502023-01-24024 January 2023 M230124: Slides/Supporting Presentation Material - B. Mccaughey - Overview of Accident Tolerant Fuel Activities ML22342A2392022-12-14014 December 2022 M221214: Slides/Supporting Presentation Material - Briefing on Equal Employment Opportunity, Affirmative Employment, and Small Business ML22341A2082022-12-0808 December 2022 M221208: Slides/Supporting Presentation Material - C. Back - Overview of Advanced Reactor Fuel Activities ML22336A1102022-12-0808 December 2022 M221208: Slides/Supporting Presentation Material - E. Lyman - Overview of Advanced Reactor Fuel Activities ML22336A1072022-12-0808 December 2022 M221208: Slides/Supporting Presentation Material - J. Vollmer - Overview of Advanced Reactor Fuel Activities ML22336A1092022-12-0808 December 2022 M221208: Slides/Supporting Presentation Material - R. 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Research Supporting Long-Term Storage of Nuclear Materials David Pickett Senior Program Manager, Center for Nuclear Waste Regulatory Analyses Nuclear Regulatory Commission Briefing on Nuclear Regulatory Research Program March 30, 2023 1
Long-Term Storage of Spent Nuclear Fuel Two central challenges
- Dry storage for much longer than originally envisioned
- Less is known about advanced reactor fuels and wastes in long-term storage Long-term storage must be safe for humans and the environment, and compatible with subsequent transportation, storage, and disposal, e.g.,
- Fuel cladding integrity
- Containment integrity A longer storage thermal management period could be needed, possibly at higher temperatures There has been much research, including sponsored by NRC, but important research needs remain Images from www.nrc.gov 2
CNWRA Support for NRC in Spent Nuclear Fuel Long-Term Storage Research Regulatory and technical gaps associated with regulating extended storage Thermal and gas flow modeling of dry cask systems using computational fluid dynamics (CFD)
Evaluated cask-drying requirements; developed vacuum drying test plan CFD model of airflow in a horizontal Experimental measurements of chloride-induced stress storage cask system corrosion cracking of stainless-steel canister materials Assessment of instrumentation for functional monitoring Technical development of aging management guidance for Stainless steel specimens in dry cask storage chloride-induced stress corrosion cracking tests 3
CNWRA Support for NRC in Spent Nuclear Fuel Long-Term Storage Licensing MAPS Report Process for Renewal Reviews Scoping Evaluation Several licensing reviews of Independent Spent Fuel Aging Management Review Storage Installations and Certificates of Compliance Development of the Managing Aging Processes in Time-Limited Aging Aging Management Analyses or Other Programs Storage (MAPS) license renewal guidance document Supporting Analyses Continued Storage rulemaking Related: Safety or environmental reviews for three centralized interim storage facilities Schematic of Related: Evaluation of information needs and irradiated metal regulatory gaps for storage of advanced reactor fuel pin wastes (TRISO, metal, molten salt) 4
Notable Ongoing U.S. Research Extended Storage Collaboration Program (ESCP)
- International cooperation in research and model benchmarking
- Aging management research, such as inspection technologies High Burnup Dry Storage Cask Research Project
- Monitoring & modeling temperatures
- Gas pressure and composition
- Sister rod studies Chloride-induced stress corrosion cracking
- Stress mitigation and crack repair
- Continued stress corrosion cracking testing and modeling, including improvements in duplicating relevant conditions
- Consequences of cracking Fuel condition, such as cladding integrity and hydride reorientation 5
High-Priority Research Needs High-burnup fuel extended storage (e.g., cladding and fuel integrity, thermal conditions)
Stress corrosion cracking (e.g., mitigation and repair, inspection, consequence models)
Thermal and decay heat model benchmarking Structural integrity under external loads (e.g., seismic)
Extended storage of advanced reactor spent fuels and associated wastes (e.g., fuel condition, identification and characterization of non-fuel wastes, criticality modeling, thermal characteristics)
Continued evaluation of greater-than-Class C waste if extended storage is needed (e.g., radiolytic gas production, thermal evolution) 6
Disclaimer This presentation describes work performed by the Center for Nuclear Waste Regulatory Analyses (CNWRA) and its contractors for the U.S. Nuclear Regulatory Commission (NRC) under Contract No. 31310018D0001.
This presentation is an independent product of CNWRA and does not necessarily reflect the views or regulatory positions of the NRC.
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