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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
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
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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Advanced Fuel Cycle Storage and Transportation Research Reactor Engineering Branch Division of Engineering Office of Nuclear Regulatory Research The views expressed in this presentation are those of the authors and do not reflect the views of the U.S. Nuclear Regulatory Commission. This material is declared a work of the U.S.
Government and is not subject to copyright protection in the United States. Approved for public release; distribution is unlimited.
Outline Advanced Advanced Fuel Cycle Storage &
External Reactors & Transportation Research Engagement Fuels Licensing Coordination Readiness
Preparing for an Increase in New &
Advanced Reactors
Preparing for Advanced Fuel Cycle Licensing
NRC Research Activities in Spent Fuel Storage and Transportation Increased interest and Research Activities and Outcome activities in Considerations development of Intended to ensure staff commercial advanced Research Activities: readiness to review near-reactors and their fuels To expand the NRC understanding term licensing/certification of the key technical and regulatory actions, support pre-considerations related to these application engagements, NRC Assessment:
ANLWR fuel types. and inform guidance Ensure readiness to license the development.
storage and transportation of various Considerations:
ANLWR fuels within the flexible May include various waste forms regulatory framework.
and waste streams, radiochemistry of constituents, storage canister performance and degradation, Advanced fuel types include:
actinide separation, tritium Metal fuel, TRISO pebbles, and management strategies, and other molten salt fuels.
attributes.
Advanced Fuel Cycle Storage Transportation
- Advanced fuel cycles have several changes relative to those of historic U.S. LWR fuels, which will affect storage and transportation.
- High enrichments from High-Assay Low-Enriched
- The U.S. NRC regulatory framework does not require any major changes, but there are some technical issues being evaluated.
Front end: HALEU and Salt Fuel Molten Salt Waste Processing Advanced Fuel Cycle Storage & Molten Salt Waste Forms Transportation MSR Off-gas Management Research Graphite Waste Management Guidance (TRISO, Metal, Salt)
- Assessment of potential transportation and preparation of High-Assay Low Enriched Uranium HALEU (HALEU) fuel materials and salt fuel and Salt Preliminary insights include:
Fuel Part 71 appears flexible enough to accommodate HALEU transportation package needs Criticality benchmarks Potential for co-located fuel fabrication facility and MSR
Reviewed information related to high-level plans for processing, storing, and transporting MSR salt waste Molten Salt Key Observations: Reactor Fuels
- Potential for co-located chemical processing facilities
- Tritium management strategies are needed for some designs
- Consider transportation of fuel salt and waste
- Potential need for long term management or immobilization Future work will look at storage casks and transportation considerations for molten salt waste and potential for salt processing
Spent Fuel Reprocessing 2009 Draft regulatory basis 2013 Commission Reprocessing and regulatory approved recommendati regulatory gap analysis framework path on in SECY-13-0093 to (SECY-09-0082). 23 forward submitted to develop Part 7X, focus gaps were identified the Commission (SECY-on Gap 5 11-0163) 2011 2021 Rulemaking cancelled.
Beginning efforts to SECY-21-0026, staff Work stopped on Gap 5; "get ready" for any can adequately address decrease in commercial potential licensing needs interest licensing applications through the existing regulatory framework" 2022 2016
Reprocessing Research Activities EXTERNAL INTERNAL TECHNICAL COORDINATION TO COORDINATION TECHNICAL ASSESSMENT OF GATHER ON TECHNICAL BASIS TO CONSIDERATIONS INFORMATION ON PERSPECTIVES INFORM FOR POTENTIAL AND PRE- GUIDANCE PYROPROCESSING REPROCESSING APPLICATION UPDATES TECHNOLOGIES ACTIVITIES
FOSTERING PARTNERSHIPS EPRI VENDORS PUBLIC US NRC NGOs International DOE SDOs
NRC is participating as observers for periodic Research Coordination Meetings between SFERA participants:
To sustain and improve the IAEA's Member States technical knowledge base on IAEA Coordinated the long-term behavior of power reactor spent fuel Research Project (CRP) through sharing and disseminating information, Spent Fuel Research and reporting topical research carried-out in participating Assessment (SFERA) Member States and by documenting on-going spent fuel performance
Forward Looking Research
- University Nuclear Leadership ProgramSupports NRCs safety and security mission by awarding university-led research projects relevant to the NRC mission that complement its current research portfolio and help the NRC prepare for upcoming challenges
- Future Focused Research ProgramSupports the identification, prioritization, performance, and monitoring of research activities intended to help the NRC prepare for upcoming challenges that have longer-term ( 3 years) horizons and greater risk opportunities than considered in typical activities Digital Twins - Licensing Modernization Regulatory Project - Operating Viability Reactors Integration of Nuclear Nano Key Attributes Safety, Technology - for Remote Security, and Advanced Fuel Operation of Applications NPPs Safeguards
NRC is assessing various advanced fuel types to ensure its readiness to license the storage and transportation of these fuels Engaged in several research activities looking at front end, Summary back end and processing aspects of advanced fuel cycles NRC is monitoring external R&D programs that address the challenges of spent fuel waste management
Thank you for your attention.