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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 ML24274A3202024-10-0404 October 2024 S9P2-Sircar NRC-NEA Harvesting WS-to NEA ML24283A1052024-10-0404 October 2024 S9P1-Tregoning-NRC Presentation on Us Harvesting Activities for Concrete Harvesting Workshop 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 ML24274A1772024-10-0101 October 2024 S0P3 Tregoning NRC Research ML24274A1792024-10-0101 October 2024 S1P4 Griesbach BWR and PWR Surveillance Capsule Test Data ML24274A0422024-10-0101 October 2024 Maritime Perspectives- Presentation for Abs and INL Offshore Nuclear Workshop 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 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 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 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 ML23194A1872023-07-20020 July 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23192A0712023-06-29029 June 2023 Assurance: Cyber Physical Systems - Exploring International Collaboration ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation 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 ML23324A2332023-10-24024 October 2023 S0P2 - Focht - NRC AMT Activities Overview v2.0 ML23324A2322023-10-24024 October 2023 S0P1 - Focht - 2023 NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications -Workshop Overview- ML23324A2702023-10-24024 October 2023 Session - Key Takeaways 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 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 Nrc’S 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 ML23152A1772023-06-15015 June 2023 28 - NRC - Fatigue Data Sharing ML23152A1702023-06-14014 June 2023 14 - NRC - PWSCC Initiation 2024-09-27
[Table view]Some use of "" in your query was not closed by a matching "". |
Text
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-NRC Assessment: considerations related to these application engagements, Ensure readiness to license the ANLWR fuel types. and inform guidance storage and transportation of various development.
ANLWR fuels within the flexible Considerations:
regulatory framework. May include various waste forms and waste streams, radiochemistry of constituents, storage canister Advanced fuel types include: performance and degradation, Metal fuel, TRISO pebbles, and actinide separation, tritium molten salt fuels. management strategies, and other 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 Advanced Fuel Molten Salt Waste Processing 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 approvedrecommendati regulatory gapanalysis framework path on in SECY-13-0093to (SECY-09-0082). 23 forwardsubmitted 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 adequatelyaddress decrease in commercial potential licensing needs interest licensingapplications through the existing regulatoryframework" 2016 2022 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 periodicResearch Coordination Meetings between SFERA participants:
Objectives:
To sustain and improve the IAEA's Member States IAEA Coordinated technical knowledge base on the long-term behavior of power reactor spent fuel Research Project (CRP) through sharing and Spent Fuel Research and disseminating information, reporting topical research Assessment (SFERA) carried-out in participating 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 Regulatory Modernization Viability Project - Operating Reactors
Integration of Nuclear Nano Key Attributes Safety, Technology - for Remote Security, and Advanced Fuel Operation of Safeguards Applications NPPs advanced fuel types to NRC is assessing various ensure its readiness to license the storage and transportation of these fuels activities looking at front end, Engaged in several research Summary back end and processing aspects of advanced fuel cycles R&D programs that address NRC is monitoring external the challenges of spent fuel waste management Thank you for your attention.