ML23083B369
| ML23083B369 | |
| Person / Time | |
|---|---|
| Issue date: | 03/30/2023 |
| From: | NRC/OCM |
| To: | |
| Shared Package | |
| ML23067A027 | List: |
| References | |
| M230330 | |
| Download: ML23083B369 (29) | |
Text
BRIEFING ON NUCLEAR REGULATORY RESEARCH PROGRAM Commission Meeting March 30, 2023
Cathy Haney D e p u t y E xe c u t ive D ire c to r fo r M ate ria l s, Wa ste, Re se a rc h, S tate,
Trib a l, C o m p lia n c e, A d m in i st rat io n,
a n d Hu m a n C a p ita l P ro g ra m s
NUCLEAR REGULATORY RESEARCH PROGRAM 3
Ray Furstenau Research Program Overview; Collaboration; Future Focused Research Mike Franovich Research Contributions to Mission Success Fred Sock Cooperation with National Reactor Innovation Center under the Nuclear Energy Innovation Capabilities Act Louise Lund Enhancing the Research Program Through Stakeholder Outreach Thomas Boyce Fuel Cycle Research Cooperation
Ray Furstenau D ire c to r Off ic e o f N u c le a r Re g u lato r y Re se a rc h
5 Be Ready for New Technologies
- World-class expertise
- Building capabilities to support our safety and security mission
- Striking a balance of in-house and external capabilities 199 RES FTE 67% RES staff with advanced degrees
$42 M contract support
6 Partnering for Success
- Strong engagement with internal and external partners
- International activities
- FIDES II and joint projects
- Robust international safety analysis code user groups
>100 International agreements
>10,000 Computer code users Photo courtesy of Idaho National Laboratory Advanced Test Reactor Rod Bundle Heat Transfer Facility CAMP RAMP CSARP
7 Fostering Readiness for New Technologies and Regulatory Innovation
- Future Focused Research (FFR) supports the mission and RES capabilities
- Mission-related R&D grants effectively engage universities
- Both programs are important for enabling the safe use of advanced nuclear technologies 46 University R&D grants (FY20-22) 24 FFR projects (FY20-23)
Remote Operations FFR (FY21)
Digital Twins FFR (FY20)
Mike Franovich D ire c to r D ivisio n o f R isk A sse s s m e nt Off ic e o f N u c le a r Re a c to r Re g u lat io n
9 Research Helps Us Make Better Decisions Upgrades Analysis NFPA 805 improvements FLEX 2020 Derecho
10 Applying Expert RES Knowledge to Challenging Licensing Issues
- Risk-informed, consequence-based solution
11 Research is Foundational to Reliable Regulations 2015 2010 2005 2020 License Renewal GEIS SOARCA SMR Licensing Non-LWR Readiness Level 3 PRA Project ATF/HBU Post - 9/11 Security Studies Post-Fukushima Studies
-Spent Fuel Pools (NUREG-2161)
-Containment Venting (NUREG-2206)
Regulatory Source Term RG 1.183 (Rev 1)
Collaborative Research MELCOR & MACCS Code Development and Applications
Frederick Sock S t ru c t u ra l E n g in e e r D ivisio n o f E n g in e e rin g Off ic e o f N u c le a r Re g u lato r y Re se a rc h
13 Nuclear Energy Innovation Capabilities Act Spurs NRIC Collaboration Organizational Structure
- Nuclear Energy Innovation Center (NRIC) established as an addendum under NEICA memorandum of understanding framework Goal
- Improving NRCs technical readiness for advanced nuclear reactor applications NRC Participation
- Two NRC staff on assignment with NRIC
- Advanced Construction Technology Initiative
- Exploring 3 technologies to build a smaller SMR version
14 Benefits of Collaboration Between NRIC and NRC Preserving Regulatory Independence
- NRIC addenda consistent with NRCs role as an independent regulator Benefits to NRC
- Access and review new construction technologies
- Evaluating inspection and acceptance criteria
- Update NRC inspection procedures and manuals in support of staff readiness for future licensing activities
15 Vertical Shaft Construction Technology Vertical Shaft Sinking Machine Conventional use of retaining walls (secant piles, etc.)
16 Use of Steel Bricks'in Construction Steel Brick'as fabricated at shop Steel Brick'prototypes at Purdue from Caunton Engineering, to be filled with concrete for stress testing
17 Advanced Condition and Performance Monitoring & Digital Twin Seismometers to monitor construction
Louise Lund Director Division of Engineering Office of Nuclear Regulatory Research
19 Engaging Domestically and Globally Technical Leadership Technical Networks Engage Industry Access Timely Data Long-term Relationships Complex Technical Issues Government-to-Government
20 Leveraging a Spectrum of Instruments Conferences and Symposia Public Meetings Codes and Standards Bilateral Agreements Interagency Agreements Project-specific Agreements International Agreements Memoranda of Understanding Contracts and Grants
21 Partnering for Success 21 Stakeholder Engagement is Enhancing Our Readiness Activities on Artificial Intelligence Four Decades of Global Leadership in Nondestructive Examination Built on Engagement and Outreach
Tom Boyce Branch Chief Materials and Structural Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
23 Informing Regulation of Storage and Transportation NRC tools & expertise for independent analysis of spent fuel licensing reviews Mission-Ready Tools Staff Expertise Risk-Informed Regulator Applications
24 Ensuring Safe Storage
- Materials research for aging management
- Cask integrity - Chloride-Induced Stress Corrosion Cracking
25 Readiness for Reprocessing
- Readiness for applications
- Technical assessments of pyroprocessing techniques Salts Most of the fission products Oxide fuel from thermal reactors Metallic fuel from from fast reactors
26 Readiness for Advanced Reactor Fuel Cycles ENRICHMENT UF6 TRANSPORTATION FUEL FABRICATION REACTOR FRESH FUEL TRANSPORTATION IRRADIATED FUEL TRANSPORTATION SPENT FUEL STORAGE 1
3 2
4 5
6 7
Technical assessments of non-LWRs SCALE/MELCOR Non-LWR Fuel Cycle Demonstration Project Domestic & international collaborations &
monitoring industry progress Gamma / Thermal Shield
Cathy Haney D e p u t y E xe c u t ive D ire c to r fo r M ate ria l s, Wa ste, Re se a rc h, S tate,
Trib a l, C o m p lia n c e, A d m in i st rat io n,
a n d Hu m a n C a p ita l P ro g ra m s
28 Glossary of NRC Computer Codes Computer Codes FAST - Code for simulating nuclear fuel behavior SCALE - Code for reactor physics and radiation shielding analysis MELCOR - Code for simulating nuclear reactor severe accidents MACCS - Code for simulating the dispersion of radioactive materials SPAR - Code for reactor risk assessments Code User Groups CAMP - Code Applications and Maintenance Program CSARP - Cooperative Severe Accident Research Program RAMP - Radiation protection computer code Analysis and Maintenance Program
29 Acronyms EPRI - Electric Power Research Institute EPZ - Emergency Planning Zone FLEX - Diverse and Flexible Coping Strategies FIDES II - Second Framework for Irradiation Experiments FTE - Full-Time Equivalent GEIS - Generic Environmental Impact Statement INL - Idaho National Laboratory NEA - Nuclear Energy Agency NFPA - National Fire Protection Association RH - Relative humidity T - Temperature SMR - Small Modular Reactor SOARCA - State-of-the-Art Reactor Consequence Analyses UNLP - University Nuclear Leadership Program