ML20178A598
| ML20178A598 | |
| Person / Time | |
|---|---|
| Issue date: | 06/26/2020 |
| From: | Kimberly Webber NRC/RES/DSA |
| To: | |
| Webber K | |
| References | |
| Download: ML20178A598 (13) | |
Text
Readiness for Advanced Reactors through Regulatory Research Kimberly Webber, PhD Deputy Director, Division of Systems Analysis Office of Nuclear Regulatory Research Kimberly.Webber@nrc.gov 1
NRCs Be Ready Attitude
- Improve Mission Value Through Cooperation
- Deliver cost savings
- Reduce duplication of effort
- Build staff expertise
- Bring regulatory perspectives to new ideas 2
NRCs Integrated Action Plan (IAP) for Advanced Reactors Near-Term Implementation Action Plan Strategy 1 Strategy 4 Knowledge, Skills, Industry Codes and Capacity p y and Standards ML17165A069 Strategy 5 Strategy 2 Technology Analytical Tools Inclusive Issues To View Status Strategy 3 Strategy 6 Flexible Review Communication Process 3
NRCs Integrated Action Plan (IAP)
Status 4
Strategy 2 : Computer Code Readiness
- Identification and development of computer codes and tools to prepare the staff for evaluation of safety of advanced non-LWRs
- Many advanced designs are under development and the landscape continues to evolve
- Objective of the IAP Strategy 2 is readiness
- Protect public health and safety, promote the common defense and security, and protect the environment
- Prioritization of code development activities
- Near-term submittals & shorter review schedules expected 5
Strategy 2: Computer Code Readiness Code Development Plans These Volumes outline the specific analytical tools to enable independent analysis of non-LWRs, gaps in code capabilities and data, V&V needs and code development tasks.
Introduction Volume 1 Volume 2 Volume 3 ML20030A174 ML20030A176 ML20030A177 ML20030A178 Volume 4 = Licensing and Siting Dose Assessment Under Development Volume 5 = Fuel Cycle Topics 6
Strategy 2: Computer Code Readiness Ongoing Research
- Fuel Performance, Source Term, Systems and Severe Accident Analyses Develop models for physical phenomena to qualifying materials and help evaluate safety of plant designs Utilize data to validate computer codes against expected power plant behavior
- Historic and current domestic and international research and experience Leverage Nuclear Energy Innovation and Capabilities Act Utilize DOE modelling and simulation tools Access to experimental results 7
Strategy 2: Computer Code Readiness Next Steps
- Complete Development Reference Plant Models
- Systems, source terms and severe accident analyses
- Heat Pipe Cooled Micro Reactor
- Molten Salt Fueled Thermal Spectrum Reactor
- High Temperature Gas Cooled Reactor
- Complete Volume 4 - Licensing and Siting Doses
- Complete Volume 5 - Fuel Cycle Topics 8
Strategy 2: Materials Integrity Readiness
- Objectives Assess performance needs/issues for materials and component integrity and build knowledge base
- Identify gaps in knowledge, data, and assessment tools
- Develop compendium of domestic and international operational experience
- Develop guidance endorsing consensus standards 9
Strategy 2: Materials Integrity Readiness Ongoing Research
- Strong Coordination with National Laboratories, Electric Power Research Institute and International Partners
- High temperature creep and fatigue; material surveillance (ANL)
- Operating experience (several countries)
- Graphite properties, data and modelling (ONR, JAEA) 10
Strategy 2: Materials Integrity Readiness Ongoing Research
- Completed Activities
- International operational experience with SFRs and HTGRs, focused on materials and component integrity (ADAMS ML18353B121)
- Technical Gap Assessment for Materials and Component Integrity Issues for Molten Salt Reactors (ADAMS ML19077A137)
- ANL-19/13, Environmental creep-fatigue and weld creep cracking: a summary of design and fitness-for-service practices, January 31, 2020 (ADAMS Accession No. ML20099A140) 11
Strategy 4: Codes and Standards
- Developing Regulatory Guidance to Endorse
- American Society of Mechanical Engineers Boiler and Pressure Vessel Code
- Section III, Division 5
- construction rules for high temperature reactors
- ASME/American Nuclear Society non-LWR Probabilistic Risk Assessment Standard
- NRC Evaluation Underway
- ASME BPV,Section XI, Division 2
- reliability integrity management 12
Summary
- NRC is actively preparing our analytic tools to support licensing and safe use of advanced reactor designs
- Volumes 1 - 5 of the IAP Strategy 2 document the codes intended for independent NRC analysis of non-LWRs in support of licensing reviews
- Materials engineering expertise and knowledge is advancing; reports have been completed
- Regulatory endorsement of consensus code and standards for advanced reactors is progressing
- Coordination with domestic and international organizations is vital 13