ML20030B780

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Nrc(Iyengar)
ML20030B780
Person / Time
Issue date: 12/09/2019
From: Raj Iyengar
Office of Nuclear Regulatory Research
To:
Harris, Brian
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ML20030B755 List:
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Download: ML20030B780 (15)
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NRC Readiness for Advanced Reactors Licensing - Materials and Component Integrity Research Advanced Non-Light Water Reactors -

Materials and Component Integrity Workshop Raj Iyengar Office of Nuclear Regulatory Research U.S. NRC December 9, 2019

Disclaimer 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.

2

Advanced Reactor Landscape Micro Liquid Metal Cooled Fast High-Temperature Gas- Molten Salt Reactors Reactors Reactors Cooled Reactors (MSR)

(LMFR) (HTGR)

Oklo GE-H (VTR) X-energy Kairos Others TerraPower General Atomics ARC Framatome Stationary Westinghouse StarCore Sodium-Cooled TRISO Fuel Terrestrial Others Westinghouse TerraPower Columbia Basin Elysium Mobile Hydromine Thorcon Lead-Cooled Muons Flibe Alpha Tech Liquid Salt Fueled 3

Framework for Rightsizing Regulatory Processes NRCs Policy Statement on the Regulation of Advanced Reactors

- Identifies desired characteristics of advanced reactors (enhanced margins of safety; use of simplified, inherent, passive, or other innovative means to achieve safety)

- Address implications for safety and regulatory processes Developer Goals - Meet the Advanced Reactor Policy Statement through innovation Regulatory processes should assure safety and provide predictability, and not be a barrier to innovation 4

Framework for Rightsizing Regulatory Processes Principles of Good Regulation Independence Openness Efficiency Clarity Reliability 5

Framework for Rightsizing Regulatory Processes Modern Risk-informed Regulator Accepting Risk in Decision Making Utilizing Technology Innovating how we work Attracting and Retaining Talent 6

Readiness for Advanced Reactors and Tomorrows Technologies

  • Staff knowledge and capacity
  • Analytical capability
  • Modern licensing approaches for advanced reactor design
  • Consensus codes and standards
  • Technology inclusive mindset Strategy Document on Non-light Water Reactor Readiness
  • International and domestic collaborations 6

7 Thimble Plugging Device

Advanced Reactors:

Materials/Component Integrity Goal:

Assess performance needs and issues for materials/component integrity Support development of a regulatory framework Approach:

International Operating Experience Technical issues identification and resolution Flexible approaches to material qualification Coordination with DOE, EPRI, and International Counterparts 8

Advanced Reactors:

Materials/Component Integrity Recent NRC Reports:

- 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)

Ongoing Activities:

Potential endorsement of ASME Section III Div. 5 Graphite: source dependency of properties; molten salt intrusion/infiltration Evaluation of creep and prevention of creep failures of structural alloys High temperature corrosion (HTGR, SFR) and molten salt corrosion of structural alloys (MSR)

Molten salt purity, redox control, and standards for corrosion experiments 9

Graphite Graphite is a material that presents a number of unique design considerations for ANLWRs (Contract support Numark Associates Inc)

Assess graphite design criteria in ASME Section III, Division 5 Code rules Assess graphite properties and degradation including source dependency

  • Review experimental data and operational experience relevant to the performance of graphite
  • Perform a gap analysis on standards, regulatory guidance, and test procedures for evaluating graphite properties and degradation 10

Creep and Creep-Fatigue Creep-induced cracking and creep-fatigue are potential life-limiting factors for components in high-temperature reactors (contract support: ANL)

Survey to identify gaps in current creep and creep-fatigue design procedures in ASME Code and other codes Develop post-processing tools to aid in executing the ASME Section III, Division 5 Code rules

  • Take FEA input and compare with code rules 11

High Temperature Corrosion /

Molten Salt Compatibility Molten Salt Compatibility of Structural Materials and Graphite High Temperature Corrosion/Erosion/Oxidation of Structural Materials Assessment of Applicability of Existing Regulatory Guides and Standards Endorsed by Regulatory Guidance to Liquid-Fueled MSRs Planned Reports:

Recommendations for molten salt corrosion testing/test plan Recommendations for high temperature corrosion/oxidation Summary of technical and regulatory gaps on molten salt chemistry 12

Technical Challenges/Opportunities High Temperature Materials Aging and Degradation Radiation; Corrosion; Mechanical Reactor Surveillance Programs; Accelerated Testing Welding and Joining Additive/Advanced Manufacturing Probabilistic Fracture Mechanics of Graphitic Components Materials Performance in Realistic Environments Lead-time for Materials Characterization & Qualification Development of New Materials - High-Entropy Alloys 13

Forging The Future Connect, Create, Contribute*

  • (ACL-OAM 2019 Theme) 14

References

  • Regulatory Review Roadmap including prototype guidance (ML17312B567)
  • RG 1.232, "Guidance for Developing Principal Design Criteria for Non-Light Water Reactors" (ML17325A611)
  • NEI-18-04, Risk-Informed Performance-Based Guidance for Non-Light Water Reactor Licensing Basis Development, (ML18271A172)
  • DG 1353, Guidance for a Technology-Inclusive, Risk-Informed, and Performance-Based Approach to Inform the Content of Applications, (ML18264A093) 15
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