ML18143B604
| ML18143B604 | |
| Person / Time | |
|---|---|
| Issue date: | 02/01/2018 |
| From: | Allen Hiser NRC/NRR/DMLR/MPHB, US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| To: | |
| Rezai A, NRR-DMLR 415-1328 | |
| References | |
| Download: ML18143B604 (16) | |
Text
Overview of NRC Advanced Manufacturing Objectives and Activities Allen Hiser Division of Materials and License Renewal Office of Nuclear Reactor Regulation National Institute of Standards and Technology Additive Manufacturing Research Center (AMRC)
February 1, 2018
Discussion Topics
- Background on NRC
- Nuclear industry plans for use of advanced manufacturing methods
- NRC technical topics of interest
- NRC AM action plan 2
U.S. Nuclear Regulatory Commission
- The Energy Reorganization Act of 1974 established the independent U.S. NRC to regulate commercial uses of nuclear material; other duties of the former Atomic Energy Commission were assigned to Department of Energy.
- The NRC is headed by four Commissioners and a Chairman, all appointed by the President and confirmed by the Senate for staggered five-year terms. No more than three can be from the same political party.
3
Our Mission To license and regulate the nations civilian use of byproduct, source and special nuclear materials to protect the public health and safety, promote the common defense and security, and protect the environment.
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NRC Organization 5
NRC Locations & Operating Reactors 6
Nuclear Industry Plans
- Additive Manufacturing (AM)
- GE and Westinghouse developing non-safety-related reactor vessel internals
- Stated intent to install in 2018
- Westinghouse looking for a host plant and GE candidate part has changed
- Powder Metallurgy-HIP
- DOE / EPRI SMR reactor pressure vessel
- 2/3 scale - upper and lower head
- Electron Beam Welding
- Diode Laser Cladding
- Cryogenic machining 7
Technical Topic Areas
- Quality/reliability of processes, materials, and components for NPPs
- Codes and standards aspects of AM
- Properties and structural performance
- Service performance / aging degradation 8
But First - For NRC Planning Purposes
- Scope of components/applications that are of interest to NRC -
similar to License Renewal
- safety-related systems, structures, and components (SSCs)
- all nonsafety-related SSCs whose failure could adversely impact functionality of safety-related SSCs
- SSCs relied on in certain safety analyses or plant evaluations for specific NRC regulations.
- Schedule and method for industry implementation
- Topical report process
- License amendment process
- 10 CFR 50.59 process
- Timing of plant-specific implementation vis--vis codes/standards action and/or topical report approval will significantly affect review complexity
- PM-HIP has an ASME Code Case that NRC finds acceptable
- Volume of licensing actions
- Could lead to prioritization of reviews 9
Quality of AM Parts for NPPs AM Build Process
- Critical parameters
- Directionality
- Uniformity
- Surface roughness
- Density
- Feed stock and powder reuse Post-Build Processing
- Densification (e.g., Hot Isostatic Pressing)
- Annealing and heat treatment
- Surface processing
- Residual stresses and geometric stability 10
Codes and Standards Aspects of AM
- American Society of Mechanical Engineers (ASME)
- ASTM International
- formerly American Society for Testing and Materials
- American National Standards Institute (ANSI)
- American Society for Nondestructive Testing (ASNT)
- NACE International
- formerly National Association of Corrosion Engineers 11
Properties and Structural Performance
- Properties
- As-built
- After post-build processing
- Coupons vs. component
- Fatigue performance
- Comparison to conventional manufacturing methods
- Defect Characteristics/Populations
- Type
- Size
- Density
- Impact on structural integrity 12
Properties and Structural Performance
- Inspectability
- In-process examinations
- Methods capable of finding structurally relevant defects
- Pre-service inspections
- Inservice inspections
- Component residual stresses 13
Service Performance / Aging Degradation In various service environments
- Aqueous (BWR/PWR/Raw) 0 Corrosion 0 Stress corrosion cracking (SCC) 0 Environmental fatigue life 0 Environmental fatigue crack growth
- Neutron effects 0 Loss of fracture toughness 0 Swelling 0 IASCC
- Thermal effects 0 Loss of fracture toughness 0 Thermal expansion 14
NRC Action Plan
- Early stages of development
- To address preparation of NRC readiness for review of AM parts
- Provide for interoffice coordination - reactor side, waste management, research
- Address involvement in standards and codes organizations
- A subject of NRC Innovation and Transformation initiative 15
Summary
- Advanced manufacturing has been identified as an area of potential future utilization by the nuclear industry -
when and how many are the questions
- NRC interest areas
- The reliability of AM processing and quality of AM parts
- The properties of AM parts
- The structural performance of AM parts, including their inspectability
- The service performance and aging degradation of AM parts
- Codes and standards aspects of AM is a key to successful implementation
- Comparison of performance of parts from AM and conventional manufacturing process (benchmarking)
- Developing an NRC advanced manufacturing action plan 16