ML24254A269
| ML24254A269 | |
| Person / Time | |
|---|---|
| Issue date: | 09/16/2024 |
| From: | Bayssie M, Eric Focht, Eric Focht, Amy Hull NRC/RES/DE |
| To: | |
| Eric Focht 301-415-2094 | |
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| RIL 2024-12 | |
| Download: ML24254A269 (36) | |
Text
RIL 2024-12
NRC 2023 WORKSHOP ON ADVANCED MANUFACTURING TECHNOLOGIES FOR NUCLEAR APPLICATIONS
Part I - Workshop Summary
Date Published: September 2024
Prepared by:
E. Focht A. Hull M. Bayssie R. Tregoning
Research Information Letter Office of Nuclear Regulatory Research Disclaimer
This report was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third partys use, or the results of such use, of any information, apparatus, product, or process disclosed in this publication, or represents that its use by such third party complies with applicable law.
This report does not contain or imply legally binding requirements. Nor does this report establish or modify any regulatory guidance or positions of the U.S. Nuclear Regulatory Commission and is not binding on the Commission.
EXECUTIVE
SUMMARY
Advanced manufacturing technologies (AMTs) include techniques and material processing methods that have not traditionally been used in the U.S. nuclear industry or that have yet to be formally standardized by the nuclear industry (e.g., through nuclear codes and standards, or through other processes resulting in NRC approval or endorsement). Industry interest in the use of AMTs for nuclear applications led the NRC to embark on activities to increase staff understanding of AMTs, specifically, the differences between materials and components fabricated by AMTs and those fabricated by traditional methods such as casting, rolling, and forging. The goal is to prepare the staff for potential reviews of licensee submittals related to AMT implementation in safety-significant and risk-significant applications and regulate activities in this area.
The purpose of the hybrid October 24-26, 2023, workshop was to update the staff and stakeholders on (1) practical experience and plans for implementing AMTs for nuclear and non-nuclear components, (2) AMT process/part qualification and certification approaches, including the incorporation of modeling and simulation, and (3) the latest developments in codes and standards pertaining to AMT adoption.
Approximately 50 in-person and approximately 340 online attendees representing domestic and international research, academic, industry, and regulatory organizations participated in the workshop. Information about the workshop (e.g., agenda and presentations) is also available online at https://www.nrc.gov/public-involve/conference-symposia/amt-workshop/2023/index.html. The workshop was organized into four sessions:
Session 1: Implementation of AMTs in Nuclear and Non-Nuclear Applications Session 2: Qualification and Certification Session 3: Performance Characteristics Session 4: Code and Standards Workshop presenters represented a range of national and international organizations, including vendors, utilities, the Electric Power Research Institute (EPRI), the Nuclear Energy Institute (NEI),
the U.S. Department of Defense (DOD), the U.S. Department of Energy (DOE) (including Department laboratories), the National Institute of Standards and Technology (NIST), and universities.
The workshop provided an opportunity to share information among U.S. and international counterparts on approaches to using AMTs. The key takeaways from the workshop highlighted that several sectors are implementing AMT components to meet the needs of their stakeholders and customers, which satisfies a business case to increase parts availability, improve readiness, broaden the supply chain, manage component obsolescence, and optimize cost and performance.
Multiple pathways to materials/component qualification and certification (Q&C) are being used such as the traditional testing-based approach, the traditional approach coupled with in-process build controls and monitoring, and an accelerated approach utilizing modeling and simulation. Initial Q&C is largely following the traditional path used for conventional materials for adoption, using Codes (e.g., ASME), developing material property databases, and component and system level testing (i.e., first article testing). Research continues aimed at understanding the performance of materials produced by various AMTs focused on understanding and optimizing as-built performance. The results suggest that build variability needs to be addressed at the outset and identifying critical process variables is essential to assessing differences among machines and operators. Relevant performance metrics can be equivalent or better than conventional wrought materials, and it is important to understand and address causal factors for differences. Regarding the status of AMT-related codes and standards, many standards exist that support Q&C while augmented or new standards are needed to provide overall quality assurance. Integrated design, surveillance, and inspection strategies, coupled with targeted key testing can be used to implement additive manufacturing systems more quickly.
iii CONTENTS
1 Overview................................................................................................................................1 1.1 Previous NRC AMT Workshops........................................................................................1 1.2 2023 Workshop Motivation and Objectives.......................................................................1 1.3 2023 Workshop Organization and Participants................................................................2
2 Summary Of Presentations................................................................................................7 2.1 Session 1: Implementation of AMTs in Nuclear and Non-Nuclear Applications 2.2 Session 2: Qualification and Certification 2.3 Session 3: Performance Characteristics 2.4 Session 4: Codes and Standards
3 Key Workshop Takeaways20
4 Appendix A: Workshop Attendees
5 Appendix B: Presenter Biographies
LIST OF TABLES Table 1. Abbreviations and Acronyms.....................................................................................v Table 2. Participating Organizations........................................................................................3 Table 3. Workshop Agenda.....................................................................................................4 Table 4. Workshop Attendees..............................................................................................A-1
iv Table 1. Abbreviations and Acronyms
Term Description ABS American Bureau of Shipping ADAMS Agencywide Documents Access and Management System AI/ML Artificial intelligence/ machine learning AM Additive manufacturing AMMT Advanced Materials & Manufacturing Technologies, DOE Program, AMT Advanced manufacturing technologies ANL Argonne National Laboratory ASME American Society of Mechanical Engineers ASTM ASTM International (formerly American Society for Testing and Materials)
ATF Accident tolerant fuels BMUV Federal Ministry for Environment, Nature Conservation, Nuclear Safety and Consumer Protection (Germany)
C&F Casting & forging CGR Crack Growth Rate CNSC Canadian Nuclear Safety Commission CS Cold Spray CT computed tomography DED Direct Energy Deposition DME Digital manufacturing environment DOE U.S. Department of Energy EAF Environmentally-assisted fatigue EBW Electron Beam Welding EPRI Electric Power Research Institute FAA Federal Aviation Administration FDA U.S. Food and Drug Administration FT Fracture Toughness GE General Electric GRS German association for reactor safety HEA High entropy alloy HIP Hot Isostatic Pressing ICME integrated computational materials engineering INL Idaho National Laboratory ISI Inservice Inspection LPBF Laser Powder Bed Fusion LVEBW Local vacuum electron beam LWR Light water reactor MDDC Multiscale Digital Data Correlation MIC-EBW modular in-chamber electron beam welding MMPDS Metallic Materials Properties, Development, and Standardization MPA Material Testing Institute, University of Stuttgart NASA National Aeronautics and Space Administration
v NAVSEA Naval Sea Systems Command NCDMM National Center for Defense Manufacturing and Machining NDE Nondestructive Examination NDT Nondestructive Testing NEI Nuclear Energy Institute NIST National Institute of Standards and Technology NNL Naval Nuclear Laboratory NRC U.S. Nuclear Regulatory Commission NRL Naval Research Laboratory ORNL Oak Ridge National Laboratory PBF Powder bed fusion PM-HIP Powder Metallurgy-Hot Isostatic Pressing PNNL Pacific Northwest National Laboratory PWR Pressurized Water Reactor Q&C Qualification & Certification R2S Research to Standards RIL Research information letter, https://www.nrc.gov/reading-rm/doc-collections/research-info-letters SCC Stress-Corrosion Cracking SF Sheffield Forgemasters SLM Selective Laser Melting SMR Small modular reactors STUK Finnish Radiation and Nuclear Safety Authority UQ Uncertainty qualification WAAM Wire Arc Additive Manufacturing
vi 1 OVERVIEW
This Research Information Letter (RIL) summarizes the presentations and discussions during the 2023 Workshop on Advanced Manufacturing Technologies for Nuclear Applications, organized by the U.S. Nuclear Regulatory Commission (NRC). This hybrid public workshop took place October 24-26, 2023.
1.1 Previous NRC AMT Workshops
Advanced manufacturing technologies (AMTs) include techniques and material processing methods that have not traditionally been used in the U.S. nuclear industry or that have yet to be formally standardized by the nuclear industry (e.g., through nuclear codes and standards, or through other processes resulting in NRC approval or endorsement). Industry interest in the use of AMTs for nuclear applications led the NRC to embark on activities meant to increase staff understanding of AMTs, specifically, the differences between materials and components fabricated by AMTs and those fabricated by traditional methods such as casting, rolling, and forging. The goal is to prepare the staff for potential reviews of licensee submittals related to AMT implementation in safety-significant applications and regulate activities in this area.
In November 2017, the NRC organized its first AMT workshop entitled, Workshop on Additive Manufacturing for Reactor Materials and Components (AM-RMC), which covered a variety of topics such as the state-of-the-art of AM, Industry activities in AM, AM qualification, NDE, cyber security, and modeling. The workshop summary can be found in the NRC Agencywide Documents Access and Management System (ADAMS) under Accession No. ML19214A205.
In December 2020, the NRC held its second AMT workshop entitled, NRC Workshop on Advanced Manufacturing Technologies for Nuclear Applications, which covered topics related to practical experience related to implementation, performance characteristics of AMT-fabricated components, codes and standards, and research and development of AMTs. The workshop RIL can be found in the ADAMS under Accession No. ML21113A081 and ML21113A082.
In May 2023, the NRC conducted a workshop entitled, 2023 Meeting on NDE of AM Components, which covered the state-of-the-art of NDE of AM components, as well as key challenges associated with the use of various NDE technologies. Specific topics included ultrasonic testing, process compensated resonance testing, qualification, structure-property relationships, and in-process monitoring. The meeting summary can be found in ADAMS under Accession No. ML23153A010.
1.2 2023 Workshop Motivation and Objectives
Since the 2020 NRC AMT workshop, the staff identified significant efforts in AMT materials and processes qualification and certification (Q&C) approaches being conducted by organizations such as the DOE and DOD. In addition, advancements in AMT applications related to areas such as electron beam welding and directed energy depositions were recognized in the private sector. Therefore, the NRC staff determined that another AMT workshop would be useful to update the staff and stakeholders on activities and advancements in AMT implementation and qualification. The motivation for the workshop stemmed from the staff recognizing that there is potential industry interest in implementing AMTs for nuclear applications such as replacement components in operating nuclear power plants and in the initial construction of small modular and advanced reactors. Additional motivation was the awareness that the efficient and effective introduction of components produced by AMTs in nuclear applications depends on a shared understanding of technical and regulatory challenges, success paths, and future opportunities.
1 The primary objectives of the 2023 workshop were to update the staff and stakeholders on: (1) practical experience and plans for implementing AMTs for nuclear and non-nuclear components, (2)
AMT process and part Q&C approaches, including the incorporation of modeling and simulation, and (3) the latest developments in codes and standards pertaining to AMT adoption.
1.3 2023 Workshop Organization and Participants
This workshop was conducted as a hybrid meeting over three days with about 50 in-person attendees and approximately 340 online attendees representing domestic and international research, academic, industry, and regulatory organizations. The workshop was organized into four sessions:
Session 1: Implementation of AMTs in Nuclear and Non-Nuclear Applications. The objective of Session 1 was to provide information on experience using AMT components for nuclear and non-nuclear applications. This session covered recent and future applications of AMTs such as laser powder bed fusion (LPBF), directed energy deposition (DED), electron beam welding (EBW), and powder metallurgy with hot isostatic pressing (PM-HIP), and advances made in these AMTs.
Session 2: Qualification and Certification. The objective of Session 2 was to share approaches developed, or under consideration, to qualify AMT materials and components made using AMTs for applications involving component manufacturing and surface treatments. Topics in this session covered qualification approaches including modeling and simulation.
Session 3: Performance Characteristics. The objective of Session 3 was to provide information related to the performance of AMT materials and components including approaches to developing data for qualification.
Session 4: Code and Standards. The objective of Session 4 was to provide updates on the latest codes and standards (C&S) related to the use of AMTs.
Table 2 lists the organizations whose staff gave presentations during the workshop. One observation is that the participating organizations were substantially different from those that presented at the 2020 workshop. In the 2020 workshop, there were 33 organizations represented by speakers. Of these, 15 participated again in 2023 (as italicized) and 11 organizations were new to this workshop.
The four sessions presented diverse topics that included implementing AMTs in the U.S. Navy fleet, accelerated qualification, irradiation, and corrosion testing of LPBF-manufactured materials, and AMTs within the casting and forging industries, as shown in the final agenda (Table 3). Section 2 of this document includes brief summaries of the workshop presentations. The workshop attendees are listed in Appendix A and available biographies of speakers are provided in Appendix B.
2 Table 2. Participating Organizations
Organization Country Link America Makes USA https://www.americamakes.us/
ABS USA https://ww2.eagle.org/en.html ASTM USA https://www.astm.org/
International Barnes Global USA https://www.barnesglobaladvisors.com/
Battelle USA https://www.battelle.org/
DOE USA https://www.energy.gov/ne/nuclear-energy-enabling-technologies-neet EPRI USA https://www.epri.com/
Fluor Marine USA https://www.fluor.com/
Systems Framatome France https://www.framatome.com/EN/home-57/index.html GBR Consulting USA (George Rawls, LLC)
Lincoln USA https://www.lincolnelectric.com/en Electric MPA Germany https://www.mpa.uni-stuttgart.de/en/
NAVSEA USA https://www.navsea.navy.mil/
NIST USA https://www.nist.gov/
ORNL USA https://www.ornl.gov/
PNNL USA https://www.pnnl.gov/
Pratt & Whitney USA https://www.prattwhitney.com/
Rolls-Royce United Kingdom https://www.rolls-royce.com/
Siemens Energy Germany https://www.siemens-energy.com/
Sheffield United Kingdom https://www.sheffieldforgemasters.com/
Forgemasters UT San Antonio USA https://www.utsa.edu/
Westinghouse USA https://westinghouse.com/
3 Table 3. Workshop Agenda
Tuesday Oct. 24 (Day 1)
Time Topic Speaker 8:00 Welcome/Intro NRC 8:10 Workshop Overview NRC 8:30 NRC Overview NRC SESSION 1: IMPLEMENTATION OF AMTs IN NUCLEAR AND NON-NUCLEAR APPLICATIONS Session Coordinators: AM: Robert Tregoning PM: Eric Focht 8:50 Rolls-Royce's Experience of Applying the PM-HIP Process Rolls Royce (John Sulley) to the Manufacture of Nuclear Plant Components 9:20 Advancing Nuclear Component Manufacturing: Sheffield Forgemasters (Jesus Harnessing Local Vacuum Electron Beam Welding Talamantes-Silva) 9:50 Break 10:00 Implementation and Qualification of AMT Components in NAVSEA (Justin Rettaliata)
Support of the U.S. Navy Fleet 10:40 Overview of DOE Advance Materials & Manufacturing DOE (Meimei Li)
Technologies Program 11:10 Discussion All 11:30 Lunch (on your own) 1:00 Demonstrations Within the AMMT Program on Insertion of ORNL (Ryan Dehoff)
Advanced Manufactured Components in Applications 1:30 Securing the Future of the Nuclear Industry NEI (Hilary Lane) 1:50 Break 2:00 Advancements in Electron Beam Welding for Heavy EPRI (David Gandy)
Section Components 2:30 Overview of Framatome's Activities Supporting Additive Framatome (Christopher Wiltz)
Manufactured Nuclear Fuel Components 3:00 Current use of wire-DED materials Lincoln Electric (Teresa Melfi) 3:30 Break 3:40 Spare Parts On Demand by Additive Manufacturing Siemens Energy (Ramesh Subramanian) 4:10 AM Activities at Westinghouse Westinghouse (David Huegel) 4:40 Discussion All 5:00 Adjourn
4 Wednesday Oct. 25 (Day 2)
Time Topic Speaker 8:00 Welcome NRC SESSION 2: QUALIFICATION AND CERTIFICATION Session Coordinators : AM: Amy Hull PM: Austin Young 8:10 Accelerated Printability Feasibility and Prioritization of PNNL (Isabella Van Rooyan)
Additively Manufactured Structural Materials 8:40 Standards Considerations Towards the In-Process Quality NIST (Paul Witherell)
Assurance of AM Parts 9:10 Break 9:20 Qualifying Laser Powder Bed Fusion 316H for Use With ANL (Mark Messner)
ASME Section III, Division 5 9:50 High Throughput, Rapid and Automated NDE for ORNL (Amir Ziabari)
Optimizing Additive Manufacturing in Nuclear Applications 10:20 High Throughput Measurement of Surface Roughness and Siemens Energy (Ramesh Tensile Properties, Using Standardized AM Test Coupons Subramanian) 10:50 Discussion All 11:10 Lunch (on your own) 12:40 Peregrine: A Scalable In-Situ Process Monitoring Software ORNL (Luke Scime)
Stack using Artificial Intelligence 1:10 Aerospace Framework for Certification and Qualification Barnes Global (Kevin Slattery) for Advanced Manufacturing Technologies with Examples in Additive Manufacturing Using 316L Laser Powder Bed Fusion 1:40 Break 1:50 MMPDS and Additive Metals Battelle (Doug Hall) 2:20 Qualification and Certification for Additive Manufacturing ABS (Dongchun Mary Qiao)
Supported by Model-Based Approaches 2:50 Accelerating the Qualification of AM Materials Through ANL (Mark Messner)
Modeling and Simulation 3:20 Break 3:30 Application of Model-Based Material Definitions Pratt & Whitney (David Furrer) 4:00 Uncertainty Quantification of the Metal Laser Powder Bed UT San Antonio (Arturo Fusion Additive Manufacturing via the Hypercomplex-Montoya) based Finite Element Method 4:30 Discussion All 4:50 Adjourn
5 Thursday Oct. 26 (Day 3)
Time Topic Speaker 8:00 Welcome NRC SESSION 3: PERFORMANCE CHARACTERISTICS Session Coordinator: Eric Focht 8:10 Testing Approach and Initial Results on PM-HIP Nickel Fluor Marine Systems (Kevin Base Alloys Fisher) 8:40 Laser Powder Bed Fusion of 316H Stainless Steel for ANL (Xuan Zhang)
High-Temperature Nuclear Applications 9:10 Break 9:20 Critical Assessment of the Safety of Advanced MPA (Martin Werz)*
Manufacturing Processes for Internationally Relevant SMR Concepts: A Project Overview 9:50 Irradiation And Corrosion Testing of Laser Powder Bed INL (Andrea Jokisaari)
Fusion-Manufactured Materials in the Advanced Manufacturing and Materials Technologies Program 10:20 Performance of Laser Additively-Manufactured SS 316L in ANL (Bogdan Alexandreanu)
LWR-relevant Environments 10:50 Break 11:00 Generation of a Fatigue Design Curve Suitable for Use on Rolls Royce (Bill Press)*
Additive Manufacture Nuclear Plant Components Produced From 316LN Stainless Steel Using Laser Powder Bed Fusion 11:30 Discussion All 11:50 Lunch (on your own)
SESSION 4: CODES AND STANDARDS Session Coordinator: Mekonen Bayssie 1:30 AM Materials Data - Challenges and Opportunities ASTM (Richard Huff) 2:00 The Current State of Additively Manufactured Ni-Based America Makes (John Martin)
Superalloys and a Future Look at AMTs within the Casting and Forging Industries 2:30 ASME Criteria for Additive Manufacturing GBR Consulting (George Rawls) 3:00 Discussion All 3:20 Break 3:30 Wrap-up & Conclusions 4:00 Adjourn - end of workshop
6
- 2.
SUMMARY
OF PRESENTATIONS
Presentations are provided in the second volume of this two-part RIL and are also available at https://www.nrc.gov/public-involve/conference-symposia/amt-workshop/2023/index.html. When available, the abstracts provided by the speakers served as the foundation for the summaries in the sections below. The views and opinions presented in this RIL are those of the individual participants, and publication of this report does not constitute NRC approval or agreement with the information contained herein. As such, these proceedings are not a substitute for NRC regulations or guidance.
Rather, the approaches and methods described in this RIL and the recommendations from the discussions are provided for information only, and compliance is not required. Use of product or trade names in this report is for identification purposes only and does not constitute endorsement by the NRC.
DAY 1 PRESENTATIONS
2.1 Session 1: Implementation of AMTs in Nuclear and Non-Nuclear Applications
Presentations were given by NRC, Rolls Royce, Sheffield Forgemasters, U.S. Navy, Argonne National Laboratory (ANL), Oak Ridge National Laboratory (ORNL), Nuclear Energy Institute (NEI),
Electric Power Research Institute (EPRI), Framatome, Lincoln Electric, Siemens Energy, and Westinghouse.
The topics presented included experience with implementing PM-HIP to manufacture nuclear components, implementing AMTs in the U.S. Navy fleet, electron beam welding, AMTs for nuclear fuel components, AMTs role in making spare parts on demand, AMTs role in the nuclear energy sector, and plans to develop a framework for qualifying AMT components and to conduct demonstrations for inserting AMT components in nuclear applications.
2.1.1 OpeningWorkshop Overview & NRC Overview Presenter(s): Eric Focht, NRC
The first two presentations introduced the workshop by covering AMTs, the AMT AP, and the workshop organization. First, the presentation provided a high-level background on AMTs, including describing the five primary technologies of interest to the NRC and potential applications of each.
Next, the presenter discussed the AMT AP, which includes technical and regulatory preparedness projects, as well as communication and knowledge management activities, including this workshop.
Finally, the presentation gave an overview of the workshop, including motivation, approach, sessions, and logistics.
2.1.2 Rolls-Royce's Experience of Applying the PM-HIP Process to the Manufacture of Nuclear Plant Components Presenter(s): John Sulley, Rolls-Royce
This presentation covers Rolls-Royces implemented applications of PM-HIP products for nuclear reactor plant components. It covers a range of components considering the consequences of failure of the component. It starts from a non-pressure boundary application - a valve hard-facing seat, through pressure boundary leak-limited applications such as a thin-walled metallic toroidal seals, 7
and thick-walled pressure boundary isolable and unisolable applications such as: heat exchanger sections, large-bore valves, large-bore pipework, and reactor circulating pump bowls. All these applications are in stainless steel, with valve seat hard facings in Stellite and a Low-Cobalt material
- Tristelle 5183. The reasons and benefits of moving to the PM-HIP process from traditional methods such as forging and casting are covered, together with Rolls-Royces approach to establishing the method of manufacture and justification. The second part of the presentation presents Rolls-Royces more recent PM-HIP development, which is to develop a PM-HIP method of manufacture for low-alloy steel nuclear pressure vessels such as: Pressurizers and Reactor Pressure Vessels. It covers the challenges that Rolls-Royce has experienced in achieving key material properties, i.e., toughness.
2.1.3 Advancing Nuclear Component Manufacturing: Harnessing Local Vacuum Electron Beam Welding Presenter(s): Jesus Talamantes-Silva, Sheffield Forgemasters Engineering Ltd.
Sheffield Forgemasters (SF) has played a pivotal role in supporting the development of materials and processes for the nuclear industry over the years. As the demand for efficient and reliable welding techniques in nuclear applications continues to rise, and the need to reduce costs and save time becomes more critical, SF has taken on the challenge by introducing local vacuum electron beam (LVEBW) technology as a promising solution. This presentation highlights the latest work, which centers around designing, constructing, and commissioning a production-ready machine capable of local vacuum welding. This precludes the necessity for large and costly vacuum chambers. This advanced equipment incorporates key enabling technologies to develop a robust set of welding parameters and hardware, ultimately leading to successfully manufacturing a full-scale demonstrator. Through detailed experimentation and optimization, SF has developed welding parameters that result in indication-free welds even in 200 mm thick sections, encompassing steady state, slope-in, and slope-out regions. Advanced techniques such as finite element modelling and dimensional inspection have demonstrated minimal vessel distortion, thanks to the highly localized and consistent heat input of the LVEBW process. To validate the efficacy of the welds, extensive material analysis and mechanical testing were also performed, showcasing the superior properties of the weld region compared to traditional fabrication methods. Additionally, SF employed multiple non-destructive testing techniques to evaluate detection capabilities, expediting the development of welding parameters. This presentation emphasizes the importance of ongoing efforts in refining and optimizing the technology to ensure its acceptability and widespread adoption in critical applications.
2.1.4 Implementation and Qualification of AMT Components in Support of the U.S. Navy Fleet Presenter(s): Justin Rettaliata, NAVSEA
The Naval Systems Sea Command (NAVSEA) is issuing guidance for AM use and issuing requirements for metal powder fusion AM. They have developed methodologies for process qualification for components. Certification is produced for AM machines. NAVSEA has developed technical publications for repeatable AM processes and > 500 approved parts, is exploring in-situ monitoring and collaborates closely with industrial base. NAVSEA is prototyping the Digital Manufacturing Environment (DME) to address the need for advanced manufacturing cybersecurity and streamlined communication between ashore and afloat activities. The DME provides a scalable, proof-of-concept secure network boundary that separates manufacturing equipment and workstations from the host network.
2.1.5 Overview of DOE Advanced Materials & Manufacturing Technologies Program Presenter(s): MeiMei Li, DOE
The DOE Advanced Materials & Manufacturing Technologies (AMMT) Program is demonstrating advanced manufactured components for nuclear applications. DOE AMMT is working with the
8 current fleet of reactors and conducting In-situ monitoring assisted large-scale AM of mild steel and 316L alloys for nuclear application. They are also conducting feasibility demonstration and post-HIP assessment of AM pressure vessels.
2.1.6 Demonstrations within the AMMT Program on Insertion of Advanced Manufactured Components in Applications.
Presenter(s): Ryan Dehoff, ORNL
The mission of the AMMT program is to maintain U.S. leadership in the development of materials and manufacturing technologies for nuclear energy applications, and to support nuclear reactor technology developers by providing access to materials and capabilities to produce components that improve safety, reliability, and are more cost effective to manufacture. This talk focused on demonstrations across the AMMT program leveraging the multi-dimensional data correlation framework for integrating in-situ process data for manufacturing, advanced modeling techniques, and post inspection data, and mechanical properties. This presentation discussed past projects, ongoing potential demonstrations and outlined ongoing work focused on deployment of these technologies to industry including methods for laser powder bed fusion and directed energy deposition technologies.
2.1.7 Securing the Future of the Nuclear Industry Presenter(s): Hillary Lane, NEI
After an overview of the role of NEI in the nuclear industry, NEI discussed the advantages of AMT applications for both the current fleet and the advanced reactor designs emphasizing improvements in cost, schedule, and quality. NEIs advanced manufacturing task force observed the following areas of opportunity: (1) Need a more coordinated campaign (with funding) similar to ATFs to jumpstart deployments (2) Code acceptance is taking too long; uncertainty in qualifying new alloys of interest (3) R&D still needed (i.e. radiation testing, etc.) (4) Interest in regulatory lessons learned and experiences.
2.1.8 Advancements in Electron Beam Welding for Heavy Section Components.
Presenter(s): David Gandy, EPRI
Significant advancements in joining heavy section materials using EBW have been realized over the past decade. As a result, many manufacturers/fabricators are now considering the use of EBW for joining major components (e.g., pressure vessels, steam generators, pressurizers, etc.). This presentation discussed a modular in-chamber (MIC-EBW) approach wherein the vacuum chamber in which the welding process is performed can be stacked and de-stacked to meet the given weld height that one is looking to achieve. The presentation highlighted the current status of the project and provided some insight into when the technology may be available for use in heavy section pressure vessel fabrication.
2.1.9 Overview of Framatome's Activities Supporting Additive Manufactured Nuclear Fuel Components Presenter(s): Christopher Wiltz, Framatome
Framatome is actively working to implement additive manufacturing technologies, where or when advantageous, to further optimize nuclear fuel components mainly for performance, manufacturability, design flexibility and cost. Success has been achieved in the development of additive manufacturing processes and methods, resulting in the introduction and operation of lead nuclear fuel components in commercial nuclear power plants. This presentation provided an overview of Framatome's activities regarding nuclear fuel component additive manufacturing
9 application, including background, status of on-going activities and future direction.
2.1.10 Current Use of Wire-DED Materials Presenter(s): Teresa Melfi, Lincoln Electric
This presentation discussed materials made by wire arc additive manufacturing (DED-wire) to replace large forgings, castings, plates, and assemblies. A high temperature, pressure retaining use case was presented. The qualification methodology was discussed, with data presented for nickel-alloy, stainless steel and mild steel materials. Specific use of materials made from weld metal in pressure retaining and in nuclear applications was given. Several referenced papers and presentations were made available for those wanting more information.
2.1.11 Spare Parts On Demand by Additive Manufacturing Presenter(s): Ramesh Subramanian, Siemens Energy
Supply chain disruptions to our critical defense and energy products have become common place with the geo-political changes affecting the global manufacturing footprint. Additive manufacturing (AM) increases the resiliency and competitiveness of Americas supply chains due to reduced lead time benefits and the ability to pivot from one component geometry to another. Siemens Energy is adapting to the rapid growth in AM market requirements for heat exchangers, aero-derivative gas turbines, distributed and centralized power generation with a global manufacturing footprint. This footprint is based on both LPBF and Wire Arc Additive Manufacturing (WAAM) manufacturing approaches. The presentation discussed the parts down-selection approach and trade-offs of LPBF cost vs component performance and lead time. Examples of parts, for application in the gas turbine fleet, with LPBF and WAAM were discussed.
2.1.12 AM Activities at Westinghouse Presenter(s): David Huegel & William Cleary, Westinghouse
This presentation covers Westinghouses fabrication of nuclear components using AM technologies and testing via installation in nuclear power plants. They are using the EOS M290 machine to print equipment out of metallic powders including Alloy 718, 316L, 304,17-4 PH and MS-1 Copper and Aluminum. Monitoring the performance of these components will be important as they provide real world application to gain knowledge for other potential components.
DAY 2 PRESENTATIONS
2.2 Session 2: Qualification and Certification
Presentations were given by PNNL, NIST, ORNL, Siemens Energy, Barnes Global, Battelle, American Bureau of Shipbuilding (ABS), ANL, Pratt & Whitney, and the University of Texas San Antonio.
The topics presented included qualification and certification approaches for materials, processes, and equipment, accelerated qualification, and modeling and simulation. Rapid high throughput testing, and nondestructive evaluation (NDE) were also covered.
2.2.1 Accelerated Printability Feasibility and Prioritization of Additively Manufactured Structural Materials Presenter(s): Isabella Van Rooyan, PNNL
10 The AMMT Program has an overarching vision to accelerate the development, qualification, demonstration and deployment of advanced materials and manufacturing technologies to enable reliable and economical nuclear energy. At the nexus of this vision, multi-national laboratory researchers undertake an integrated approach, combining advanced characterization, high-throughput and accelerated testing, modeling and simulation including machine learning and artificial intelligence. This presentation focuses on accelerated approaches followed to understand potential candidate alloys and down selecting a specific material that would have a significant impact when fabricated using advanced manufacturing technologies like laser powder bed fusion. While 316H has been identified as a key alloy to be integrated into the AMMT accelerated alloy qualification approach due its relevance for many current and future nuclear energy reactors, many other alloys could be considered for the advanced fabrication of innovate high-performance nuclear components.
Therefore, printability feasibility development was performed on Fe-, Ni-, W-based and HEA (high entropy alloy) materials with microstructural characterization on selected printed structures.
As part of this accelerated approach, a selection criteria matrix was established to evaluate the alloys and includes criteria like the potential impact to the nuclear industry, material processability via AM technologies, improved performance, and technology readiness. Additionally, a chemical composition-based machine learning model has been developed to predict the printability of any given alloy in LPBF using experimental data from peer-reviewed literature.
2.2.2 Standards Considerations Towards the In-Process Quality Assurance of AM Parts Presenter(s): Paul Witherell, NIST
This presentation proved an overview of the diversity of AMT studies at NIST and the increasing roles of modeling and simulation, including the distinction with digital twins. Modeling and simulation are being used to: (1) Digitally realize a desired state of a part or process (2) Provide insight into physics interactions of parts and processes (3) Set expectations of expected performance through observed interactions (4) Provide a foundation for predictive analytics and course corrections during design, manufacture, and use phases of a part or subject.
2.2.3 Qualifying Laser Powder Bed Fusion 316H for Use With ASME Section III, Division 5 Presenter(s): Mark Messner, ANL
The LPBF manufacturing process has recently seen large-scale applications in the aerospace, automotive, and medical fields. The process can produce finely detailed components with excellent material properties, at least at room temperature. Qualifying LPBF Class A components to the ASME Section III, Division 5 rules would make this flexible manufacturing process available for the designers of the next generation of high temperature nuclear reactors. The key challenge here is understanding the materials performance and structure-properties connection for critical high temperature material properties like creep and creep-fatigue resistance. This presentation described a plan to qualify LPBF 316H stainless steel for Class A,Section III, Division 5 components both to provide the material and manufacturing process to reactor developers and to serve as a test bed for exploring and testing accelerated qualification approaches that could greatly reduce the time and amount of testing needed to qualify future advanced materials. The talk detailed the qualification plan, provide an update on completed and ongoing high temperature testing, and describe several accelerated qualification approaches being explored using the LPBF 316H data.
2.2.4 High Throughput, Rapid and Automated NDE for Optimizing Additive Manufacturing in Nuclear Applications Presenter(s): Amir Ziabari, ORNL
This talk focused on NDE efforts for additively manufactured nuclear components, conducted under the AMMT program of the DOE Office of Nuclear Energy. Recent developments were presented on artificial intelligence (AI)-based X-ray CT reconstruction algorithms which allow for rapid and high-11 quality characterization of hundreds of additively manufactured components with dense metals (stainless steel and Ni-based alloys), further enhancing our ability to optimize the additive manufacturing process. Moreover, work was demonstrated on merging the NDE characterization output with other modalities such as electron and optical microscopy, and then integrating them into the Multiscale Digital Data Correlation (MDDC) framework along with in-situ monitoring, modeling and mechanical testing data. Our objective is to understand the process-structure-property-performance relationships, and in turn leverage that in finding a high confidence optimum printing process window (power, velocity, composition, etc.) for fully dense printing with minimal flaws and defects.
Finally, printing large scale, complex nuclear components necessitate complementary NDE techniques to X-ray computed tomography (CT). To that end, plans were shared for future work on correlations between neutron and X-ray CT imaging of AM components. Exploration of ultrasonic techniques for characterizing bulk material was discussed, spotlighting the unique capabilities and synergistic potential of these techniques.
2.2.5 High Throughput Measurement of Surface Roughness and Tensile Properties, Using Standardized AM Test Coupons Presenter(s): Ramesh Subramanian, Siemens Energy
Both LPBF and WAAM of metallic components are unlocking new design options for high efficiency gas turbine component designs not possible by conventional manufacturing technologies. Surface roughness is a key characteristic of LPBF components that impacts heat transfer correlations and crack initiation from co-located surface defects - both are critical for gas turbine and heat exchanger component durability and performance. However, internal surface roughness variations are not measurable accurately. In addition, estimation of internal surface roughness during the design phase is not available. The presentation discussed the use of standardized hollow coupons for correlating internal and external surface roughness as a function of the location in the build plate, orientation and wall thickness. In addition, high throughput tensile testing techniques for both WAAM and LPBF were discussed, which enable statistically-relevant populations of properties, which vary due to intentional or aleatoric process changes. To that end, an efficient method to destructively evaluate the stochastic mechanical properties on a build-by-build basis is a necessary element. As a first step, the high throughput tensile testing data was compared with conventional data to show equivalence in materials property evaluation.
2.2.6 Peregrine
A Scalable In-Situ Process Monitoring Software Stack using Artificial Intelligence)
Presenter(s): Luke Scime, ORNL
This presentation provided an overview the Peregrine scalable in-situ process monitoring application developed at ORNL and deployed at several U.S. government labs, industry research organizations and universities. The presentation discussed the philosophy of the Peregrine project which includes, in part, sensor flexibility, acceptance of data from many printer manufacturers and integration with the ORNL Manufacturing Demonstration Facility (MDF). The presentation covered several aspects of the Peregrine application related to data acquisition, calibration, registration and fusion, and how machine learning is being utilized. Near-term future activities include work on an integrated visualization and analysis tool suite for X-CT data, integration of fracture mechanics models for predicting fatigue life, and improved integration with the MDF Digital Platform and web interface.
2.2.7 Aerospace Framework for Certification and Qualification for Advanced Manufacturing Technologies with Examples in Additive Manufacturing Using 316L Laser Powder Bed Fusion Presenter(s): Kevin Slattery, The Barnes Global Advisors 12 While the materials, requirements, and service environments between aerospace and nuclear applications differ, there is much commonality including part criticality, service life, and use of nondestructive testing. Additionally, as small reactors are developed, annual production rates for nuclear parts will approach those for aerospace. This presentation discussed a common framework used for certification and qualification, with examples on how it would be applied for an alloy in common between aerospace and nuclear, 316L. This framework and the example addressed feedstock, process development, design values, equipment & facility qualification, part qualification, and certification.
2.2.8 MMPDS and Additive Metals Presenter(s): Doug Hall, Battelle
The Metallic Materials Properties, Development, and Standardization (MMPDS) handbook is the primary source of statistically-based materials allowable properties for metallic materials and fasteners used in many different commercial and military weapon systems. The MMPDS Volume II is being updated to help facilitate AMTs for various applications including, potentially, nuclear applications. This presentation covered the proposed additions to the MMPDS Volume II that cover AMTs and described the MMPDS General Coordinating Committee functions through various task groups, steering groups, and working groups. The presentation also covered how the MMPDS is coordinating its activities with standard development organizations (e.g., ASTM, SAE) and other organizations developing AMT specifications (e.g., FAA, NIAR).
2.2.9 Qualification and Certification for Additive Manufacturing Supported by Model-Based Approaches Presenter(s): Dongchun Mary Qiao, ABS
This presentation introduces the development of model-based approaches for the rapid qualification of AM parts for marine and offshore applications. The Powder Bed Fusion (PBF) process is used as an example to demonstrate the implementation of the expert/knowledge statistical model, in-situ process machine learning model, and physics simulation model. The main goals of the rapid qualification of AM parts supported by the model-based approaches are to reduce the documentation of key parameters for procedure qualification, reduce types and frequencies of approval tests for material/manufacturer qualification, and simplify the approval tests for part qualification. By considering criticality levels as well as regulation and quality requirements, the rapid qualification plan can be based on the standard qualification process, finely tuned for the AM technology and customized for marine and offshore applications.
2.2.10 Accelerating the Qualification of AM Materials Through Modeling and Simulation Presenter(s): Mike Messner, ANL
The US DOE recently launched the AMMT program with the goal of accelerating the development, qualification, demonstration, and deployment of advanced materials and manufacturing technologies for the nuclear industry. A key challenge in high temperature material qualification is that the material strength and other critical properties are often time dependent - the material microstructure and hence material strength changes with time at elevated temperature conditions. The need to generate time-dependent material data often limits the pace of a qualification test campaign; long-term tests need to wrap up before generating qualified design material data. Advanced modeling and simulation is one potential means to speed up the qualification of high temperature materials.
This presentation described AMMT efforts to develop a physics-based processing-structure-properties model for LBPF 316H stainless steel. This model could be used to accelerate the qualification of LPBF 316H for use in future high temperature reactors by extending the time 13 extrapolation factor between the longest duration tests and the qualified material service life.
Additionally, the model could help enable alternative methods of qualification, for example approaches based on linking in situ process monitoring data to local microstructures to determine the acceptability of individual components for the anticipated in-service thermal and environmental conditions.
2.2.11 Model-Assisted Validation and Certification of AM Components Presenter(s): David Furrer, Pratt & Whitney & Sergei Burlatsky, Raytheon Technologies Research Center
The focus of the talk was on (1) Materials definitions in the Information Age (Industry 4.0) (2)
Product and process design approaches (3) Approaches for component material requirements and (4) Testing and qualification planning. Integration of modeling, sensors and data analytics are providing significant benefits. Model-based material and process definitions are becoming the new standard in holistic design, manufacturing and part/process validation and certification.
2.2.12 Uncertainty Quantification of the Metal Laser Powder Bed Fusion Additive Manufacturing via the Hypercomplex-based Finite Element Method Presenter(s): Arturo Montoya, UT San Antonio
Uncertainty Quantification (UQ) in AM finite element simulations poses challenges due to the computational demands of high-fidelity modeling. To mitigate computational costs, UQ can be performed using inexpensive surrogate models. Among surrogate models, the Taylor series expansion, a derivative-based approach, offers greater efficiency than sampling-based models for low-order expansions. The accuracy of the Taylor series expansion depends on the input parameter variation range, and increasing the expansion order enhances accuracy for a wider range of variations. However, constructing higher-order expansions becomes challenging due to the computation of higher-order derivatives.
In this study, the Hypercomplex-based Finite Element Method is utilized to efficiently calculate higher-order derivatives. This method enables obtaining derivatives of any order with respect to initial conditions, load conditions, thermal properties, mechanical properties, or shape using a single average sample. The methodology is validated by constructing higher-order Taylor series expansions of finite element outputs for a model simulating the laser melting of a powder layer on top of a bedplate along a rectilinear track. The finite element model accounts for property variations caused by temperature, phase change, and a mobile energy beam source. Random variables are considered for material properties, geometry, initial conditions, and process controls.
Comparisons with non-intrusive methods, including the linear regression-based perturbation method and polynomial chaos expansion, demonstrate that the hypercomplex-based Taylor series expansion achieves superior accuracy and efficiency. This innovative methodology has the potential to revolutionize the AM process by providing near-real-time feedback on the primary causes contributing to the lack of reproducibility and reliability in the process, as well as uncertainties in the mechanical properties of fabricated parts. Such critical insights form the basis for modifying, designing, and controlling the AM process to enhance quality and reliability, instilling confidence for the implementation of AM parts in nuclear applications.
DAY 3 PRESENTATIONS
2.3 Session 3: Performance Characteristics
14 Presentations were given by Naval Nuclear Laboratory, ANL, Materials Testing Institute (U. of Stuttgart, INL, and Rolls Royce.
The topics presented included testing approaches and results for PM-HIP nickel-base alloys, LPBF of 316L stainless steel for high temperature applications, irradiation and corrosion testing of LPBF-manufactured materials, performance of LPBF 316L stainless steel in light water reactor relevant environments, data generation and fatigue design curve development for LBPF 316LN stainless steel, and an overview of a new project to perform a critical assessment of the safety of AMTs for international SMR concepts.
2.3.1 Testing Approach and Initial Results on PM-HIP Nickel Base Alloys Presenter(s): Kevin Fisher, Fluor Marine Systems
A testing program for the characterization of PM-HIP nickel base alloys 600, 690 and 625 for the potential use as direct replacements to wrought materials is underway. Given the widespread acceptance of these materials in their wrought forged and cast forms, the testing approach aimed to show that PM-HIP materials resulted in properties comparable to those expected for wrought versions of these alloys. As such, a limited testing approach was undertaken to spot check properties including tensile properties (yield, ultimate, % elongation, and % reduction of area), low cycle fatigue life, fatigue crack growth rate in air, thermo-physical properties, impact toughness, and fracture toughness. Additional work included isotropy testing (with respect to orientation within the bulk material) and position effects (with respect to distance from the fill port) to verify the expected homogenous and isotropic nature of the PM-HIP material. While minor differences compared to wrought materials have been identified (both better and worse performance depending on the alloy and property), all three alloys perform similarly to their wrought counterparts in a majority of tests.
Current work is underway to better understand the structure-processing-property relationships to inform improvements to the processing methods that will result in properties more in-line with wrought material properties. This presentation outlined the scope of the approach, which was undertaken, results on all three alloys highlighting similarities and differences with wrought properties, and current development efforts to improve the properties with respect to wrought materials.
2.3.2 Laser Powder Bed Fusion of 316H Stainless Steel for High-Temperature Nuclear Applications Presenter(s): Xuan Zhang, ANL
To use LPBF 316H stainless steel in high-temperature nuclear reactor applications, research efforts are needed to develop laser processing conditions and proper heat treatments to yield optimal material properties. This study focuses on the LPBF of 316H stainless steel. Test cubes were printed exploring a wide process parameter space. The down-selection was based on inputs from in-situ monitoring and the density/porosity of the samples. Using the optimized process parameters, large block materials were fabricated for heat treatments and subsequent high-temperature tension, creep and creep-fatigue testing. The results are an important first step toward the qualification of LPBF 316H for reactor applications.
2.3.3 Critical Assessment of the Safety of Advanced Manufacturing Processes for Internationally Relevant SMR Concepts: A Project Overview Presenter(s): Martin Werz, Material Testing Institute (MPA), University of Stuttgart
Nuclear energy is seen as a bridge technology for reaching international climate goals and replacing fossil fuel power plants on a global scale. Especially small modular reactors (SMRs) seem promising as they can be operated complementary to renewable energy sources and therefore increase energy reliability. Although German policy has turned its back on nuclear power generation there is 15 interest in following international developments and maintaining competence regarding the assessment of newly developed reactor concepts. For this reason, the Federal Ministry for Environment, Nature Conservation, Nuclear Safety and Consumer Protection (BMUV) is funding a new research group at the Material Testing Institute (MPA), University of Stuttgart which runs under the administration of the German association for reactor safety (GRS). The aim of this research group is to build up far-reaching competences for the assessment of the safety of new manufacturing methods that will be used to produce SMRs.
In addition to more general new fabrication methods for pressurized water SMR reactor types, some aspects of solid-state SMR reactors using heat pipes for heat transfer in operation and as part of the safety concept are explored in this project as an example of the many SMR concepts. In order to achieve a high degree of significance, the most important manufacturing processes for the production of SMRs are considered. These include LPBF, SLM for small and complex parts, WAAM for parts of the pressure vessel, electron beam welding for high wall thicknesses, HIP part manufacturing for large and complex parts and cold spray coating for austenitic corrosion protection layers. For these manufacturing processes, possible discontinuities, the type and size of occurring imperfections as well as their number, distribution and impact on structural integrity are analyzed and quantified to define evaluation groups and allowability limits. As part of the development of new innovative reactors, the use of liquid metal heat pipes as a passive heat transfer system for heat removal is proposed in some SMR concepts. Therefore, additively manufactured heat pipes are chosen in this research project as an academic test case to evaluate the impact of different advanced manufacturing processes on the functional and structural safety of a key component of such SMRs. This includes the interaction of the new manufacturing processes with hydrogen as well as high-temperature behavior, the influence of liquid metal corrosion, and the dynamic behavior at beyond design load. The corresponding investigations are conducted for the materials AISI 316L, IN718, and 22NiMoCr3-7. Non-destructive testing (NDT) during fabrication and operation is mandatory for the safe operation of nuclear facilities. For this reason, this project also evaluates NDT methods for their applicability to geometrically complex parts, such as those resulting from the manufacturing of SMRs.
2.3.4 Irradiation And Corrosion Testing of Laser Powder Bed Fusion-Manufactured Materials in the Advanced Manufacturing and Materials Technologies Program Presenter(s): Andrea Jokisaari, INL
The AMMT program operating under the DOE Office of Nuclear Energy is accelerating the qualification and deployment of additively manufactured materials in advanced reactor environments. The LPBF has emerged as a promising additive manufacturing technique to fabricate complex components with the potential of tailored material properties. In the nuclear industry, metal additive manufacturing can offer numerous advantages, such as reduced lead times, streamlined quality assurance, and cost-effective low-volume production of new and replacement components with conventional or novel materials and geometries. The rapid and effective qualification of the effect of processing variability on the performance and degradation of additively manufactured materials is essential for the deployment of these components into advanced reactor environments.
As part of this effort, AMMT is performing irradiation and corrosion testing of several materials built by LPBF, including 316L and 316H stainless steels. Efforts encompass neutron irradiation testing, ion irradiation testing, and advanced modeling to provide a robust technical basis for understanding the effect of process variability on materials degradation and developing a sound methodology for accelerated ion irradiation testing. Focused irradiation test plans were developed that align well with risk-informed and technologically inclusive approaches to licensing. Plans were discussed and specific concerns for corrosion testing additively manufactured material, with a primary focus on molten salt and liquid sodium environments.
16 2.3.5 Performance of Laser Additively-Manufactured SS 316L in LWR-relevant Environments Method Presenter(s): Bogdan Alexandreanu, ANL
The advance of AM in recent years has made it possible for rapid prototyping and cost-effective production of high-quality nuclear components. As such, AM technologies are expected to not only improve the operating performance of the current reactors, but also accelerate the development of advanced SMRs of LWR-type. Yet, current understanding on the environmental degradation of AM materials in light water reactor (LWR) relevant service conditions is limited. To address this need, a US DOE LWRS-funded research program was initiated at ANL with the purpose of informing the existing codification and regulatory acceptance efforts by providing an understanding of how the microstructure and surface of AM components affect their performance in LWR environments.
Performance testing in the LWR environment will focus on environmental-assisted fatigue (EAF) and stress corrosion cracking (SCC) - two critical material properties for LWR service. The performance of the AM alloys will be compared with that of the conventionally-produced alloys (and their associated weldments) that are currently in use, and these activities will help evaluate and/or confirm the readiness of AM materials for LWR service. In initial efforts, SS AM 316L specimens extracted from component-like L-PBF builds were examined for microstructure and porosity, and tested for low-cycle fatigue, environmental fatigue, and stress corrosion cracking performance. It was found that the low-cycle fatigue behavior of the AM material in air was comparable to that of wrought stainless steels, suggesting that the microstructure and porosity level resulting from a well-controlled printing process do not significantly impact the fatigue performance. The corrosion fatigue and SCC crack growth responses of the AM specimens were also similar to those of conventional stainless steels, exhibiting high resistance to SCC degradation in high-temperature water. Additional research needs on environmental fatigue and crack initiation are discussed in the context of qualifying AM materials for broader applications in the LWRs and future water-based advanced reactors.
2.3.6 Generation of a Fatigue Design Curve Suitable for Use on Additive Manufacture Nuclear Plant Components Produced From 316LN Stainless Steel Using Laser Powder Bed Fusion Presenter(s): Bill Press, Rolls Royce
This presentation outlines Rolls-Royces approach to the derivation of a fatigue design curve specific to AM LPBF 316LN stainless steel with HIP process step, for use in ASME III, Subsection NB-3200 or NB-3600 fatigue crack initiation assessments on nuclear plant applications within its portfolio, including small bore globe valves and pipework tees and reducers. As part of a safety justification strategy for the implementation of AM LPBF small bore globe valves for nuclear plant Rolls-Royce carried out an initial suite of materials testing, including in-air uniaxial fatigue endurance tests on AM LPBF 316LN stainless steel samples. The limited data generated was seen to fall within the expected scatter when compared to the data upon which the NUREG/CR-6909 air best-fit curve is based. However, on completion of further testing in various test orientations on multiple powder batches and builds a more complex fatigue behavior was observed.
The presentation provides an overview of the investigation into the orientation effects on the material fatigue behavior, especially at high strain amplitudes, and how a combined best fit curve has been constructed for this material using either a fit to the limiting orientation data or the NUREG/CR-6909 mean curve at each point across the S-N curve, whichever is lower. A fatigue design curve is then produced from the best fit curve by first applying a mean stress correction and then applying transference factors on stress and on cycles to account for material variability, component size and surface finish, and load history.
17 The fatigue design curve generated specific to AM LPBF 316LN stainless steel is judged to be suitably conservative for the design assessment and analysis of the material on nuclear plant applications, including the AM small bore globe valves which have also undergone supporting ASME,Section III, Appendix II, thermal cyclic testing.
2.4 Session 4: Code and Standards
Presentations were given by ASTM International, America Makes and GBR Consulting. The topics covered included overviews of activities related to the challenges and opportunities associated with additive manufacturing materials data, the current state of additively manufactured nickel-based super alloys and a future look at AMTs within the casting and forging industries, and ASME criteria for additive manufacturing.
2.4.1 AM Materials Data - Challenges and Opportunities Presenter(s): Richard Huff, ASTM
While traditionally a rapid prototyping technology, the realization of AM as a full-scale industrial production technology continues to advance at a rapid pace. A recent study of large firms showed those who were active in AM that had produced functional end use parts increased by more than 30% in the past four years. However, as a percentage of the total manufacturing economy, AM is still a niche process. A few of the main impediments to greater adoption remain the high capital equipment cost, the maturity of AM systems for reliable and repeatable production, and the availability of materials data and standards. AM materials data is key for the design of AM parts and the qualification and quality assurance of production processes. Even at times when data may be available, the pedigree is often too low to trust the data and fully utilize. ASTM has conducted Research to Standards (R2S) projects to quantify the effects of typical process variables on the resulting material structure and properties. The ASTM Consortium for Materials Data and Standardization (CMDS) initiative is bringing companies together from across a broad range of industries representing the entire AM value stream to collaborate on standardizing the requirements and best practices for AM material data generation and managing shared high-pedigree reference datasets. This presentation discussed the opportunities created from standardized data workflows and high-pedigree materials data for developing the tools, such as physics-based and AI/ML models, needed to support rapid process optimization and qualification of new AM applications, materials and technologies and real-time quality assurance needed to scale AM production.
2.4.2 The Current State of Additively Manufactured Ni-Based Superalloys and a Future Look at AMTs within the Casting and Forging Industries Presenter(s): John Martin, America Makes
Uncertainty Driven by the National Center for Defense Manufacturing and Machining (NCDMM),
America Makes is a Department of Defense Manufacturing Innovation Institute focused on AM technologies. Since its inception, America Makes has leveraged a national collaborative ecosystem to advance the readiness level of AM technologies and invigorate the knowledge base, skills, and training available for the domestic AM supply chain. The America Makes strategy is the product of collaboration with its membership, which is comprised of representation from all tiers of the domestic AM supply chain. Nickel alloys play a critical role in high temperature applications, such as those found in nuclear reactors. While traditionally manufactured high temperature nickel alloys are relatively well developed, the process to manufacture them is both time consuming and expensive.
This can often involve vacuum melt and vacuum cast processes followed by precipitation hardening.
Furthermore, downstream processes, such as joining and machining are known to be difficult for these types of materials as well. The ability to 3D print these alloys offers the potential to reduce the
18 time and cost put into making these components, as well as open up geometrical design freedoms in addition to potentially reducing or eliminating tedious heat treatment processes. Another area that America Makes has been focusing on that could be beneficial to the nuclear industry is the development of a roadmap to help industrialize AM capabilities to accelerate casting and forging (C&F) lead times as well as jointly overseeing several projects within those sectors. The C&F roadmap and project topics were developed from a series of workshops that were held from March to July of this year consisting of experts in casting, forging, and additive manufacturing from diverse areas including academia, government, industry, and professional organizations to outline a strategic approach for implementation and scaling of AM in the C&F industries. An overview of these efforts as they pertain to nuclear applications was presented.
2.4.3 ASME Criteria for Additive Manufacturing Presenter(s): (George Rawls, in absentia), GBR Consulting, Teresa Melfi, Lincoln Electric Corp.
The presentation provided an overview of the current criteria and Code Case ASME is developing for the DED and PBF additive manufacturing processes. The presentation described the bracketed qualification process used for directed energy deposition (DED) to meet the verification requirements for including allowable stress values in ASME BPVC Section II Part D. Pressure Technology Book (PTB) 2021 was published in May 2021 and includes criteria for pressure retaining metallic components using additive manufacturing and will be used to document the work done to develop the technical baseline for both powder bed fusion and DED AM processes.
19
- 3. Key Workshop Takeaways
The workshop provided an opportunity to share information among U.S. and international counterparts on approaches to using AMTs. The key takeaways recorded from each session are provided below and summarized here. They were developed during the workshop and presented at the conclusion of the workshop by NRC staff. The key takeaways from the workshop highlighted that several sectors are implementing AMT components to meet the needs of their stakeholders and customers, which satisfies a business case to increase parts availability, improve readiness, broaden the supply chain, manage component obsolescence, and optimize cost and performance. Multiple pathways to materials and component qualification and certification (Q&C) are being used such as the traditional testing-based approach, the traditional approach coupled with in-process build controls and monitoring, and an accelerated approach utilizing modeling and simulation. Initial Q&C is largely following the traditional path used for conventional materials for adoption, using Codes (e.g., ASME),
developing material property databases, and component and system level testing (i.e., first article testing). Ongoing research is aimed at understanding the performance of materials produced by various AMTs focused on understanding and optimizing as-built performance to maximize value. The results suggest that build variability needs to be addressed at the outset and identifying critical process variables is essential to assessing differences among machines and operators. Relevant performance metrics can be equivalent or better than conventional wrought materials, and it is important to understand and address causal factors for differences. Regarding the status of AMT-related codes and standards, many standards exist that support Q&C while augmented or new standards are needed to provide overall quality assurance. Integrated design, surveillance, and inspection strategies, coupled with targeted key testing can be used to implement additive manufacturing systems more quickly.
Key Takeaways for Each Session:
Session 1:
- Several sectors are implementing AMT components to meet the needs of their stakeholders/customers, which satisfies a business case:
o Improve parts availability to improve readiness o Broaden the supply chain o Manage component obsolescence o Optimize cost and performance
- Initial applications have been low risk to gather manufacturing and operating experience.
- Safety-significant applications are proceeding cautiously.
- It is important for designers to be proactive and intimately involved with fabrication process, especially as safety-significance increases.
- Significant opportunities exist for supporting both existing and future platforms.
Session 2:
- Multiple qualification pathways:
o Traditional testing based o Traditional coupled with in-process build controls and monitoring o Accelerated, with modeling and simulation (M&S) support (integrated computational materials engineering (ICME))
- Initial Q&C is largely following the traditional path used for conventional materials for adoption, using Codes (e.g., ASME), developing material property databases, and component and system level testing (i.e., first article testing). M&S provides the opportunity to both identify critical tests for optimizing/demonstrating AM systems while simultaneously accelerating Q&C:
o Building trust in M&S approaches is needed to fully realize their benefits 20
- There may be opportunities to leverage Q&C efforts developed (or being developed) within other industries.
Session 3:
- Many studies are focusing on understanding and optimizing as-built performance to maximum AM value:
o Anisotropy considerations are a stronger consideration within this approach
- Build variability needs to be addressed at the outset and identifying critical process variables is essential to assessing differences among machines and operators.
- Relevant performance metrics can be equivalent or better than conventional wrought materials:
o Important to understand and address causal factors for differences
- M&S provides a needed tool to most efficiently understand environmental effects.
Session 4:
- Many standards already exist that support AM Qualification:
o Powder quality and handling o Heat treatment o Testing and characterization o Post-fabrication inspection
- Augmented or new standards are needed to provide overall quality assurance:
o Identification and control of essential process variables o Implementation of in-process monitoring
- Incentivize knowledge and data sharing among practitioners.
- Codification processes are incorporating AM but processes are lengthy by design and due to uncertainties:
o Integrated design, surveillance, and inspection strategies, coupled with targeted key testing can be used to more quickly implement AM systems
21 APPENDIX A Table 5. WORKSHOP ATTENDEES
Name (last, first ) Organization Name (last, first ) Organization UK Atomic Energy Bowker, Brian NRC Allison, Amanda Authority Abu-Eid, Boby NRC Bozga, John NRC Addo, Fredrick Ghana Atomic Energy Brand, Javier NRC Kwaku Commission Bream, Jeff NRC Adjei,-Kyereme, Nuclear Regulatory Shanghai Institute of Serwaa Authority Bu, Jichao Applied Physics Nawah Energy Al Jaberi, Hussain Company Buford, Angie NRC Alekos, Bobby NRC Burton, Mat NRC Alexandreanu, Cairns-Gallimore, DOE Office of Nuclear Bogdan ANL Dirk Energy Allik, Brian NRC Carinne, Shannon Battelle Alvarado, Lydiana NRC Carlson, Jesse NRC Nawah Energy Cataldo, Paul NRC Amin, Ankir Company Chandran, Anchondo-Lopez, Nachiketh NRC Isaac NRC Shanghai Institute of Anderson, J NA Chang, Litao Applied Physics Andersson, David LANL Chen, Yiren ANL Attanasio, Steven NNL DOOSAN Enerbility, Cho, Sungwoo South Korea Audrain, Meg NRC Christensen, Jason INL DOE Office of Nuclear Barr, Christopher Energy Christopher, Omoni KEPCO Bass, Joseph NRC Clayton, Kelly NRC Batra, Chirayu Terra Praxis Cleary, William T Westinghouse Bayssie, Mekonen NRC Cohn, Brian NRC Bechtel, William NA Colaccino, Joseph NRC Bell, Edward Holtec Govt Services Collins, Jay NRC Benson, Michael NRC Colon Fuentes, Luis NRC Bettes, Brian NRC Colon Gonzale, Francheska NRC Bjurman, Martin Studsvik Como, Jen DOJ/FBI Bloom, Steven NRC Condron, Thomas US Navy Boninger, Ron Swift Current, LLC Constantinescu, Technical Standards &
Boruk, Reena NRC Liliana Safety Authority Contreras, Bosley, Michael Westinghouse Jonathan NRC Bouffioux, Ryan A. INL Cooper, Paula NRC A-1 Name (last, first ) Organization Name (last, first ) Organization
Couret, Ivonne NRC Floyd, Nik NRC Sheffield Forgemasters Focht, Eric NRC Crabbe, Marcus Engineering LTD Cumblidge, Fong, CJ NRC Stephen NRC Nawah Energy Cunningham, Francis, Johns Company Daniel Lucideon TAES (Toshiba Daniel, Jason NRC American Energy Franzen, Michael Systems Corporation)
Dave (Guest) NA Fu, Bart NRC Davis, Robert NRC Furrer, David Pratt & Whitney Dehoff, Ryan ORNL Gandy, Dave EPRI Ontario Power Deleanu, Gabriela generation Gardocki, Stanley NRC Delisle, Dale NRC Gavula, James NRC Desai, Binoy NRC Gee, Jess GE Vernova Dhakal, Sandeep Boise State University Chalmers Institute of Geers, Christine Technology Diane, Mory NA NIST (International Dijamco, David NRC Gibbons, Duncan Assoc)
DiLoreto, Edward, Westinghouse Goldsmith, Jason Westinghouse Donmez, Alkan NIST Golumbfskie, Bill NSWC Carderock Dornke, Matthew NRC Gordon, Matthew NRC Douglas, Jared Centrus Energy Goss, Sandra DOD NSA Downey, Steve NRC Goyer, Dennis NNL Drake, James NRC Graham, Jacqueline Constellation Energy Dudek, Michael X-energy Graves, Todd Centrus Energy Dunn, Darrell NRC Gray, Mel NRC GE-H Nuclear Energy Eckes, Scott NA Americas & GE-H SMR Erling, Warren NRC Grewal, Harpreet Technologies Escobar Veras, Griman, Brian NRC Sam NRC Grinsteinner, Todd Eve, Elise NRC James LLNL NRC Germany, te 234 Fabritiis, Nick Constellation Energy Gud, Menz Brlin Fairbanks, Carolyn NRC Guieb, Angela NRC Faraone, Kevin ORNL Gurdziel, Tom Member of the public Feliz Adorno, Hall, Doug Pratt & Whitney Nestor NRC Feng, Shaw NIST Hannifin, Bridgette Terrapower Fernandez, Edison NRC Hansing, Nicholas NRC Finch, Shannon Westinghouse Harisis, Becki Nebraska DHHS Fisher, Kevin NNL Harris, Brian NRC Fitzgerald, Michael NRC Harris, Doug ORNL
A-2 Name (last, first ) Organization Name (last, first ) Organization
Havrilak, Cody DOE HQ Kavanaugh, Kerri NRC Haywood, Emma NRC Khan, Omar NRC Heath, Rick Framatome Ulan National Institute of Science &
Heidrich, Brenden INL Kim, B. Technology Heras, Marisa G tecnatom Kim, Hongdeok KEPRI Hills, David NRC Klein, Paul NRC Hiser, Allen formerly NRC, retired Kobayashi, Tatsuro TEPCO Hiser, Matt NRC Kochmanski, Urzad Dozoru Andrzej Technicznego. Centrala Hobbs, Alec NRC Koenigsfeld, David PWROG Homiack, Matthew NRC Korinchak, Nate NSWC Carderock Honcharik, John NRC Korzeniowski, Hovanec, Susan NSWC Carderock Patrick NSWC Carderock Howard, Arlette NRC Kulp, Jeff NRC Huang, Jason NRC Kumari, Geeta ORNL Huegel, David Westinghouse Lane, Hillary NEI Huff, Richard ASTM Lane, John NRC Hull, Amy NRC Law, Yiu NRC Hwang, Kihoon Starobowelds Inc. Lawler, Steven Frazer-Nash Iyengar, Raj NRC Le, Tuan NRC Pennsylvania State Jacob, Richard PNNL Lee, Saya University Jacques, Brian formerly NEI -retired? Levine, Lyle NIST Jayroe, Peter NRC Levitus, Steven NRC Czech Technical Li, MeiMei ANL University in Prague, Faculty of Nuclear and Lin, Bruce NRC Jedlan, Stepan Physical Engineering Lisova, Dana NA Jenkins, Joel NRC Lizardi-Barreto, Jensen, Paul Arizona Public Service Jonathan NRC Jerry (guest) NA Magnuson, Eric NRC jiang, Xiaodong NA Magyar, Michael NRC Jiang, Yan Shanghai University Makar, Greg NRC Johnson, Andy NRC Makor, Shiattin NRC Jokisaari, Andrea INL Malik, Shah formerly NRC, retired Jovic, Riznic CNSC Mangan, Kevin NRC California Dept of Martin, John America Makes Jue, Tracy Public Health (CDPH) Massey, Caleb ORNL Kagel, Gary W. Lucideon Matrachisia, John NRC Kalikian, Varoujon NRC McClay, Samuel NRC Karoutas, Zeses Westinghouse McCormack, Dave formerly Dade Moeller A-3 Name (last, first ) Organization Name (last, first ) Organization
& Assoc. -retired? Park, Dong NRC
McCormick, Kevin NRC Park, Joon NRC McCracken, Jessica NRC Parker, Cory NRC McMurtrey, Michael Parsi, Arash Westinghouse D. INL Patel, Raju NRC Meadows, Tenisha NRC Peterson, Alyse NYSERDA ARPA-E (Booz Allen Meany, Joseph Hamilton) Philipps, Caleb University of Missouri Medoff, James NRC NNL-Fluor Marine Meher, Subhashish PNNL Pica, Paul Propulsion Mejia, James NRC Poehler, Jeff NRC Melendez-Colon, Ponko, Anthony NRC Daneira NRC Pottle, David. W. Lucideon Melfi, Teresa Lincoln Electric Press, Bill Rolls-Royce Mentzer, Nate NRC Prokofiev, Iouri formerly NRC, retired Messner, Mark ANL Purtscher, Pat NRC Mills, Lloyd Greenberry Industrial American Bureau of Min, Seung NRC Qiao, Dongchun Shipping Mirmohammad, Raleigh, Deann NA Hadi Westinghouse Ray, Devendra NRC Mitchell, Matthew NRC Raynaud, Patrick NRC University of Texas at Reed, Wendy NRC Montoyo, Arturo San Antonio (UTSA) Nuclear Power Plant Morgan, DJ WV House of Delegates Regener, Benjamin Leibstadt AG Morganti, Giovanni Centrus Energy Reichelt, Eric NRC Moyer, Carol NRC Rettaliata, Justin NAVSEA Nabuurs, Tony formerly NB Power, retired Rettew, Andrew NA Nakatsuka, Toru Japan Atomic Energy Rezai, Ali NRC Agency Nash, Kenneth GE Vernova Rivera Ortiz, Joel NRC Nellis, Christopher NRC Roach, Allen INL Nelson, Katelyn NA Robinson, Jazmin NRC Neumeyer, Gayla Rock, Peggy Fermi 2 M. University of Missouri Rudland, David NRC Nove, Carol NRC Ruffin, Steve NRC Oberson, Greg NRC State Office for Nuclear Ohl, Brandon Pratt & Whitney Rydlova, Jolana Safety, (SONS)
Nuclear Regulatory Sampson, Michelle NRC Ono, Masato Authority Sanchez Santiago, Onuschak, DOE Office of Nuclear Elba NRC Rebecca Energy Sandra (guest) NA Palmer, Eric NRC Savara, Aditya NRC
A-4 Name (last, first ) Organization Name (last, first ) Organization
Saya, Lee NRC Tony (guest) NA Scarbrough, Tran, Anthony NRC Thomas NRC Scates, Erica NSWC Carderock Travis, Adam Westinghouse Schoppy, Joseph NRC Tregoning, Rob NRC Scime, Luke ORNL Tsao, John NRC Scott (guest) NA Turilin, Andrey NRC Semple, Jenny NSWC Carderock Twarek, Cameron NNL Sengupta, Abhijit DOE Nuclear Safety Tyree, Christopher NRC Czech Technical Ulmer, Christopher NRC Sevecek, Martin University Unknown user" NA Sewing, Luke Framatome Vail, Caroline NSWC Carderock SG NA Valentino, Anita WV House of Delegates Shaikh, Atif NRC van Rooyen, Shannon, Carinne Battelle Isabella J. PNNL Shoulders, Jacky Constellation Energy Vasquez, Jose NRC Sida, Karen NRC Vener, Luisa NNL Sinclair, LaToya NRC Verderber, Kimberly NYSERDA The Barnes Global Vollmer, James TerraPower Slattery, Kevin Advisors Walker, Shakur NRC Smith, John BWX Technologies Wallace, Jay NRC Smith, Laura NRC Webb, Tom NNL Soler, Mark Holtec Govt Services Wei, Xuejun CNSC Song, Rongjie INL University of Wisconsin Werz, Martin MPA Sridharan, Kumar - Madison White,Tessa NNL Stewart, Robb Boston Atomics Widrevitz, Dan NRC Subramanian, Ramesh Siemens Energy Williams, Robert NRC Sulley, John Rolls-Royce Wiltz, Christopher Framatome Sutton, Benjamin EPRI Wise, John NRC T., Janet NA Witherell, Paul NIST Talamantes-Silva, Sheffield Forgemasters Wolf, Carolyn NRC Jesus Engineering LTD Taller, Stephen ORNL Xu, Peng INL Talukdar, Priyam NRC Yee, On NRC Taylor, Nicholas NRC Yoder, Matthew NRC Terry, Leslie NRC Yoo, Mark NRC Thompson, Scott University of Missouri Young, Austin NRC Thompson, Young, Garrett Holtec Govt Services Spencer EOS North America Young, George A. Kairos Power Tokey, Jason NRC A-5 Name (last, first ) Organization
Yu, Zefeng Westinghouse Yutaka, Kadoya Embassy of Japan American Bureau of Zhang, Xi-Ying Shipping Zhang, Xuan ANL Ziabari, Amir ORNL
A-6 APPENDIX B: TABLE 6. PRESENTER BIOGRAPHIES (alphabetically, as available)
The information provided about the presenter biographies is based on that provided by the speakers. Thus there is variability in content and emphasis. Some speakers did not provide biographical information and thus are not listed below.
responsible for technical oversight of major projects on powder metallurgy, advanced ALEXANDREANU, Bogden is a Principal welding, AM, GEN IV alloys, and next-Nuclear Materials Engineer in the Nuclear generation erosion/wear resistant alloys. Mr.
Science and Engineering Division at Argonne Gandy has 36+ years of demonstrated National Laboratory. He is part of a research leadership and excellence in materials and team dealing with reliability issues in aging of welding technologies supporting the power nuclear reactor components. The research industry in the development and implementation focuses on the effects of environment on of advanced life prediction methodologies of component cracking, particularly on boiler, steam & gas turbine, reactor pressure environmental effects on fatigue crack initiation vessels, and heat recovery steam generators.
and growth, SCC of nickel alloys and weldments, effects of welding parameters and HUEGEL, David is a fellow engineer at defects on SCC.. Bogdan received MSc and Westinghouse and currently involved in PhD degrees in Nuclear Engineering and Westinghouses efforts in the area of AM and Radiological Sciences from The University of specifically laser powder bed fusion to produce Michigan at Ann Arbor. fuel related components. His background includes approximately 20 years in safety DEHOFF, Ryan is the Director of the analyses and the last 13 years in fuel assembly Manufacturing Demonstration Facility at ORNL. design. Mr. Huegel was directly involved in His focus of research includes understanding Westinghouses efforts to install an additively correlations between process conditions of manufactured thimble plugging device in Byron advanced manufacturing processes materials Unit 1 in the spring 2020 outage.
microstructure and mechanical performance.
HUFF, Richard is the Director, Industry FISHER, Kevin works for Fluor Marine Systems Consortia and Partnerships at ASTM and obtained a Ph.D. in Materials Science and International, leading the Consortium for Engineering at the University of Michigan. Materials Data and Standardization program.
FURRER, David is the Senior Fellow Discipline JOKISAARI, Andrea is a computational Lead for the Materials and Processes scientist in the Fuel Modeling and Simulation Engineering organization at Pratt & Whitney. He Department of INL. She is the INL lead for is responsible for leading the Pratt & Whitney DOEs Advanced Materials and Manufacturing Materials Discipline Leaders and Materials Technologies Program.
Fellows in the development of technical strategy and the development/improvement of LANE, Hillary is Director of Fuel and Radiation engineering standard work for all processes in Safety Generation and Supplies at NEI.
the discipline.
GANDY, David is a Senior Technical Executive LI, MeiMei is a Principal Materials Scientist and in EPRIs Nuclear Materials area where he is manages the Nuclear Materials Group in the
B-1 Nuclear Science and Engineering Division. Her design, safety justification, manufacture and research covers a broad area of nuclear operation. Most recently, Bill has applied his materials science and engineering including specialist technical knowledge to drive forward physical metallurgy, mechanical property (creep, the introduction of the Additive Manufacture fatigue, creep-fatigue), microstructural Technology within the business in order to characterization, radiation effects, and corrosion deliver important quality, cost and program of metallic materials for nuclear fission and benefits. He has over 25 years mechanical fusion energy applications. design experience working with Rolls-Royce Submarines and its alliance partners to support the UKs strategic defense capability.
MARTIN, John is the Director, Additive Manufacturing Research at America Makes.
RAWLS, George is the chair of the ASME -
Special Committee for Use of Additive MELFI, Teresa is a Technical Fellow with Manufacturing for Pressure Retaining Lincoln Electric Company. She has been Equipment. Now retired from Savannah River involved in the welding industry for over 30 National Laboratory, he heads GBR Consulting.
years, with roles in the manufacture, design and application of welding machines, consumables and processes. She supports the global welding RETTALIATA, Justin has over 20 years in and additive manufacturing communities industry and the federal government, working in through involvement in standards bodies, mechanical engineering, systems engineering, industry and academic projects and technical and program management. Justin is currently seminars. the Technical Warrant holder for AM in charge of the development of specifications and standards for how the NAVSEA adopts/utilizes MESSNER, Mark is a member of ANLs AM and serves as the technical lead for AM for technical staff. His research focused on NAVSEA. Justin holds a B.S. in Mechanical developing materials, design methods, and Engineering from Lehigh University, a Masters systems for high temperature concentrating in Business Administration from the College of solar power, nuclear, and aerospace William and Mary, and a Ph.D. in Systems applications. He is a member of the ASME Engineering from the George Washington Boiler & Pressure Vessel Code,Section III University.
Committee Subgroup on High Temperature Reactors, and serves on and chairs several relevant ASME working groups covering high SUBRAMANIAN, Ramesh is Principal Expert temperature reactor materials, design, and and Innovation Manager at Siemens. He construction. graduated with Ph.D. from Cornell University, in Materials Science & Engineering.
MONTOYO, Arturo holds a dual appointment as an Associate Professor in the Departments SULLEY, John is a European Registered of Civil and Environmental Engineer and UK Chartered Engineer, and a Engineering and Mechanical Engineering at Fellow of the UK Institution of Mechanical UTSA. He earned his Ph.D. from Columbia Engineers. He has 36 years of design, University manufacturing development, and justification experience of nuclear plant components working for Rolls-Royce Submarines. He has held PRESS, Bill is a Technical Specialist in positions of Chief Engineer, Chief Design component design within Rolls Royce Engineer, Chief of Engineering Capability, and Submarines. He has led technical projects A-10 Valves Internal Authority, and is currently a across a broad range of safety critical Rolls-Royce Associate Fellow. John is a components and vessels, supporting their member of two ASME Section III design code B-2 committees - valves and pumps. He has been heavily involved in instigating and implementing WERZ, Martin is the Head of Department advanced manufacturing techniques such as hot Joining Technology and Additive Manufacturing isostatic pressing and AM in Materials Testing Institute (MPA) University of Stuttgart.
TALAMANTES-SILVA, Jesus is the Research, Design and Technology Director at Sheffield WILTZ, Christopher has nearly 30 years in the Forgemasters in the United Kingdom. nuclear fuel assembly research & development, design, manufacturing and licensing. Wiltz is based in Richland, Washington and currently VAN ROOYEN, Isabella holds a Ph.D. in functions as the worldwide manager of physics, M.Sc. in metallurgy, and an MBA. She Framatomes design to cost and design to is the National Technical Director: Advanced manufacture activities, which includes Methods for Manufacturing Program for the US implementation and industrialization of new Department of Energy. She is also a products and technologies both internal and distinguished staff scientist at INL where she external to Framatome.
has led the advanced electron microscopy and micro-analysis examinations for the Advanced Gas Reactor TRISO fuel development program is a Materials Scientist in the ZHANG, Xuan since 2011. In addition, she is the principal Nuclear Science Engineering (NSE) Division at investigator of a variety of research projects for ANL. Her research focuses on the development nuclear applications that focus on areas and qualification of advanced structural alloys including TRISO coated particles, AM for nuclear reactor applications.
qualification reviews and AMM.
B-3
ML24254A266; ML24254A269 OFFICE RES/DE/CMB RES/DE/MEB RES/DE NAME EFocht EF SRuffin SR CAraguas CA DATE Sep 11, 2024 Sep 11, 2024 Sep 16, 2024