AMP 05 July-August 2025

ADVANCED MATERIALS & PROCESSES | JULY/AUGUST 2025 20 Exposure, Journal of Nuclear Materials, 276(1-3), p 123-142, 2000. 10. F. Onimus, et al., Irradiation Creep in Materials, Comprehensive Nuclear Materials, 1, p 310-366, 2021. 11. M.R. Gilbert, et al., Neutron-induced DPA, Transmutations, Gas Production, and Helium Embrittlement of Fusion Materials, Journal of Nuclear Materials, 442, p S755-S760, 2013. 12. M.E. Sawan, Damage Parameters of Structural Materials in Fusion Environment Compared to Fission Reactor Irradiation, Fusion Engineering and Design, 87(5-6), p 551-555, 2012. 13. R. Behrich, et al., Material Erosion at the Vessel Walls of Future Fusion Devices, Journal of Nuclear Materials, 313-316, p 388-392, 2003. 14. M. Imran, et al., Studies of Erosiondeposition of Plasma-facing Materials due to Plasma-wall Interactions in East Tokamak, Journal of Nuclear Materials, 598, p 155195, 2024. 15. R.A. Pitts, et al., Material Erosion and Migration in Tokamaks, Plasma Physics and Controlled Fusion, 47(12B), p B303-B322, 2005. 16. ARPA-E, https://arpa-e.energy.gov/ programs-and-initiatives/search-all- projects?filter[field_reference_program]=chadwick. 17. C. Hatler, et al., The Path Towards Plasma Facing Components: A Review of State-of-the-Art in W-based Refractory High-entropy Alloys, Current Opinion in Solid State and Materials Science, 34, p 101201, 2025. 18. A. Nisar, et al., A Perspective on Challenges and Opportunities in Developing High Entropy Ultrahigh Temperature Ceramics, Ceramics International, 46(16), p 25845-25853, 2020. 19. M. Moschetti, et al., Design Considerations for High Entropy Alloys in Advanced Nuclear Applications, Journal of Nuclear Materials, 567, p 153814, 2022. 20. D. Raabe, et al., Grain Boundary Segregation Engineering in Metallic Alloys: A Pathway to the Design of Interfaces, Current Opinion in Solid State and Materials Science, 18(4), p 253-261, 2014. 21. P.R. Cantwell, et al., Grain Boundary Complexion Transitions, Annual Review of Materials Research, 50, p 465-492, 2020. 22. L. Zhang, Understanding the Radiation Resistance Mechanisms of Nanocrystalline Metals from Atomistic Simulation, Metals, 11(11), p 1875, 2021. 23. G. Sabiston, et al., Volumetrically Complex Materials for Reducing Electric Propulsion Facility Effects, IEPC-2022594, 2022. 24. S. Smolentsev, et al., Integrated Liquid Metal Flowing First Wall and Open-surface Divertor for Fusion Nuclear Science Facility: Concept, Design and Analysis, LLNL-JRNL-818277, 2021. 25. ASTM, Standard Test Method for Thermal Diffusivity by the Flash Method, https://www.astm.org/e146113r22.html. 26. ASTM, Standard Test Methods for Elevated Temperature Tension Tests of Metallic Materials, https://www.astm. org/e0021-20.html. 27. X. Qian, et al., Comparative Study of Helium Bubbles, Microstructure, and Mechanical Properties in the White Bright Band of SA508-3/52 Dissimilar Metal Weld Joints, Journal of Materials Research and Technology, 33(1), p 77617766, 2024. 28. H.Y. Fu, et al., Effect of Post-weld Heat Treatment and Neutron Irradiation on a Dissimilar-metal Joint between F82H Steel and 316L Stainless Steel, Fusion Engineering and Design, 98, p 1968-1972, 2015. lead scientist, Booz Allen Hamilton, trivedi_pankaj@bah.com; and Ahmed Diallo, program director, Advanced Research Projects Agency-Energy, ahmed. diallo@hq.doe.gov. References 1. S. Wurzel, et al., Progress Toward Fusion Energy Breakeven and Gain as Measured Against the Lawson Criterion, Physics of Plasmas, 29, p 062103, 2022. 2. A. Quadling, et al., Materials Challenges for Successful Roll-out of Commercial Fusion Reactors, Journal of Physics: Energy, 4, p 030401, 2022. 3. B.L. Garcia-Diaz, et al., The ‘Softer’ Side of Fusion Materials Development, Advanced Materials & Processes, 181(6), p 12-16, 2023. 4. A. Bhattacharya, et al., Irradiation Hardening and Ductility Loss of Eurofer97 Steel Variants After Neutron Irradiation to ITER-TBM Relevant Conditions, Fusion Engineering and Design, 173, p 112935, 2021. 5. A. Bhattacharya, et al., Irradiation Damage Concurrent Challenges with RAFM and ODS Steels for Fusion Reactor First-wall/Blanket: A Review, Journal of Physics: Energy, 4(3), p 034003, 2022. 6. X. Gao, et al., Effects of Irradiation Plus Thermal Aging on the Phase Boundary Microstructure of Austenitic Stainless-Steel Welds, Materials Characterization, 217(1-2), p 114367, 2024. 7. D.L. Smith, et al., Performance Limits for Fusion First-wall Structural Materials, Journal of Nuclear Materials, 283-287, p 716-720, 2000. 8. S. Taller, et al., Predicting Structural Material Degradation in Advanced Nuclear Reactors with Ion Irradiation, Scientific Reports, 11(1), p 2949, 2021. 9. F.A. Garner, et al., Comparison of Swelling and Irradiation Creep Behavior of FCC-austenitic and BCC-ferritic/ martentic Alloys at High Neutron GET ENGAGED, GET INVOLVED, GET CONNECTED The ASM Advanced Materials Manufacturing Committee was launched in 2023 and ASM members with interest and experience in additive manufacturing and other materials processing and manufacturing innovations are welcome to join. Visit the ASM Connect home page at connect.asminternational.org to post information or ask questions related to advanced manufacturing. For more information, contact committee chair Emily Kinser, FASM, or staff liaison Scott Henry, matinfo@asminternational.org.

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