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2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
Meysam Karimi, Behrooz Shayegh Boroujeny, Hadi Adelkhani, Seyed Masoud Araghchi
Nuclear Science and Engineering | Volume 200 | Number 8 | August 2026 | Pages 1911-1923
Research Article | doi.org/10.1080/00295639.2025.2551472
Articles are hosted by Taylor and Francis Online.
Zirconium alloys are vital for nuclear fuel cladding. Surface mechanical attrition treatment (SMAT) improves mechanical properties, with treatment duration playing a crucial role in grain refinement and corrosion resistance. This study examines SMAT’s impact on Zr-1%Nb alloy microstructure, hardness, and wear resistance. Samples were treated for 4, 8, and 12 min and compared to untreated ones. X-ray diffraction analysis revealed grain size reduction from 1.8 µm (untreated) to 0.76 µm (4 min), 0.43 µm (8 min), and 0.21 µm (12 min). SMAT also induced compressive residual stresses of 167 MPa (4 min), 186 MPa (8 min), and 225 MPa (12 min). Hardness increased from 220 Hv0.1 (untreated) to 282 Hv0.1 (12 min). However, surface roughness rose from 0.064 to 0.579 µm after 12 min. Corrosion resistance improved, especially with a passive coating, reducing corrosion rates. In conclusion, SMAT enhances Zr-1%Nb alloy properties—refining microstructure, increasing hardness, improving wear and corrosion resistance—despite higher surface roughness.