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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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July 2025
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Latest News
Hinkley Point C gets over $6 billion in financing from Apollo
U.S.-based private capital group Apollo Global has committed £4.5 billion ($6.13 billion) in financing to EDF Energy, primarily to support the U.K.’s Hinkley Point C station. The move addresses funding needs left unmet since China General Nuclear Power Corporation—which originally planned to pay for one-third of the project—exited in 2023 amid U.K. government efforts to reduce Chinese involvement.
Jordan A. Evans, Scott A. Anderson, Eric J. Faierson, Delia Perez-Nunez, Sean M. McDeavitt
Nuclear Technology | Volume 205 | Number 4 | April 2019 | Pages 563-581
Technical Paper | doi.org/10.1080/00295450.2018.1502001
Articles are hosted by Taylor and Francis Online.
In this experiment, Type 316L stainless steel rods were fabricated through laser additive manufacturing (LAM) in three different orientations, and microstructural and mechanical changes induced by high dose ion irradiation were characterized based on orientation. The rods were irradiated with Fe2+ self-ions to a peak dose of 80 displacements per atom at 475°C. Results were compared to concurrently irradiated conventionally manufactured control specimens. Electron backscatter diffraction of the rods yielded statistically relevant information related to grain microstructure and texture. Transmission electron microscopy revealed a high density of elongated radiation-produced defects in the LAM specimens that were aligned with the major axes of the defects parallel to the build direction. Mechanical testing of LAM rods revealed anisotropic radiation-induced hardening, where hardening is greatest perpendicular to the build direction and least parallel to the build direction. Several radiation-induced hardening phenomena are considered that contribute to the observed anisotropic strengthening.