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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2023 ANS Winter Conference and Expo
November 12–15, 2023
Washington, D.C.|Washington Hilton
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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November 2023
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Fusion Science and Technology
Latest News
New TRIGA fuel delivered to a U.S. university reactor for the first time in a decade
Penn State’s Radiation Science and Engineering Center (RSEC) has received the first new TRIGA fuel shipped to the United States since 2012, the university announced on September 28. The fuel reached University Park, Pa., on September 27 and is destined for RSEC’s Breazeale Reactor, the nation’s longest continuously operating university research reactor.
Jing Wu, Yajing Chen, Jian Liu, Pengcheng Guo, Lei Xue, Lieming Yao
Fusion Science and Technology | Volume 79 | Number 5 | July 2023 | Pages 578-591
Technical Paper | doi.org/10.1080/15361055.2022.2162793
Articles are hosted by Taylor and Francis Online.
This paper studies electromagnetic (EM) loads during major disruptions and vertical displacement events by introducing a two-dimensional spatiotemporal plasma current attenuation filament profile derived from the DINA code. Three-dimensional geometry models of the HL-2M tokamak are established by ANSYS, including the plasma-facing components (PFCs), the vacuum vessel (VV), poloidal magnetic field/central solenoid magnetic field coils, and divertor. Eddy currents are induced with plasma current decay and flow into the PFC components. The interaction between eddy currents and magnetic fields generates enormous EM forces and torques. The halo current also flows into the VV and divertor components from the inner and outer target plates, the demo plate, and the cassette box. The halo current–induced EM loads are the most substantial forces in the inward radial and upward vertical forces for the VV and divertor. The simulation results provide a reference for the design and safety assessment of the magnetically confined tokamak HL-2M.