ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Moo-Hoon Bae, Gwanyoung Kim (KINS), Taewan Kim (Incheon National Univ), Ae Ju Cheong (KINS)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 143-147
In order to enhance the capability to perform realistic analyses of the core neutronic behavior and the plant system dynamics in respect of accidents with asymmetric core power such as main team line break (MSLB), a three-dimensional reactor kinetics model has been incorporated into a system thermal-hydraulic (T/H) code. In this study, we developed a PARCS core model for coupling with a TRACE 3D T/H model for the reactor vessel and performed a steady-state calculation prior to a MSLB accident for the Advanced Power Reactor-1400 plant.