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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Latest News
First GAIN vouchers of 2025 go to Curio, Deep Fission, Kairos, and NuCube Energy
The Department of Energy’s Gateway for Accelerated Innovation in Nuclear (GAIN) has awarded four fiscal year 2025 vouchers to support the development of advanced nuclear technologies. Each company will get access to specific capabilities and expertise in the DOE’s national laboratory complex—in this round of awards both Idaho National Laboratory and Pacific Northwest National Laboratory are named—and will be responsible for a minimum 20 percent cost share, which can be an in-kind contribution.
Craig E. Peterson, John G. Shatford, Ardesar Irani, Nicholas G. Trikouros, Antonio F. Dias, Lance J. Agee
Nuclear Technology | Volume 128 | Number 2 | November 1999 | Pages 233-244
Technical Paper | RETRAN | doi.org/10.13182/NT99-A3028
Articles are hosted by Taylor and Francis Online.
A main-steam-line-break accident analysis for Three Mile Island Unit 1 is performed with point kinetics and three-dimensional kinetics with RETRAN-3D MOD002. These analyses were performed to demonstrate differences in results that can be expected due to different reactor kinetics models. To illustrate the difference in kinetics models, the RETRAN-3D models used for both analyses were the same with the exception of the reactor core modeling. The key assumptions and methods used to model loop mixing are described.The point-kinetics analysis demonstrates a significant return-to-power following the reactor trip while the three-dimensional kinetics case does not. This study shows that three-dimensional core transient modeling provides margin to recriticality over a point-kinetics approach. Such margin is desirable to allow for power uprate and extended refueling cycles.