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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Yousri Elkassabgi, Graydon L. Yoder, Wallace R. Gambill
Nuclear Technology | Volume 105 | Number 3 | March 1994 | Pages 411-420
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT94-A34940
Articles are hosted by Taylor and Francis Online.
The Advanced Neutron Source Reactor (ANSR) is being designed to become the world’s most advanced reactor for neutron scattering research. It is both moderated and cooled by heavy water (D2O) and uses a core of highly enriched uranium silicide fuel in a plate geometry. During the refueling process of the ANSR, the spent fuel must be moved from within the primary coolant loop (containing D2O), through a pool of D2O, and finally into a light water spent-fuel storage area. This is accomplished by using a refueling tunnel and fuel transfer cask or lock. Some means of cooling the core, using either natural circulation or forced convection, must be accommodated during this process. Several thermal-hydraulic aspects of this refueling process have been studied. A modified version of the NATCON computer code developed at Argonne National Laboratory was used for the analysis. The NATCON code was revised and modified to incorporate improved friction and heat transfer correlations, and routines for the physical properties of D2O were added. The revised code can also accommodate a two-dimensional power density distribution. The results for the refueling process design show that ∼48 h is required to ensure the no-boiling condition. The addition of a short chimney reduces that time to ∼12 h.
