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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Nam-Il Tak, Min-Hwan Kim, Hong Sik Lim, Jae Man Noh
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 352-365
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A13480
Articles are hosted by Taylor and Francis Online.
For the thermal analysis and the design of a prismatic gas-cooled reactor, local analyses have been widely used by modeling a unit cell or single assembly instead of a whole-core geometry. In spite of the recent rapid development of the computational fluid dynamics (CFD) technology, a whole-core CFD analysis for a prismatic reactor still requires tremendous computational expense and might be a heavy burden for designers desiring a large number of calculations with various design options.This paper provides a practical method for the whole-core thermal analysis of a prismatic gas-cooled reactor. The method combines the merits of CFD and system approaches in order to provide the detailed analysis without much computational expense. It solves the three-dimensional heat conduction equation for a solid as in a CFD code. On the other hand, one-dimensional conservation equations are adopted for a fluid as in a system code. With such a combination, a significant reduction in the computational expense, as well as reasonable accuracy, is achieved. In addition, the present method adopts the basic unit cell concept, which eliminates an elaborate grid generation process. Detailed geometries and materials of the prismatic fuel and reflector blocks are efficiently modeled using the basic unit cells.