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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Chang Hyo Kim, Jin Young Cho, Han Gyu Joo
Nuclear Science and Engineering | Volume 118 | Number 2 | October 1994 | Pages 108-121
Technical Paper | doi.org/10.13182/NSE94-A28540
Articles are hosted by Taylor and Francis Online.
Three-dimensional (3D) correction factors designed to take into account the heterogeneity effects of the missing dimension in two-dimensional (2D) reactor computation are rigorously defined. An approximate method for computing the 3D correction factors is proposed by introducing simplified model cores. For verification of the proposed method, 2D and 3D ROCS code computations are performed for the first three cycles of the Yonggwang Unit 2 pressurized water reactor. The utility of the proposed method is then discussed by demonstrating that the 2D ROCS results with the use of the approximate 3D correction factors agree well with the 3D ROCS results in the letdown behavior of the critical soluble boron concentration and the core power distribution.