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
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
DOE-EM awards $37.5M to Vanderbilt University for nuclear cleanup support
The Department of Energy’s Office of Environmental Management announced on January 16 that it has awarded a noncompetitive financial assistance agreement worth $37.5 million to Vanderbilt University in Nashville, Tenn., to aid the department’s mission of cleaning up legacy nuclear waste.
RAYMOND T. SHANSTROM, MANSON BENEDICT
Nuclear Science and Engineering | Volume 11 | Number 4 | December 1961 | Pages 377-385
Technical Paper | doi.org/10.13182/NSE61-A26039
Articles are hosted by Taylor and Francis Online.
FUELCYC is a code, written in the Fortran II language for a 32,000-word IBM 704 computer, which has been developed for the study of fuel cycles in large cylindrical thermal power reactors. It is a two-dimensional diffusion-theory code in which it is assumed that the reactor core is symmetrical in the azimuthal direction. Core properties such as the fuel composition, burnup, flux and power-density distributions, and reactivity can be calculated throughout the life history of the fuel for different methods of managing fuel and control poisons. Only a few minutes of computer time are required for a complete fuel-cycle analysis of the life history of the core.