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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
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.