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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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
Hot Fuel Examination Facility named a Nuclear Historic Landmark
The American Nuclear Society recently announced the designation of three new nuclear historic landmarks: the Hot Fuel Examination Facility (HFEF), the Neely Nuclear Research Center, and the Oak Ridge Gaseous Diffusion Plant. Today’s article, the first in a three-part series, will focus on the historical significance of HFEF.
Hiromi Maruyama, Junichi Koyama, Motoo Aoyama, Kazuya Ishii, Atsushi Zukeran, Takashi Kiguchi, Akira Nishimura
Nuclear Technology | Volume 118 | Number 1 | April 1997 | Pages 3-13
Technical Paper | Kiyose Birthday Anniversary Special / Fission Reactor | doi.org/10.13182/NT97-A35351
Articles are hosted by Taylor and Francis Online.
A core analysis system has been developed for the recent advanced designs of boiling water reactors. This system consists of a fuel assembly analysis code VMONT and a three-dimensional core simulator COSNEX. To cope with heterogeneous structures found in the recent high-performance fuel, VMONT employs a Monte Carlo neutron transport calculation method. COSNEX is based on a three-group nodal expansion method to treat spectral interactions among fuel assemblies. Both codes are vectorized to meet timing requirements as design tools. The analysis system is verified by the tracking of recent plant operations. Although the analyzed cores are highly heterogeneous in the multienrichment configuration, the system gives sufficient accuracy both in critical eigenvalues and thermal power distributions.