ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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!
Latest Magazine Issues
Dec 2024
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
ANS standard updated for determining meteorological information at nuclear facilities
Following approval in October from the American National Standards Institute, ANSI/ANS-3.11-2024, Determining Meteorological Information at Nuclear Facilities, was published in late November. This standard provides criteria for gathering, assembling, processing, storing, and disseminating meteorological information at commercial nuclear power plants, U.S. Department of Energy/National Nuclear Security Administration nuclear facilities, and other national or international nuclear facilities.
Sergey S. Gorodkov
Nuclear Science and Engineering | Volume 172 | Number 2 | October 2012 | Pages 193-201
Technical Paper | doi.org/10.13182/NSE11-105
Articles are hosted by Taylor and Francis Online.
Significant underprediction bias in uncertainties of neutron flux is observed in Monte Carlo criticality calculations of large cores. It is universally recognized that this underprediction is closely associated with the ratio of the second-largest eigenvalue to the largest eigenvalue, or the dominance ratio, of the fission kernel. In this paper a close analogy is presumed between neutron flux autocorrelations in Monte Carlo calculations and flux variances due to stochastic uncertainties of the properties of fuel assemblies within the manufacturing tolerance limits. Interesting consequences following from this analogy are confirmed in quite realistic calculations. A useful expression is derived for fast evaluation of the minimal number of histories to be modeled to achieve preset confidence limits of flux distribution in large cores.