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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
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
IEA report: Challenges need to be resolved to support global nuclear energy growth
The International Energy Agency published a new report this month outlining how continued innovation, government support, and new business models can unleash nuclear power expansion worldwide.
The Path to a New Era for Nuclear Energy report “reviews the status of nuclear energy around the world and explores risks related to policies, construction, and financing.”
Find the full report at IEA.org.
D. C. Leslie, A. Jonsson
Nuclear Science and Engineering | Volume 23 | Number 3 | November 1965 | Pages 272-290
Technical Paper | doi.org/10.13182/NSE23-03-272
Articles are hosted by Taylor and Francis Online.
A method of calculating first-flight collision probabilities in cluster geometry is developed. The method is analytic and approximate and is comparable in speed to codes now available for annular geometry. The proposed scheme is based on a consideration of the properties of the nonescape probability from a nonuniform body in the limits of high and low macroscopic cross sections, together with an interpolation procedure that allows one to determine the probability itself with sufficient accuracy. When calculated for combinations of different rings of fuel pins in a cluster, the resulting set of nonescape probabilities enables one to proceed to a determination of the probability of going from one ring to another. The coolant and the fuel pins are treated separately. Results of the method are compared with exact calculations on two fuel-element types of current interest. In these cases the form factor, defined as the ratio of maximum to mean flux in the cluster, is in error by at most 2%. The hyperfine structure in each ring (i.e. the ratio of the mean flux in the coolant to the mean flux in the fuel) is calculated with comparable accuracy. A one-group calculation on a 37-rod fuel element takes approximately 5 sec on an IBM-7090, so that the method is certainly usable for multigroup applications.