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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
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
David P. Chan, David L. Larkin
Nuclear Technology | Volume 76 | Number 3 | March 1987 | Pages 319-324
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33917
Articles are hosted by Taylor and Francis Online.
Boiling water reactor fuel channels bulge and bow because of pressure, temperature, fast neutron flux, and their gradients. Channel deformations can be calculated by means of the finite element technique. Calculated bulge and bow results for WNP-2 fuel channels in different core locations and at different power levels have been obtained as functions of core residence time. In general, channel bulge is largest at the core center and decreases toward the core periphery. Bulge increases with the power level and the core residence time. Channel bow is largest at the core periphery and decreases for the next two rows of channels radially inward. Bow rate is highest in the first reactor cycle and then decreases. After an initial period, bow ceases to increase with residence time and may even decrease. The analytical results are being used by the Channel Management Program at Washington Public Power Supply System to optimize the utilization of fuel channels.