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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
William L. Daugherty, K. Linga Murty
Nuclear Technology | Volume 80 | Number 3 | March 1988 | Pages 443-450
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT88-A34068
Articles are hosted by Taylor and Francis Online.
X-ray diffraction techniques have been used to measure the texture of Zircaloy-4, which is described quantitatively by the crystallite orientation distribution function (CODF). Procedures for evaluating the anisotropy parameters in the modified Hill equation (R and P) from the CODF and their use in predicting creep behavior are reviewed. Alternatively, the same anisotropy parameters can be obtained from creep test data using appropriate mechanical deformation concepts. These R and P parameters are used to predict the creep behavior of fuel rod cladding both out of pile and in pile. The procedures involved in obtaining the anisotropy parameters from either crystallographic texture data or creep test data are summarized. These two approaches, previously discussed separately in the literature, are brought together for a direct comparison. Predictions of creep behavior based on texture measurements are compared with creep data. The utility of the anisotropy parameters in predicting postirradiation cladding dimensions is illustrated by reviewing the work of another research group. Excellent agreement between their model predictions and experimental results of postirradiation examination is observed.