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Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
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.