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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Yoshinori Miyoshi, Masafumi Itagaki, Masanori Akai, Hideyuki Hirose, Masao Hashimoto
Nuclear Technology | Volume 103 | Number 3 | September 1993 | Pages 380-391
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT93-A34858
Articles are hosted by Taylor and Francis Online.
In the nuclear criticality safety design of a nuclear fuel cycle facility, the geometric buckling of the fuel core is one of the most important quantities used in estimating criticality. When the material buckling value is known for a system consisting of fissile materials, it is possible to judge whether or not the system is subcritical by comparing the material buckling with the geometric buckling. It is widely known that the geometric buckling of a given core can be calculated by using a simple formula for some geometries, e.g., square, cylinder, slab, and sphere. The experimental results of the geometrical buckling for typical regular polygons are described. Geometric buckling for three types of regular polygons has been measured in light-water-moderated UO2-H2O lattices in the tank-type critical assembly at the Japan Atomic Energy Research Institute. Based on the known critical buckling of a given experimental lattice and the measured critical water levels, the horizontal buckling has been evaluated for various sizes of regular hexagonal, square, and regular triangular cores. This method is based on the separability of geometric buckling into horizontal and vertical components. From the measured critical water levels of each core, it was found that the horizontal buckling of the effective core region is inversely proportional to the square of the radius of the circumscribed circle of the core. The geometric buckling can therefore be expressed in the form of (aN/Rc)2 using the geometric constant aN. The data for geometric buckling values on these geometries are available for the validation of calculation codes, and the empirical formula for geometric buckling obtained in this study can be applied to the basic criticality safety design of fuel cycle facilities.