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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Oklo completes end-to-end demonstration of advanced fuel recycling
Oklo Inc. has announced that it has completed the first end-to-end demonstration of its advanced fuel recycling process as part of an ongoing $5 million project in collaboration with Argonne and Idaho National Laboratories. Oklo’s goal: scaling up its fuel recycling capabilities to deploy a commercial-scale recycling facility that would increase advanced reactor fuel supplies and enhance fuel cost effectiveness for its planned sodium fast reactors.
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.
