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Division Spotlight
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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC 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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Latest News
Drones fly in to inspect waste tanks at Savannah River Site
The Department of Energy’s Office of Environmental Management will soon, for the first time, begin using drones to internally inspect radioactive liquid waste tanks at the department’s Savannah River Site in South Carolina. Inspections were previously done using magnetic wall-crawling robots.
Saam Yasseri, Farzad Rahnema
Nuclear Science and Engineering | Volume 176 | Number 3 | March 2014 | Pages 292-311
Technical Paper | doi.org/10.13182/NSE13-9
Articles are hosted by Taylor and Francis Online.
In this paper, a new spatial homogenization method in transport theory is developed that reproduces the heterogeneous solution by using conventional flux-weighted homogenized cross sections. By introducing an additional source term via an auxiliary cross section, the resulting homogeneous transport equation becomes consistent with the heterogeneous equation, enabling easy implementation into existing solution methods/codes. This new method utilizes on-the-fly rehomogenization, performed at the assembly level, to correct for the effect of core environment on the homogenized cross sections. The method is derived in general geometry and continuous energy and implemented and tested in fine-group one-dimensional slab geometries typical of boiling water reactor and gas-cooled reactor cores. The test problems include two single-assembly and four-core configurations.