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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
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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Latest News
US, Korea sign MOU for nuclear cooperation
The U.S. departments of Energy and State have signed a memorandum of understanding with the Republic of Korea’s ministries of Trade, Industry and Energy and of Foreign Affairs for the two nations to partner on nuclear exports and cooperation.
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.