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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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November 2024
Latest News
Acceleron Fusion raises $24M in seed funding to advance low-temp fusion
Cambridge, Mass.–based fusion startup Acceleron Fusion announced that it has closed a $24 million Series A funding round co-led by Lowercarbon Capital and Collaborative Fund. According to Acceleron, the funding will fuel the company’s efforts to advance its low-temperature muon-catalyzed fusion technology.
Rodolfo M. Ferrer, Joel D. Rhodes III
Nuclear Science and Engineering | Volume 182 | Number 2 | February 2016 | Pages 151-165
Technical Paper | doi.org/10.13182/NSE15-6
Articles are hosted by Taylor and Francis Online.
A linear source (LS) approximation scheme is presented for the two-dimensional method of characteristics (MOC). The LS approximation relies on the computation of track-based spatial moments over source regions to obtain the LS expansion coefficients. The proposed LS scheme improves the solution accuracy relative to the constant or flat source (FS) approximation. The LS scheme is capable of treating arbitrarily shaped source regions under isotopic or anisotropic scattering assumptions. The LS scheme is also compatible with standard coarse-mesh finite difference acceleration. Numerical tests presented for the C5G7 mixed oxide benchmark show that for comparable accuracy with respect to the reference solution, the LS approximation can reduce the run time by a factor of 4 and the memory requirements by a factor of 10 relative to the FS scheme. This is because the LS scheme permits the use of a much coarser grid than the FS scheme. Numerical tests presented for simple cold critical core configurations with anisotropic scattering confirm the advantage of using the LS scheme.