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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
Is waste really waste?
Tim Tinsley
I’ve been reflecting on the recent American Nuclear Society Winter Conference and Expo, where I enjoyed the discussion on recycling used nuclear fuel to recover valuable minerals or products for future applications. I have spent more than 30 years focusing on dissolving and separating nuclear material, so it was refreshing to hear the case for new applications being made. However, I feel that these discussions could go further still.
Radiation is energy, something that our society seems to have an endless need for. A nuclear power station produces a lot of radiation that is mostly discarded. But once fuel has been used, it still produces significant levels of radiation and heat energy. The associated storage, processing, and eventual disposal of this used fuel requires careful management and investment to protect systems and people from the radiation. Should we really disregard—and discard—this energy source, along with all the valuable minerals in the used fuel, when we could instead use it to deliver significant value to society?
Edward W. Larsen, Blake W. Kelley
Nuclear Science and Engineering | Volume 178 | Number 1 | September 2014 | Pages 1-15
Technical Paper | doi.org/10.13182/NSE13-47
Articles are hosted by Taylor and Francis Online.
The coarse-mesh finite difference (CMFD) and the coarse-mesh diffusion synthetic acceleration (CMDSA) methods are widely used, independently developed methods for accelerating the iterative convergence of deterministic neutron transport calculations. In this paper, we show that these methods have the following theoretical relationship: If the standard notion of diffusion synthetic acceleration as a fine-mesh method is straightforwardly generalized to a coarse-mesh method, then the linearized form of the CMFD method is algebraically equivalent to a CMDSA method. We also show theoretically (via Fourier analysis) and experimentally (via simulations) that for fixed-source problems, the CMDSA and CMFD methods have nearly identical convergence rates. Our numerical results confirm the close theoretically predicted relationship between these methods.