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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Investment bill would provide funding options for energy projects
Coons
Moran
The bipartisan Financing Our Futures Act, which expands certain financing tools to all types of energy resources and infrastructure projects, was reintroduced to the U.S. Senate on February 20 by Sens. Jerry Moran (R., Kan.) and Chris Coons (D., Del.).
Via amendment to the Internal Revenue Code, the legislation would allow advanced nuclear energy projects to form as master limited partnerships (MLPs), a tax structure currently available only to traditional energy projects.
An MLP is a business structure that is taxed as a partnership but the ownership interests of which are traded like corporate stock on a market. Until the Internal Revenue Code is amended, MLPs will continue to be available only to investors in energy portfolios for oil, natural gas, coal extraction, and pipeline projects that derive at least 90 percent of their income from these sources. This change would take effect on January 1, 2026.
W. P. Barthold, J. C. Beitel
Nuclear Technology | Volume 44 | Number 1 | June 1979 | Pages 44-60
Technical Paper | Reactor | doi.org/10.13182/NT79-A32237
Articles are hosted by Taylor and Francis Online.
Six homogeneous and heterogeneous core configurations with different fuel pin diameters and different degrees of neutronic coupling have been analyzed. All designs were based on the same design assumptions and constraints. Homogeneous and heterogeneous designs were evaluated with respect to fissile inventory, flux and power distribution, burnup, breeding ratio and doubling times, sodium void reactivity, Doppler coefficient, control rod worth, and transient response. The sensitivity of breeding performance to different fuel life criteria was determined.
