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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
Bipartisan nuclear waste bill introduced in U.S. House
U.S. representatives Mike Levin (D., Calif.) and August Pfluger (R., Texas) have introduced the bipartisan Nuclear Waste Administration Act of 2024, which would establish an independent agency to manage the country’s nuclear waste.
In addition to establishing a new, single-purpose administration to manage the back end of the nuclear fuel cycle, the bill would direct a consent-based siting process for nuclear waste facilities and ensure reliable funding for managing nuclear waste by providing access to the Nuclear Waste Fund. According to Pfluger and Levin, the bill’s provisions are in line with recommendations from the Blue Ribbon Commission on America’s Nuclear Future.
Constantine P. Tzanos
Nuclear Technology | Volume 82 | Number 1 | July 1988 | Pages 5-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34113
Articles are hosted by Taylor and Francis Online.
A method was developed for the analysis of a once-through steam generator that is based on a multinode movable boundary formulation and an accurate description of the departure from nucleate boiling boundary. In the development of this method, a liquid-metal reactor steam generator was used as a reference design. To evaluate its performance, the Energy Technology Engineering Center steam generator shutdown experiment in the once-through mode was analyzed. Also, the predictions of this method were compared with those of another steam generator code. These analyses showed that the predictions of this methodology agree very well with the experimental measurements and the predictions of the other code. The maximum difference between the temperatures predicted by this model and measurements was ∼5 K.
