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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.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Disney World should have gone nuclear
There is extra significance to the American Nuclear Society holding its annual meeting in Orlando, Florida, this past week. That’s because in 1967, the state of Florida passed a law allowing Disney World to build a nuclear power plant.
M. Nishikawa, K. Munakata, T. Takeishi, A. Baba, T. Kawagoe, S. Beloglazov, N. Nakashima, K. Hashimoto, Yokoyama, K. Okuno, Y. Morimoto, H. Moriyama, K. Kawamoto
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 1025-1029
Blanket Material and Process | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22739
Articles are hosted by Taylor and Francis Online.
Release curve of bred tritium from various ceramic breeder materials such as Li2ZrO3, Li2TiO3, and Li4SiO4 were obtained using the out-pile temperature programmed desorption method in the Kyoto University Research Reactor. A 0.4g sample of breeder particles contained in a quartz tube was irradiated for 120s at the thermal neutron flux of about 2.8x1017n/m2s in N2 atmosphere under the temperature of 360K. Tritium release behavior was measured using an ionization chamber connected to the release tritium measurement apparatus. The sample was purged by dry N2, N2 with hydrogen of various partial pressure, or humidified N2 gas. The temperature of the sample bed was changed linearly from room temperature to 1073K with the rising rate of 5K/min.Characteristics of tritium release behavior obtained for various ceramic breeder materials under various purge gas conditions are compared in this paper.
