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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Natalie Cannon is passionate about nuclear policy
Some people are born leaders, and some people make themselves leaders. Take Natalie Cannon, a fourth-year doctoral candidate in the Department of Nuclear and Radiological Engineering and Medical Physics at the Georgia Institute of Technology. She has been driven to succeed since she was a teenager in Southern California, when she was inspired by NASA’s Mars Exploration Program.
Xing L. Yan, Tetsuaki Takeda, Tetsuo Nishihara, Kazutaka Ohashi, Kazuhiko Kunitomi, Nobumasa Tsuji
Nuclear Technology | Volume 163 | Number 3 | September 2008 | Pages 401-415
Technical Paper | Fission Reactors | doi.org/10.13182/NT08-A3998
Articles are hosted by Taylor and Francis Online.
A rupture of the primary piping in the helium-cooled and graphite-moderated high-temperature gas-cooled reactor (HTGR) represents a design-basis event that should not result in significant safety consequences. In such a loss-of-coolant event, the reactor would be shut down inherently, and the decay heat would be removed passively with the ultimate reactor temperature rise being less than the design limit. Still, an important concern for reactor safety continues to be graphite oxidation damage to the fuel and core should a major air ingress take place through the breached primary pressure boundary. Two major cases of air ingress are studied. The first case results from the rupture of a control rod or refuel access standpipe atop the reactor pressure vessel (RPV). To rule out the possibility of such a standpipe rupture, a design change is proposed in the vessel top structure. The feasibility of the modified vessel local structure is evaluated. The second case of air ingress results from the rupture of one or more main coolant pipes on the lower body of the RPV. Experiment and analysis are performed to understand the multiphased air ingress phenomena in the depressurized reactor. Accordingly, a new passive mechanism of sustained counter air diffusion is proposed and shown to be effective in preventing major air ingress through natural circulation in the reactor. The results of the present study are expected to enhance the HTGR safety and economics.