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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.
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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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MIT’s nuclear professional courses benefit United States—and now Australia too
Some 30 nuclear engineering departments at universities across the United States graduate more than 900 students every year. These young men and women are the present and future of the domestic nuclear industry as it seeks to develop and deploy advanced nuclear energy technologies, grow its footprint on the power grid, and penetrate new markets while continuing to run the existing fleet of reactors reliably and economically.
Jiyun Zhao, C. P. Tso, K. J. Tseng
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 78-88
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT12-A14520
Articles are hosted by Taylor and Francis Online.
The effects of two-phase-flow modeling on nuclear reactor single-channel stability analysis are investigated with four two-phase-flow models, namely, the homogeneous-equilibrium model, the homogeneous-nonequilibrium model, the nonhomogeneous-equilibrium model, and the nonhomogeneous-nonequilibrium model. The models are applied to hot-channel analyses of a proposed typical supercritical-water-cooled-reactor (SCWR) design. The neutral stability boundaries derived by using the four models are compared and plotted on the traditional subcooling number versus phase change number plane. To ensure proper development of the models, they are benchmarked to the experimental data. It is found that the homogeneous models predict more conservative stability boundaries than the nonhomogeneous models and that the differences of the stability boundaries predicted by all four two-phase-flow models are reduced under higher-pressure conditions.