ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
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January 2025
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Latest News
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Peter J. Jensen, Kent D. Richert, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 290-302
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33882
Articles are hosted by Taylor and Francis Online.
A RETRAN-02 analysis was performed for a loss-of-feedwater transient without scram for a Westinghouse four-loop plant with Series 51 steam generators. A goal of this study was to use the same plant parameters that were used by Westinghouse in a report issued in December 1979. The primary differences in results from the two studies can be attributed to differences in the two methodologies. Sensitivity of the primary pressure response to steam generator nodalization, turbine trip time, moderator reactivity feedback coefficients, and Doppler reactivity coefficients was also studied.