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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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July 2025
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
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.
