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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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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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.
S. Bian
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 401-407
Technical Note | Reactor | doi.org/10.13182/NT78-A32124
Articles are hosted by Taylor and Francis Online.
A rod ejection accident introduces a large positive reactivity insertion in a core, causing a large power excursion. The point kinetics method is usually used to analyze this type of accident. The reactivity changes due to Doppler effect are usually obtained by static neutronics calculations with nominal (pre-ejection) core flux shapes for different fuel temperatures. The effect of locally peaked shapes due to the rod ejection is not included in the Doppler reactivity calculation. The resultant Doppler reactivity feedback is considerably underestimated, while the magnitude of the power excursion is overestimated. A simplified method that incorporates the local flux peaking effect on the Doppler feedback in a point kinetics code has been developed. The results based on this weighted Doppler feedback compare favorably with a three-dimensional kinetics analysis.