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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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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.
William D. Rhodes, Raymond V. Furstenau, Howard A. Larson
Nuclear Technology | Volume 130 | Number 2 | May 2000 | Pages 145-158
Technical Paper | Reactor Safety | doi.org/10.13182/NT00-A3083
Articles are hosted by Taylor and Francis Online.
The generic technique of applying pseudorandom, discrete-level, periodic reactivity perturbation signals to measure the reactivity-to-power frequency response function was extended to the liquid-metal reactor, Experimental Breeder Reactor-II (EBR-II). This technique was developed in the late 1960s and applied in several reactor designs with extensive testing performed at the Molten Salt Reactor Experiment. Signals employed at EBR-II included the pseudorandom binary sequence, quadratic residue binary sequence, pseudorandom ternary sequence, and multifrequency binary sequence. For all the signals employed, the resultant reactor power perturbation was small enough to be acceptable for normal at-power operation and in-place irradiation experiments. The frequency response results are compared with the zero-power frequency response function, yielding a quantitative measure of the EBR-II reactivity feedback effects. The frequency response function results are in good agreement with rod-oscillator data and model predictions. The multifrequency binary sequence concentrated 64% of the total signal power into the four feedback frequencies associated with the predominant feedback time constants. The input signal quality, characterized by the autocorrelation function and power spectra, validated the automatic control rod drive system design and operation as an effective tool for frequency response determination over the range of frequencies where important system dynamic effects occur.