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
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
Germany’s Unterweser completes removal of steam generators
All four steam generators at Germany’s Unterweser nuclear power plant have been removed from the reactor building, plant owner PreussenElektra has announced. The single-unit pressurized water reactor was shut down in 2011 as part of Germany’s decision to phase out nuclear energy. Decommissioning and dismantlement of the reactor began soon after PreussenElektra was granted a permit for the work in February 2018.
Thomas J. Marciniak
Nuclear Technology | Volume 8 | Number 5 | May 1970 | Pages 401-416
Paper | Reactor | doi.org/10.13182/NT70-A28685
Articles are hosted by Taylor and Francis Online.
A simple, stable, time-optimal digital control program has been developed with general application to zero- or low-power nuclear reactors for power-level changes, especially power increases. The program is required to increase the power level while maintaining a minimum allowed period, and to reach the demand power with little or no overshoot. A switching criterion was derived using a discrete version of the Pontryagin Maximum Principle. The switch point was found to be dependent upon the minimum allowed period and the maximum reactivity removal rate of the controlled regulating rod. The control program developed was applied to digital simulation of three reactor models and was adapted for use on the Argonne Thermal Source Reactor (ATSR) for power-level changes. The maximum overshoot experienced was ∼1% for various minimum allowed reactor periods and reactivity removal rates.