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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Nuclear Science and Engineering
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Nuclear Technology
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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.
Soon Sam Kim, Jerry L. Judd
Nuclear Technology | Volume 110 | Number 1 | April 1995 | Pages 71-85
Fission Reactor | Burnup Credit | doi.org/10.13182/NT95-A35097
Articles are hosted by Taylor and Francis Online.
Fission rate monitor measurements and startup testing data recorded during operation of the Advanced Test Reactor (ATR) have been used to validate a three-dimensional PDQ full-core model developed for the physics analysis to support an updated final safety analysis report. The three-dimensional analysis utilizes the flux synthesis technique as well as the explicit method in solving for the spatial flux distribution in the core. Measured data used for comparison are specific powers from a string offission rate monitors, located in water channels of individual fuel elements, as well as the lobe and fuel element powers. Good agreement was observed in the specific power comparison. For the overall pointwise data, the mean errors were within 1.6% with a standard deviation of ±9%. An excellent agreement was observed for the fuel element power except for a few fuel positions in the corner lobes. Measured ATR startup testing data are also compared with the PDQ calculated values. The PDQ calculated parameters were conservative with respect to measured data. The validation study provided valuable data for assessment of the three-dimensional analytical model and techniques to be employed in the ATR physics analysis. The study also indicated that the PDQ three-dimensional flux synthesis solution technique is an economical and reasonably accurate method for determining global and local three-dimensional power distributions in the core.
