ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Mitchel E. Cunningham, Courtney R. Hann, Anthony R. Olsen
Nuclear Technology | Volume 47 | Number 3 | March 1980 | Pages 457-467
Technical Paper | Fuel | doi.org/10.13182/NT80-A32400
Articles are hosted by Taylor and Francis Online.
With the increasing sophistication and use of computer codes in the nuclear industry, there is a growing awareness of the need to identify and quantify the uncertainties of these codes. Work is now being performed at Battelle-Pacific Northwest Laboratories to study the uncertainties in steady-state stored energy calculations by using linear propagation of uncertainties. This method predicts the uncertainty of variables by propagating input variances through models. Comparison of Monte Carlo analysis to linear propagation shows good agreement and verifies the adequacy of linear propagation. Linear power, radial gap width, fuel thermal conductivity, flux depression, and fuel heat capacity are all shown to be parameters of major importance when calculating both stored energy and its uncertainty. The uncertainty for stored energy at beginning-of-life is ∼17% (99% confidence level) and rises to a maximum of 37% during a simulated two-cycle power history.