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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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.
Stefan Schmid, Rudi Kulenovic, Eckart Laurien (University of Stuttgart)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 406-413
For the investigations of leakage flow rates with reduced stagnation pressure (maximum 1.0 MPa) and stagnation temperature (maximum 170 °C) compared to real plant conditions, the Leakage Flow (LF) test rig is used. The design of the test rig enables experimental measurements of leakage flow rates through cracks with different shapes, sizes and wall thicknesses.
In the paper, experimental results of leakage flow measurements for one artificial through-wall crack geometry with a rectangular shape are presented. The fluid conditions of the investigations vary in the pressure range from 0.2 MPa to 1.0 MPa with a maximum temperature of 170 °C. The experimental values in the single-phase regime up to 90 °C are used to calculate the overall loss coefficient respectively the friction factor and are compared to theoretical models. The results at elevated temperature from 100 °C to 170 °C are discussed considering the subcooling of the fluid and compared to theoretical values calculated by the modified Bernoulli equation.
