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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Report: New York state adding 1 GW of nuclear to fleet
New York Gov. Kathy Hochul has instructed the state’s public electric utility to add at least 1 gigawatt of new nuclear by building a large-scale nuclear plant or a collection of smaller modular reactors, according to the Wall Street Journal.
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.
