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Conference 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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
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.
