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.
Explore membership for yourself or for your organization.
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!
Latest Magazine Issues
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
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.
J. Reimann, M. Khan
Nuclear Science and Engineering | Volume 88 | Number 3 | November 1984 | Pages 297-310
Technical Paper | doi.org/10.13182/NSE84-A18584
Articles are hosted by Taylor and Francis Online.
A small break in a horizontal coolant pipe is investigated. This flow geometry and accident scenario are of interest in nuclear reactor safety research. For the calculation of break mass flow rate, appropriate experiments are needed, especially for the case where stratified two-phase flow exists in the main pipe. The flow geometry corresponds to a “T”-junction with a large-diameter ratio of the horizontal pipe, D, to the branch pipe, d. In the present experiments, D was 206 mm, the downward-oriented branch diameters were 6, 12, and 30 mm. Air/water experiments were performed at a system pressure of 0.5 MPa and various differential pressures. The flow field could be observed visually. Photographs reveal both vortex-induced and vortex-free gas pull-through the break and the corresponding correlations for the onset of gas pull-through. The mass flow rate and quality distribution as a function of a dimensionless interface level are presented.