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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Natalie Cannon is passionate about nuclear policy
Some people are born leaders, and some people make themselves leaders. Take Natalie Cannon, a fourth-year doctoral candidate in the Department of Nuclear and Radiological Engineering and Medical Physics at the Georgia Institute of Technology. She has been driven to succeed since she was a teenager in Southern California, when she was inspired by NASA’s Mars Exploration Program.
Sule Ergun, Jason G. Williams, Lawrence E. Hochreiter, Hergen Wiersema, Marcel Slootman, Marek Stempniewicz
Nuclear Technology | Volume 163 | Number 2 | August 2008 | Pages 273-284
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT08-A3987
Articles are hosted by Taylor and Francis Online.
In this study, calculations were performed to simulate a postulated large-break loss-of-coolant accident for the High Flux Reactor (HFR) cooling system using the COBRA-TF computer code. COBRA-TF has been chosen for this analysis since it has suitable and validated two-phase flow models and critical heat flux (CHF) correlations for channels having small hydraulic diameters. Calculations have been performed to determine the CHF margins for the HFR. Six types of calculations were performed to provide a range of CHF margins. All COBRA-TF calculations indicate that margin does exist to the CHF limit for the small-hydraulic-diameter highest-power HFR channel. The range of margin is 2.1 to 1.3 times the nominal power of the highest power channel, depending on the boundary conditions and CHF correlation used. The range of margin identified in the HFR analysis is consistent with the margin values used in commercial nuclear power plants.
