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
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
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.
B.D. Boyer, J. W. Hartzell,† S. Lider, G. E. Robinson, A. J. Baratta, A. J. Roscioli
Nuclear Technology | Volume 103 | Number 2 | August 1993 | Pages 206-219
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT93-A34844
Articles are hosted by Taylor and Francis Online.
The effects of condensation steam quenching in modeling two-phase flow phenomena during a nuclear reactor transient are studied. The RETRAN-02-MOD002 code, with three field equations and a nonequilibrium pressurizer model option, and the TRAC-BF1 code, with six field equations, predicted plant response to a boiling water reactor plant test of a main steam isolation valve closure without safety relief valve opening. The basic RETRAN-02-MOD002 field equations cannot model steam quenching by condensation. However, by activating the nonequilibrium modeling option of the basic RETRAN-02-MOD002 code and by inputting appropriate interfacial heat transfer coefficients, steam quenching by condensation was calculated. This approach gave results closer to those obtained with the test data. The two TRAC-BFI models used two different methods of tracking water level to approximate the condensation quenching effect. Because the void fraction changes too gradually, the calculation without the TRAC two-phase water level tracking option overquenched the pressure and filled the vessel with too much water. However, because the void fraction changes virtually instantaneously (as it does in the plant), the TRAC two-phase water level tracking option’s prediction of the quenching of the pressure was 50% closer to the data than was any RETRAN-02-MOD002 calculation, and it followed the water level almost as well as the RETRAN-02-MOD002 best-estimate case. Both codes overpredicted the pressure spike.
