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!
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Nuclear Science and Engineering
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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.
Gary Chung, Nathan Siu, George Apostolakis
Nuclear Technology | Volume 69 | Number 1 | April 1985 | Pages 14-26
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33591
Articles are hosted by Taylor and Francis Online.
An integral part of a probabilistic analysis of the risk from fires in nuclear power plants is the estimation of the fire severity in compartments. The computer code COMPBRN implements physical models that predict the thermal hazards, e.g., temperatures and heat fluxes, during a compartment fire, as well as the failure time of objects, such as cables, that are subjected to these hazards. The COMPBRN II code is an improved version of COMPBRN; it includes radiative and convective heat losses from fuel elements and distinguishes between damage and ignition thresholds. Comparison with experimental results shows that the modifications generally lead to improved predictions.