ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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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.
David A. Mandell
Nuclear Technology | Volume 52 | Number 3 | March 1981 | Pages 383-392
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32712
Articles are hosted by Taylor and Francis Online.
To calculate the radiative heat transfer between fuel bundle surfaces and from the surfaces to the vapor and droplets in a boiling water reactor, it is necessary to calculate the geometrical fuel factors. These view factors, which are the fraction of energy leaving one surface that reaches a second surface when no fluid exists, must be calculated for every pair of fuel rods, from every rod to every channel segment, and from one channel segment to a second channel segment. The crossed-string method was used to obtain algebraic equations for the view factors between rods of the same diameter, from rods-to-channel segments, and from one channel segment to a second channel segment. These equations can be easily incorporated into computer codes. Conservation of energy was used to verify the view factor equations.