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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.
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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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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.
R. J. Mcwhorter, John Russell, Bertram Wolfe
Nuclear Science and Engineering | Volume 5 | Number 6 | June 1959 | Pages 382-389
Technical Paper | doi.org/10.13182/NSE59-A25614
Articles are hosted by Taylor and Francis Online.
The use of thermally black control sheets in a reactor is examined for three special cases: a finite slab reactor with a control sheet at its midplane, an infinite slab reactor containing an array of uniformly spaced control sheets, and a finite slab reactor with two control sheets placed symmetrically about the reactor centerline. The critical equation is obtained in each case and the physical significance of the solutions is examined by allowing the critical parameters to take limiting values. The conclusions reached are: (1) For τ/L2 « 1, thermally black control sheets are effectively black to all neutrons and divide the reactor into independent parts provided the distance W between control sheets, or core boundary and control sheet, is » τ3/2/L2. For W ≾τ3/2/L2, the control sheet is less effective. (2) For τ/L2 » 1 and W » τ/L, thermally black control sheets effectively divide the reactor into independent parts. For W ≾τ/L, the control sheets are less effective. (3) For τ/L2 » 1, W/L » 1, and W2/τ ∼ 1, a thermally black control sheet is relatively ineffective as compared with a sheet black to all neutrons. (4) The criteria for placing a given number of sheets most effectively in a reactor depend upon the worth of the sheets as determined from the conditions above. Thus, for sheets which are essentially black to all neutrons, the position of maximum effectiveness occurs when the reactor is cut into pieces of nearly equal size. However, for sheets of less worth, the positions of maximum effectiveness occur closer to the center of the reactor. In the limiting case, where the control effectiveness is very much smaller than the leakage from the reactor, the sheets should be placed about the reactor center, separated by about one diffusion length. It is pointed out that a very weak thermally black control element in a very large reactor may produce a large effect on the power distribution.