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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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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.
J. W. Kutcher, M. E. Wyman
Nuclear Science and Engineering | Volume 26 | Number 4 | December 1966 | Pages 435-446
Technical Paper | doi.org/10.13182/NSE66-A18414
Articles are hosted by Taylor and Francis Online.
An absolute experimental measurement has been made of the time dependence of the beta energy spectrum from fission fragments, specifically beta particles of energies greater than 0.75 MeV produced in the thermal neutron fission of uranium-235. This measurement has been made for four cases: the initiation of a constant fission rate in a cold uranium foil; shutdown after 1- and 3-h runs at a steady fission rate; and an instantaneous burst of fissions produced by a reactor pulse. The fission source was a foil coated with approximately 38 mg of 235U and placed in a thermal neutron beam from a reactor. The fission rate was measured with an ionization chamber. The beta energy spectrum was measured with a plastic scintillator, with absolute counting being determined by the known solid angle between source and detector. Background counts have been reduced to less than 10% in all cases. The total uncertainty in the analyzed data was less than 5% for the steady power runs and less than 8% for the reactor pulsing runs. The experimental results are in substantial agreement with those predicted by theory.