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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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
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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.
L. R. Fawcett, Jr.
Nuclear Science and Engineering | Volume 113 | Number 2 | February 1993 | Pages 173-183
Technical Paper | doi.org/10.13182/NSE93-A24006
Articles are hosted by Taylor and Francis Online.
Tritium production in a sphere of 6LiD with an Oralloy core irradiated by a central source of 14-MeV neutrons has been calculated and compared with experimental measurements. The experimental assembly consisted of an Oralloy sphere surrounded by three solid 6LiD concentric shells with ampoules of 6LiH and 7LiH located in several positions throughout the assembly. The Los Alamos Monte Carlo Neutron Photon Transport Code (MCNP) was used to calculate neutron transport throughout the system and tritium production in the ampoules. The MCNP calculations were three-dimensional and employed ENDF/B- V cross sections. The overall experimentally observed-to-calculated ratios of tritium production were 0.996 (±2.5%) in 6LiH ampoules and 0.903 (±5.2%) in 7LiH ampoules. Tritium production in a sphere of 6LiD without an Oralloy core has been reanalyzed using ENDF/B-V cross sections, and the results are reported. The reanalyzed observed-to-calculated values of tritium production were 1.053 (±2.1%) in 6LiH and 0.999 (±2.1%) in 7LiH. The foregoing several uncertainties do not include an estimated <6% systematic error in the observed values.