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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
June 2025
Nuclear Technology
Fusion Science and Technology
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.
P. B. Parks, N. P. Baumann, R. L. Currie, and C. E. Jewell
Nuclear Science and Engineering | Volume 59 | Number 4 | April 1976 | Pages 298-310
Technical Paper | doi.org/10.13182/NSE76-A26832
Articles are hosted by Taylor and Francis Online.
Experimental data that test the validity of a numerical solution of the transient few-group neutron diffusion and delayed precursor equations in two-dimensional hexagonal geometry are presented. The experiments involve free fall insertion of 235U-bearing rods into an off-center location of a large critical, heavy-water-moderated lattice. The resulting transient flux tilts are strongly influenced by delayed neutron holdback. The calculated flux tilts agree with the measured flux tilts within the small uncertainty of the measurements. The data and input to the calculations are presented in sufficient detail to allow other methods of solution to be tested.
