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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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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.
L. Srinivasan
Nuclear Science and Engineering | Volume 79 | Number 2 | October 1981 | Pages 228-233
Technical Note | doi.org/10.13182/NSE81-A27411
Articles are hosted by Taylor and Francis Online.
A new numerical approach is attempted to solve the three-dimensional multigroup diffusion equation in rectangular geometry using the principles of variational calculus. The method essentially consists in separating the variables along the x, y, and z directions so that the neutron flux can be synthesized into three components to get an approximate solution. This solution can be used as a starting trial function for flux in the next step, where the variables are treated nonseparable in order to get a better solution. The effect of separation of variables is also studied. Detailed calculations are performed for a benchmark problem and the results are presented along with published values that are calculated using finite difference codes.