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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
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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.
Alain Kavenoky
Nuclear Science and Engineering | Volume 65 | Number 2 | February 1978 | Pages 209-225
Technical Paper | doi.org/10.13182/NSE78-A27152
Articles are hosted by Taylor and Francis Online.
The CN method of solving the transport equation has been developed at Saclay during the past few years. This method is based on a lemma proved by Placzek; an integral equation is provided for the angular flux at the boundary of the various media, and its kernel is the infinite medium Green's function. Four plane geometry problems are solved in one-velocity theory, with a linearly anisotropic scattering kernel: the albedo for the Milne problem, the extrapolation length for the same problem, albedo and transmission factor for slabs, and the critical thickness for slab reactors. Numerical results are obtained and compared with data computed by reference methods.