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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Nuclear Science and Engineering
March 2025
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Fusion Science and Technology
February 2025
Latest News
WEST claims latest plasma confinement record
The French magnetic confinement fusion tokamak known as WEST maintained a plasma in February for more than 22 minutes—1,337 seconds, to be precise—and “smashed” the previous record plasma duration for a tokamak with a 25 percent improvement, according to the CEA, which operates the machine. The previous 1,006-second record was set by China’s EAST just a few weeks prior. Records are made to be broken, but this rapid progress illustrates a collective, global increase in plasma confinement expertise, aided by tungsten in key components.
Lakshmi Rangaswamy, L. S. Kothari, Feroz Ahmed
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 261-270
Technical Paper | doi.org/10.13182/NSE76-A26824
Articles are hosted by Taylor and Francis Online.
For one-speed neutrons, we have investigated the effect of anisotropy in the scattering kernel on their angular distribution at various space points inside slabs of different thicknesses. This has been done by solving the one-speed space-angle-dependent neutron transport equation for a pulsed source, by numerically iterating over the space and angle variables. We find that the fundamental decay constant decreases with increasing anisotropy, the effect being more in thicker slabs. The effect of scattering anisotropy on the angular flux inside slabs, as well as on leakage flux, has been reported. For a specific scattering kernel, the variation of angular flux with thickness of the slab is also discussed. Some of these results have been compared with those based on P1 and P3 approximations.