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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
Pierre Benoist
Nuclear Science and Engineering | Volume 77 | Number 1 | January 1981 | Pages 1-12
Technical Paper | doi.org/10.13182/NSE81-A21334
Articles are hosted by Taylor and Francis Online.
In an earlier work, the author presented a theory of the diffusion coefficient in a reactor lattice, leading to expressions valid in full generality. However, for practical purposes it was necessary to admit simplifying assumptions. But now, with the help of modern computers, weaker approximations appear possible. Assuming only two hypotheses, (a) zero-order approximation in , and (b) cylindricalization of the cell, a diffusion coefficient calculation can be transformed into a one-dimensional problem, the solution of which is practically as simple as the calculation of the classical fine structure. The difficulty concerning the reflection of neutrons from the boundary is overcome here; moreover, handling of angular fluxes is avoided, without any approximation. Formulas for the calculation of the diffusion coefficients in the framework of integral transport theory are presented.