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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Bacteria found to reduce uranium mobility in clay
Researchers at the Helmholtz-Zentrum Dresden-Rossendorf (HZDR) research laboratory in Germany have investigated a microorganism capable of transforming water-soluble hexavalent uranium [U(VI)] to the less-mobile tetravalent uranium [U(IV)]. The researchers found that the sulfate-reducing bacterium Desulfosporosinus hippei, a relative of naturally occurring microorganisms present in clay rock and bentonite, showed a relatively fast removal of uranium from clay pore water.
S. T. Perkins, E. F. Plechaty, R. J. Howerton
Nuclear Science and Engineering | Volume 90 | Number 1 | May 1985 | Pages 83-98
Technical Paper | doi.org/10.13182/NSE85-A17433
Articles are hosted by Taylor and Francis Online.
Using a Monte Carlo technique and recent double-differential measurements, a reevaluation of the 9Be(n, 2n) reaction has been completed. This evaluation is currently available for use in the most recent evaluation of the Evaluated Nuclear Data Library and will be used in ENDF/B-VI. Calculations have been carried out with these data, and implications for neutron multiplication in beryllium fusion reactor blankets are discussed.
