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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.
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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
Beyond conventional boundaries: Innovative construction technologies pave the way for advanced reactor deployment
In a bid to tackle the primary obstacle in nuclear deployment—construction costs—those in industry and government are moving away from traditional methods and embracing innovative construction technologies.
Shigeyasu Sakamoto, Eiping Quang, Glenn F. Knoll
Nuclear Science and Engineering | Volume 109 | Number 2 | October 1991 | Pages 215-220
Technical Note | doi.org/10.13182/NSE91-A28519
Articles are hosted by Taylor and Francis Online.
Neutron capture cross sections for the 197Au(n, γ)198Au reaction have been absolutely determined at neutron energies of 23 and 967 keV. These are the median energies of the two photoneutron sources, Sb-Be and Na-Be, applied in this study. Reaction rates were determined by gamma counting of the 198Au activity using a pair of cylindrical NaI(Tl) detectors. The detection efficiency of the detectors was determined using 4π beta-gamma coincidence counting techniques. The neutron emission rates of the photoneutron sources were determined by indirect comparison with the U.S. National Bureau of Standards NBS-I neutron standard source using the University of Michigan manganese bath. The values obtained for the 197Au(n,γ)198Au cross section are 617.8 ± 11.1 mb and 99.7 ± 2.8 mb at 23 and 967 keV, respectively.
