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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
L. R. Greenwood, R. R. Heinrich, R. J. Kennerley, R. Medrzychowski+
Nuclear Technology | Volume 41 | Number 1 | November 1978 | Pages 109-128
Technical Paper | Technique | doi.org/10.13182/NT78-A32137
Articles are hosted by Taylor and Francis Online.
Integral tests have been made for 27 nuclear activation cross sections required for neutron dosimetry at accelerator-based irradiation facilities. Thirteen materials were irradiated in a well-defined geometry using neutrons produced by stopping 14- to 16-MeV deuterons in a thick beryllium target. The neutron spectrum was measured by time-of-flight spectrometry. Comparison of the activation integrals with the differential neutron spectrum provided an assessment of the nuclear data. A small fission chamber was used to monitor the irradiation, map flux gradients, and study attenuation and scattering effects. Comparison of the fission rates to fission product activations in the foil materials was also used to measure cumulative fission yields for 235U and 238U.