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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.
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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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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.
Arthur W. Dalton
Fusion Science and Technology | Volume 12 | Number 3 | November 1987 | Pages 409-415
Technical Paper | Tritium System | doi.org/10.13182/FST87-A25072
Articles are hosted by Taylor and Francis Online.
A cylinder of natural lithium carbonate, supported on a slab of graphite, was irradiated from above by a low-intensity source of 14-MeV neutrons and the tritium produced within it subsequently determined from measurements of beta activity. Results obtained for small lithium carbonate detectors highly enriched in 6Li (96%) or 7Li (99.9%) at six positions along the cylinder axis were compared with predictions based on three-dimensional Monte Carlo calculations and multi-group cross-section data. The experimental accuracy was sufficient to detect deviations from theory > 7% with a 95% level of confidence. On this basis, good agreement with theoretical predictions was obtained for the 7Li results. For the 6Li data, however, significant differences were observed in the lower half of the assembly. A detailed analysis indicated that these deviations could not be explained in terms of conceivable environmental perturbations of the neutron flux and may arise as a consequence of inadequate representation of anisotropic neutron scattering.