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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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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.
Martin Lochter, Reinhard Uhlemann, Jochen Linke
Fusion Science and Technology | Volume 19 | Number 4 | July 1991 | Pages 2101-2111
Technical Paper | Carbon Material Special | doi.org/10.13182/FST91-A29346
Articles are hosted by Taylor and Francis Online.
The high heat flux ion beam test facility at Forschungszentrum Jülich can produce peak power densities of 0.14 to 12 kW/cm2 for pulse lengths of 10 ms to 15 s. Longer pulses up to steady-state operation are possible with reduced power. The total ion beam power can be varied between 70 kW and 6 MW at particle energies of 10 to 60 keV. The particles are hydrogen and helium. The beam illuminates a 1300-cm2 area, which allows a large area for materials tests. The rise time of the beam pulses can be adjusted between 2 and 200 ms, and the pulse repetition rate is between 1 and 5 min. The test facility is equipped with a sample manipulator with a vacuum lock that allows a sample size of 15 × 10 cm with active or passive cooling. The extensive diagnostic system of the test stand, originally designed for developing and conditioning the neutral beam ion sources for the Tokamak Experiment for Technology Oriented Research (TEXTOR), and the diagnostic system of the sample manipulator are described. The results of a materials test series performed for the development of wall materials for the Next European Torus/International Thermonuclear Experimental Reactor (NET/ITER) are shown. Possible upgrades of the facility are also discussed.