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Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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
Cattle industry poised to lead the way to a cooler Earth
In discussing how to counter global warming, it’s pretty easy to argue that nuclear should be the major electricity source and heat producer to replace fossil fuels. At 6 grams per kilowatt-hour, it has the lowest carbon emissions of any energy source, according to the United Nations, and is objectively the safest form of energy for humans and the environment alike, again from a recent UN report.
Yuichi Ogawa, Nobuyuki Inoue, Kunihiko Okano
Fusion Science and Technology | Volume 26 | Number 2 | September 1994 | Pages 168-178
Technical Paper | Fusion Reactor | doi.org/10.13182/FST94-A30340
Articles are hosted by Taylor and Francis Online.
As an intense 14-MeV neutron source, a steady-state subignited tokamak plasma is proposed, where a 60-MW neutral beam is injected to sustain a subignited plasma and to drive a plasma current for steady-state operation. Plasma and device parameters are self-consistently designed, taking into account physical (confinement characteristics, beta limit, current drive efficiency, and so on) and engineering (maximum magnetic field strength, blanket/shield thickness, and others) constraints. The result of a comparison between plasmas with A = 2.8 and A = 4 indicates that a large aspect-ratio device is preferable as a neutron source. A surface-averaged 14-MeV neutron flux of ∼0.6 MW/m2 is achievable with R = 4 to 5 m, A = 4, and Bmax = 10 T and is not so sensitive to the major radius. When the maximum magnetic field strength of toroidal field coils is raised to 13 T, a neutron flux more than 1 MW/m2 is available with a device with R = 4 m. If the plasma performance is advanced and plasmas with an L-mode enhancement factor fL of ∼3 and a Troyon coefficient in beta limit g of ∼5 are attainable, a neutron flux of ∼1.6 MW/m2 is achievable even with a device with R = 4 m and Bmax = 10 T. These devices seem to be very attractive not only as a neutron source but also as a supplementary device of an ignition-oriented International Thermonuclear Experimental Reactor (ITER) device.
