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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
Release of Fukushima’s treated water going as planned, IAEA says
An International Atomic Energy Agency task force has confirmed that the discharge of treated water from Japan's Fukushima Daiichi nuclear power plant is progressing in accordance with the plan approved by Japan’s Nuclear Regulation Authority.
Hoai Nam Tran, Yasuyoshi Kato
Nuclear Science and Engineering | Volume 159 | Number 1 | May 2008 | Pages 83-93
Technical Paper | doi.org/10.13182/NSE159-83
Articles are hosted by Taylor and Francis Online.
A new 237Np burning strategy in a supercritical CO2-cooled fast reactor core has been proposed: consuming 237Np as fuel and burnable poison to attain zero burnup reactivity loss. Addition of 237Np at content of 6.5 wt% in fuel engenders nearly zero burnup reactivity loss of 0.02% k/k during 10 yr. The burning rate of 237Np in the core is ~69 kg/yr, which is equivalent to the quantity produced in a year from about 20 light water reactors of equivalent electrical output. The zero burnup reactivity loss enables reduction of the control rod number to half that of a typical sodium-cooled mixed-oxide fuel MONJU core without added 237Np and no need for rod operation with fuel burning to compensate for the burnup reactivity loss. Void reactivity is 0.72% k/kk', which is three-fourths that of a typical Na-cooled core, although 237Np is added and the active core length is elongated to 1.2 m. The power density is reduced to ~20% of that in a Na-cooled core. The hot-spot temperature of cladding is below its maximum permissible temperature of 700°C.