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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
A look inside NIST’s work to optimize cancer treatment and radiation dosimetry
In an article just published by the Taking Measure blog of the National Institute of Standards and Technology, Stephen Russek—who leads the Imaging Physics Project in the Magnetic Imaging Group at NIST and codirects the MRI Biomarker Measurement Service—describes his team’s work using phantom stand-ins for human tissue.
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.