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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
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.
M. J. Rapp, Y. Danon, F. J. Saglime, R. M. Bahran, D. G. Williams, G. Leinweber, D. P. Barry, R. C. Block
Nuclear Science and Engineering | Volume 172 | Number 3 | November 2012 | Pages 268-277
Technical Paper | doi.org/10.13182/NSE11-55
Articles are hosted by Taylor and Francis Online.
The Gaerttner Laboratory electron linear accelerator at Rensselaer Polytechnic Institute was used in the measurement of the neutron total cross section of natural beryllium and carbon (graphite) in the energy range of 0.4 to 20 MeV. Neutron transmission measurements were made using the time-of-flight method with a 100-m flight path, fast detector response and electronics, and a narrow neutron pulse width to provide good energy resolution. A method was developed to determine the time-dependent background component associated with the transmission measurement using a combination of experimental data and Monte Carlo methods. The signal-to-background ratio combined with low counting statistics error resulted in low uncertainties and highly accurate data. The graphite measurement, showing excellent agreement with the current evaluations, provided a verification of the accuracy in the measurement and analytical methods used. The measurements of beryllium resulted in an accurate measurement of total cross section, showing some deviations with commonly used evaluations and better agreement with ENDF/B-VI.8. These results can be used for the improvement of future neutron cross-section evaluations of beryllium.