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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
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Iskender Atilla Reyhancan, Ayse Durusoy
Nuclear Science and Engineering | Volume 174 | Number 2 | June 2013 | Pages 202-207
Technical Paper | doi.org/10.13182/NSE11-96
Articles are hosted by Taylor and Francis Online.
In this study, the activation cross sections were, first, measured for the 144Sm(n,)141mNd reaction at six different neutron energies from 13.57 to 14.83 MeV. The fast neutrons were produced by using a neutron generator, through the 3H(2H,n)4He reaction. The cyclic activation technique was used as the irradiation and counting method. Induced gamma activities were measured using a high-resolution gamma-ray spectrometer equipped with a high-purity germanium detector. In the cross-section measurements, corrections were made regarding the effects of gamma-ray attenuation, dead time, fluctuation of neutron flux, and low-energy neutrons. The measured cross sections were compared with the results of model calculations (TALYS code).