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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.
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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
Argonne researching “climate-ready” nuclear plant design
Scientists at Argonne National Laboratory have partnered with Washington state–based Energy Northwest to look at alternative ways to cool nuclear reactors as climate change impacts relied-upon water sources.
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).