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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Nobuhiro Yamamuro
Nuclear Science and Engineering | Volume 118 | Number 4 | December 1994 | Pages 249-259
Technical Paper | doi.org/10.13182/NSE94-A21495
Articles are hosted by Taylor and Francis Online.
An estimation of the production of long-lived radionuclides by neutron-induced reactions in potential fusion reactor materials is very important for the development of low-activation materials. Although some measured data of activation cross sections leading to long-lived radioactive nuclides are available, the development of a calculation capability is necessary to provide complete excitation functions of the reactions involved. Calculations are not generally effective when experimental data to determine the parameters used in the model calculation are limited. In the SINCROS-II system, the consistency of the method of calculation is respected, and the parameters used are cross-checked by the available experimental data and the systematic trend of the calculated results. Thus, the SINCROS-II is expected to predict the activation cross sections with good accuracy, even if the cross section is calculated for a radioactive target nucleus. As an example of the cross-section predictions, the activation cross-section calculations are presented up to 20 MeV for neutron-induced production of long-lived radioactive nuclides 60Co, 59Ni, 63Ni, 91Nb, 94Nb, 93Mo, 99Mo, 108mAg, 150mEu, 152Eu, 158Tb, and 186mRe.