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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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
Nominations open for CNTA awards
Citizens for Nuclear Technology Awareness is accepting nominations for its Fred C. Davison Distinguished Scientist Award and its Nuclear Service Award. Nominations for both awards must be submitted by August 1.
The awards will be presented this fall as part of the CNTA’s annual Edward Teller Lecture event.
M. Yiğit, A. Kara, A. Yilmaz
Fusion Science and Technology | Volume 80 | Number 2 | February 2024 | Pages 156-165
Research Article | doi.org/10.1080/15361055.2023.2211190
Articles are hosted by Taylor and Francis Online.
Niobium is an important alloying material in nuclear reactors because of its enormous strength, low density, low neutron absorption, and high melting point. This study is structured on nuclear data calculations that are based on a Monte Carlo simulation approach. The GEANT4, SRIM, and TALYS codes were used to create a comprehensive simulation of 3.6-MeV alphas and 14.7-MeV protons on a target. We present calculation results on nuclear parameters as ion energy losses, displacements, vacancies, projected ranges, and cross sections. A comparison between the GEANT4 and SRIM codes was made for the projected ranges and ion energy losses. Besides, the calculations of cross sections in the TALYS code were carried out using level densities on the Skyrme energy density functional and the Fermi gas model.