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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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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
First astatine-labeled compound shipped in the U.S.
The Department of Energy’s National Isotope Development Center (NIDC) on March 31 announced the successful long-distance shipment in the United States of a biologically active compound labeled with the medical radioisotope astatine-211 (At-211). Because previous shipments have included only the “bare” isotope, the NIDC has described the development as “unleashing medical innovation.”
Mohamed A. E. Abdel-Rahman, Mohamed A. E. M. Ali, Sayed A. El-Mongy
Nuclear Technology | Volume 206 | Number 5 | May 2020 | Pages 766-778
Technical Paper | doi.org/10.1080/00295450.2019.1697173
Articles are hosted by Taylor and Francis Online.
This research work aims to investigate the penetrability of electromagnetic gamma rays and fast neutrons and the static performance of newly developed concrete. To achieve this target, seven concrete samples of three different coarse aggregates—dolomite, hematite, iron slag (with five different densities, i.e., 3.23, 3.34, 3.42, 3.10, and 3.03 g/cm3, respectively) with dolomite used as the control specimen—have been synthesized and investigated to determine their mechanical and radiation penetration properties. The mechanical performances were evaluated in terms of tensile and compressive strength, slump measurements, and water permeability. X-ray fluorescence was carried out to determine the chemical composition of the synthesized materials. The materials’ mineralogical constituents were also determined by X-ray diffraction analysis. The radiation transmissioxn characteristics were also checked by using gamma-ray collimated beams of both 60Co and 238Pu/Be neutron source. A stilbene crystal organic scintillator coupled with a fast n/γ pulse shape discriminating spectrometer as well as an NaI(Tl) scintillator gamma spectrometer were used to measure the radiation penetrated through the concrete samples. The fast neutron macroscopic cross section and total gamma-ray linear attenuation were derived for the developed mixes. The results obtained show that iron slag concrete of density 3.10 ton/m3 has superior characteristics against the transmission of gamma rays and fast neutrons and distinguished resistance withstanding mechanical pressure and loads.