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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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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
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Y. Keheyan et al.
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 230-233
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A919
Articles are hosted by Taylor and Francis Online.
The sorptive behaviour of radioactive waste on Armenian zeolites, natural, irradiated, chemically treated and heated at high temperatures was studied and their capacity for the separation and enrichment of radionuclides was evaluated.The influence of temperature, acidity, basicity, specific activity, electron and gamma irradiation on sorption have been studied. The chemical analysis of exchanged samples was carried out and the cation exchange capacity was determined. Absorption properties of mono-cationic forms of different clinoptilolite samples were studied depending on type of guest cation and contact time.By means of model experiments the laboratory plant for absorption of metal cations from solutions in dynamic regime was designed and developed. This plant was used for experiments of radioactive waste removal from the Armenian nuclear reactor.