ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
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.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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August 2024
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
C. Lepscky, P. L. Rotoloni, G. Testa, G. Trezza
Nuclear Technology | Volume 9 | Number 4 | October 1970 | Pages 536-549
Fuel | doi.org/10.13182/NT70-A28764
Articles are hosted by Taylor and Francis Online.
Uranium-plutonium mixed oxide sol-gel fuel is attracting interest as a promising nuclear material for fast reactor fuel subassemblies. However, this material, if employed for commercial fuel production particularly in the fast reactor area, must be extensively tested both inpile and out-of-pile. For this purpose, some irradiation tests have been carried out by CNEN in the RS-1 swimming pool reactor in Italy and in the Halden BHWR in Norway under the Plutonium Program and the Fast Reactor Program. The results obtained show: in-reactor homogenization of plutonium in the UO2 matrix, increase of the integral of conductivity after in-pile sintering process has taken place, and cladding attack caused by impurities originally present in the fuel particles.