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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 Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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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Katy Huff reflects on her time in the Office of Nuclear Energy
After three years in the Department of Energy, including two as assistant secretary of the Office of Nuclear Energy, Katy Huff stepped down in May to return to the world of academia as a professor at the University of Illinois–Urbana-Champaign.
Among her many accomplishments while serving as NE-1, Huff pushed for energy security—both at home and abroad, in places like war-torn Ukraine—and for the development of additional advanced and traditional nuclear plants, the potential restart of shuttered nuclear facilities, and a better funding stream for college nuclear programs.
J. T. A. Roberts, E. Smith, N. Fuhrman, D. Cubicciotti
Nuclear Technology | Volume 35 | Number 1 | August 1977 | Pages 131-144
Technical Paper | Fuel | doi.org/10.13182/NT77-A31856
Articles are hosted by Taylor and Francis Online.
Results of three related projects undertaken to elucidate the mechanism of Zircaloy cladding fracture caused by pellet-cladding interaction (PCI) in water reactor fuel rods are described. A detailed microscopic examination of incipient i.d. cladding defects in some Maine Yankee Core I fuel rods determined that these defects and clad penetrations in related rods were caused by a PCI mechanism that was promoted by chemical species, i.e., stress corrosion cracking (SCC). A consideration of the internal fuel rod chemistry and fission product distribution indicates that one potential agent for SCC of Zircaloy cladding is iodine released from Csl deposited on the i.d. surface and another is cadmium metal. A simple analytical model of crack propagation in Zircaloy cladding based on linear elastic fracture mechanics indicates two possible rate-controlling events, depending on the value of the stress intensification KISCC. If KISCC for irradiated Zircaloy is very low, i.e., on the order of 2.2 to 3.3 MN/m3/2 (2 to 3 ksi ), crack growth is relatively easy, and hence the rate-limiting step must be the nucleation of sharp cracks in the cladding i.d. surface. However, if KISCC for irradiated Zircaloy is relatively large, i.e., ≥11 MN/m3/2 (10 ksi ), a high interfacial friction coefficient, for example, caused by fuel-clad bonding, would be required to propagate the i.d. defect.