ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
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.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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Latest News
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
R. E. Williford
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 208-220
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT84-A33511
Articles are hosted by Taylor and Francis Online.
Uranium dioxide fuel pellets crack during the irradiation of light water reactor fuel rods, enhancing fuel/cladding mechanical interactions and creating asymmetric fuel rod internal geometries that result in nonlinear mechanical behavior. A formulation analogous to a constitutive equation is developed to describe the nonlinear load-displacement behavior of cracked fuel. Cladding elastic ridge heights are computed via a simple shell analysis during the iterative solution of the cracked-fuel constitutive equation. Results indicate that maximum cladding ridge heights do not necessarily occur at the smallest initial fuel/cladding gap size, and that the mode of cladding deformation depends on gap size and rod power. The method can be extended to more detailed cladding deformation analyses, and is useful for estimating the cladding stresses needed for fuel rod failure analyses.