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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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!
Latest Magazine Issues
Jul 2024
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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Henry H. Wong, Ertugrul Alp, W. R. Clendening,+ M. Tayal,+, Lloyd R. Jones
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 203-212
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26282
Articles are hosted by Taylor and Francis Online.
The ELESTRES code is a computer code designed to model the behavior of the Canada deu-terium-uranium nuclear fuel elements under normal operating conditions. It models a single element by accounting for the radial and axial variations in stresses and displacements. The constituent models are physically (rather than empirically) based and include such phenomena as fuel-to-sheath heat transfer; temperature and porosity dependence of fuel thermal conductivity; burnup-dependent neutron flux depression; burnup- and microstructure-dependent fission product gas release; and stress-, dose-, and temperature-dependent constitutive equations for the sheath. The finite element model for the pellet deformation includes thermal, elastic, plastic, and creep strains as well as swelling and densification; pellet cracking; and rapid drop of UO2 yield strength with temperature. It uses the variable stiffness method for plasticity and creep calculations and combines it with a modified Runga-Kutta integration scheme for rapid convergence and accuracy. Comparison of code predictions with experimental data indicates good agreement for the calculation of gas release and pellet-midplane and pellet-end sheath strains.