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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
M. T. A-Moneim
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 464-475
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32582
Articles are hosted by Taylor and Francis Online.
A three-dimensional pipe element, with eight degrees-of-freedom per node, is developed to consider the stresses arising from the pipe internal pressurization as well as the stresses arising from the three-dimensional flexural motion of the piping system. The scheme is developed for coupling with piping hydrodynamics so that a realistic safety assessment of a reactor’s piping system can be achieved. Using rigid co-rotational coordinates, the finite element formulation is suited for large displacement but small strain situations. Both geometric and material nonlinearities are considered. The equations of motion are integrated by an explicit procedure. Sample results are presented to demonstrate the performance of the element in its individual as well as coupled modes of deformation.