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Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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.
N. J. Olson, C. M. Walter, W. N. Beck
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 134-151
Technical Paper | Fuels for Pulsed Reactor / Fule | doi.org/10.13182/NT76-A31547
Articles are hosted by Taylor and Francis Online.
A reasonably large number (39) of Mark-IA driver fuel cladding failures have been obtained from run-to-failure experiments in the Experimental Breeder Reactor II over the past few years. These experiments were designed to yield failure information for various design variables and to qualify the fuel element design to a burnup limit such that the risk of an end-of-design-life failure was exceedingly small for normal operating conditions. None of the design variables or operating conditions tested had a significant effect on the failure statistics. The failure mode fit the Weibull statistical failure model and is characterized by a burnup threshold of 3.0 at.% maximum burnup (BUmax), which must be surpassed prior to failure. The cumulative failure probability [F(BUmax)] for peak linear pin powers between 6.4 and 8.0 kW/ft and maximum cladding temperatures from 890 to 1050°F can be expressed as Once 3.0 at.% BUmax is achieved, it was also found experimentally that the failure rate could be decreased over a small burnup interval by lowering the power ratings. The Type 304L stainless-steel cladding in-reactor fracture mode for the Mark-IA driver fuel elements is characterized by inter granular crack propagation that originates at the outside surface of the cladding. This mode of failure appears to be assisted by stress corrosion and potentially deleterious grain boundary precipitation. Although the fracture mode is brittle in nature, uniform mechanical hoop strains >1% are achieved prior to failure.