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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Nuclear Science and Engineering
July 2025
Nuclear Technology
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Latest News
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.
Kin Wah Wong, Vijay K. Dhir, W. E. Kastenberg
Nuclear Technology | Volume 39 | Number 2 | July 1978 | Pages 121-137
Technical Paper | Reactor | doi.org/10.13182/NT78-A32073
Articles are hosted by Taylor and Francis Online.
A mechanistic model that describes events leading to in-channel fuel plateout following fuel pin failure under slow transient overpower accident conditions has been proposed. The thermal and hydraulic effects of the plated out fuel have also been investigated. Results based on this model indicate that during a slow transient overpower accident (2.4 cent/s), in-core fuel freezing and channel plugging can be expected to occur. The extent of fuel freezing and channel plugging is sensitive to fuel particle size, the amount of fuel injected, and the amount of fission gas injected into the coolant channel The results are also compared with experimental data from the TREAT H-4 experiment.
