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The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—April through June
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from April through May 2024.
Stay tuned for the top stories from the rest of the past year.
Askar A. Gubaidullin, Bal Raj Sehgal
Nuclear Technology | Volume 138 | Number 1 | April 2002 | Pages 90-92
Technical Note | Thermal Hydraulics | doi.org/10.13182/NT02-A3280
Articles are hosted by Taylor and Francis Online.
A semiempirical correlation for an estimate of crust thickness in a molten pool is presented and validated against published experimental data. The proposed correlation between the dimensionless crust thickness and the Biot and the Prandtl numbers has been developed as [overbar]* = 14.49BiPr -0.074. A scaling methodology is discussed to analyze the thermal resistance of the crust. The results are of interest for the corium melt coolability in a postulated severe accident scenario in a light water reactor.