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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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ANS sends waste policy recommendations to DOE
The American Nuclear Society has sent a letter to Energy Secretary Chris Wright with a set of recommendations for the Department of Energy to take to establish an effective national program to manage the storage, reprocessing, and final disposal of U.S. commercial used nuclear fuel.
Fan-Bill Cheung, K. H. Haddad, Y. C. Liu
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 243-264
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT99-A2972
Articles are hosted by Taylor and Francis Online.
A subscale boundary-layer boiling (SBLB) test facility was developed with the aid of a scaling analysis to simulate the phenomena of pool boiling and critical heat flux (CHF) on the external bottom surface of a heated hemispheric vessel. Saturated and subcooled boiling experiments were performed in the SBLB facility to measure the spatial variation of the CHF and observe the underlying mechanisms, including the vapor dynamics and the resulting buoyancy-driven two-phase boundary-layer flow along the downward-facing hemispheric heating surface. Based on the experimental evidence and an advanced hydrodynamic CHF model, a scaling law was established for estimating the local CHF on the vessel outer surface. The scaling law, which compared favorably with the available CHF data obtained for various vessel sizes, was shown to be useful in predicting the local CHF limits on large commercial-size vessels. Additional work, however, is needed to determine the effect of thermal insulation.