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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Latest News
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
T. C. Chawla
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 397-402
Technical Paper | doi.org/10.13182/NSE72-A22507
Articles are hosted by Taylor and Francis Online.
Through the use of potential flow theory, an expression for two-dimensional axisymmetric pressure distribution in an “infinite” plenum for a coolant-expulsion process in a single-subassembly accident is obtained. An expression for the temporal distribution of the corresponding spatially averaged pressure at the exit of a fuel subassembly is also obtained. The illustrative example considered indicates that the use of a fixed-pressure boundary condition instead of a time-dependent-pressure boundary condition at the exit (or at the inlet) of a subassembly is not valid for very rapid transients, such as due to molten fuel-coolant interaction or to rapid release of fission gas from simultaneous or near-simultaneous breach of several pins near the top of the core region. Furthermore, the results of sample calculations presented for an FFTF subassembly indicate the possibility that, for a sufficiently rapid transient, the transient pressure in the exit region of the subassembly can fall to the saturation pressure of the sodium and result in local boiling during the expulsion in the exit region of the subassembly. The expression developed here for the transient, spatially averaged pressure distribution in the plenum at the exit of a subassembly could be coupled with the one-dimensional type of analysis of the expulsion process in the fuel subassembly.