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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
Michael L. Corradini, Warren M. Rohsenow, Neil E. Todreas
Nuclear Science and Engineering | Volume 73 | Number 3 | March 1980 | Pages 242-258
Technical Paper | doi.org/10.13182/NSE80-A19849
Articles are hosted by Taylor and Francis Online.
A major portion of the safety analysis effort for the liquid-metal fast breeder reactor is involved in assessing the consequences of a hypothetical core disruptive accident. A postulated loss-of-flow transient without scram may produce a two-phase fuel source at high pressures. The heat transfer process between the fuel and the sodium coolant as it is ejected into the upper plenum is described in this study. One mechanism that can cause the coolant to become entrained in the two-phase fuel is Taylor instabilities. The characteristic size of the entrained coolant droplets is considered to be equal to the critical wavelength of a Taylor instability. Analysis of full-scale reactor conditions indicates that the dominant heat transfer mechanism is radiation. Also, if noncondensible gases are absent, fuel vapor condensation on the sodium coolant droplets is controlled by mass diffusion, hence the subsequent rate of coolant vaporization is small. The net effect of the heat transfer is to reduce the fuel vapor pressure and reduce the expansion work by a factor of 1.2 to 2.5. Small-scale simulant experiments utilizing refrigerants could confirm the fuel condensation/sodium vaporization behavior, while reactor material tests must be done to investigate the radiation heat transfer mechanism.