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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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NRC begins special inspection at Hope Creek
The Nuclear Regulatory Commission is conducting a special inspection at Hope Creek nuclear plant in New Jersey to investigate the cause of repeated inoperability of one of the plant’s emergency diesel generators, the agency announced in a February 25 news release.
D. H. Lister, S. A. Kushneriuk, R. H. Campbell
Nuclear Science and Engineering | Volume 85 | Number 3 | November 1983 | Pages 221-232
Technical Paper | doi.org/10.13182/NSE83-A17314
Articles are hosted by Taylor and Francis Online.
A once-through loop containing pressurized water at 300°C and constant chemistry conditions of high pH (with LiOH) and dissolved hydrogen has been used to study the deposition and release of 60Co at heated Zircaloy surfaces. The activation of the surfaces proceeds by a mechanism involving dissolved species. The mechanism is affected little by heat flux, but a great deal by the type of oxide film formed by corrosion on the Zircaloy. To take account of the mechanism, a mathematical model has been developed. It describes first-order processes, such as adsorption/desorption or ion exchange occurring at a continuously changing surface. The model has furnished deposition and release coefficients for 60Co on thin black and thick white ZrO2 films for operation with and without heat flux.