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Division Spotlight
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.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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
BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
Karl O. Ott
Nuclear Science and Engineering | Volume 99 | Number 1 | May 1988 | Pages 13-27
Technical Paper | doi.org/10.13182/NSE88-A23541
Articles are hosted by Taylor and Francis Online.
The longer term response of oxide- and metal-fueled liquid-metal-cooled reactors to unscrammed loss-of-flow and loss-of-heat-sink failures is investigated. The investigation consists of a review of numerical transient calculations performed by the Argonne National Laboratory Reactor Analysis and Safety Division, and of analytical analyses of semiasymptotic states. The emphasis is on the identification and evaluation of an inherent shutdown state for metal fuel, with its high heat conductivity, as an alternative to the familiar low-power asymptotic critical state. Design implications for retaining the inherently effected shutdown for a sufficiently long period are discussed and quantitatively evaluated. In addition, the effect of uncertainties of reactivity coefficients on predictions for such unscrammed transients is investigated. It is shown how measurements during a preoperational safety demonstration phase can validate and possibly correct those predictions.