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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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DOE fast tracks test reactor projects: What to know
The Department of Energy today unveiled 10 companies racing to bring test reactors online by next year to meet Trump's deadline of next Independance Day, leveraging a new DOE pathway that allows reactor authorization outside national labs. As first outlined in one of the four executive orders on nuclear energy released by President Trump on May 23 and in the request for applications for the Reactor Pilot Program released June 18, the companies must use their own money and sites—and DOE authorization—to get reactors operating. What they won’t need is a Nuclear Regulatory Commission license.
Keith Woodard
Nuclear Technology | Volume 12 | Number 3 | November 1971 | Pages 281-289
Technical Paper | Reactor Siting | doi.org/10.13182/NT71-A31008
Articles are hosted by Taylor and Francis Online.
The atmospheric dispersion characteristics in the vicinity of a nuclear power plant are important in establishing criteria for safety features, reactor containment, and site boundaries so that there is reasonable assurance that radiation dose guidelines would not be exceeded should a major accident occur. Large quantities of meteorological data are now available from many sites which provide a good statistical base for evaluating the effect of local site weather conditions on the total dose risk. A model has been developed for determining dose level versus probability based on combining time variant weather data with the time variant fission product release following an accident. The results obtained using this model to evaluate several sites indicate that the probability of any individual receiving a dose in excess of regulatory guidelines is quite low, given that an accident has occurred and that the resulting fission product releases are evaluated using conservative AEC licensing assumptions. These results also show a large variation in dose among facilities at a given probability level. Other applications of this model for evaluating doses due to hydrogen purging, for predicting the most faborable time to make routine effluent releases, and for assessing total dose risk of a given site are also discussed.