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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Anton Bayer, Klaus Burkart, Joachim Ehrhardt, Wolfgang Hübschmann, Manfred Schückler, Siegfried Vogt, Wolfgang Jacobi, Herwig G. Paretzke, Klaus-Rüdiger Trott, Eduard Hofer, Bernard Krzykacz
Nuclear Technology | Volume 59 | Number 1 | October 1982 | Pages 20-50
Technical Paper | Nuclear Safety | doi.org/10.13182/NT82-A33050
Articles are hosted by Taylor and Francis Online.
The possible accidental releases from nuclear power plants with pressurized water reactors are classified into eight release categories. To assess the damage resulting from these releases, a model for accident consequences (UFOMOD) is set up. In this model, the atmospheric dispersion and ground deposition are evaluated, and the space- and time-dependent activity concentration in the atmosphere and on the ground is calculated. From these concentration values, the potential doses on which the different protective measures and countermeasures depend are first determined. The doses to be expected are then calculated taking into account these protective measures and countermeasures. Based on these doses, the consequences are assessed for the population affected, in terms of somatic early fatalities, somatic late fatalities, and genetic exposure. The consequences are then assessed by running several times through the 8 release categories at 19 sites with a total of 25 reactor units. The calculations for each site are based on 115 different weather sequences of several hours’ duration, assuming that these sequences have the same probability in each of the 36 predetermined wind directions (each of 10 deg). In parallel, the corresponding frequencies of occurrence are determined. From the pairs of values “extent of consequences/frequency of occurrence,” the final results are derived: