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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
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: