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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Anton Bayer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 217-227
Technical Paper | Nuclear Safety | doi.org/10.13182/NT85-A33720
Articles are hosted by Taylor and Francis Online.
As a continuation of the “German Risk Study: Phase A,” further plant-oriented analysis has been performed and the off-site accident consequence model has been partially improved. The plant-oriented analysis carried out at the Karlsruhe Nuclear Research Center has been focused on two release categories, namely FK2 (core meltdown followed by immediate release of radionuclides from the leaking containment) and FK6 (core meltdown followed by late release of radionuclides as a result of failure due to overpressure in the containment). The thermohydraulic processes in the molten mass and the behavior of the fission and activation products released from the molten mass are considered in a more realistic way. The improvements of the off-site accident consequence model relate mainly to a more realistic modeling of the deposition and resuspension processes, to the ingestion submodel, and to dose factors. The results show that the improvements of the off-site accident consequence model do not change the final results dramatically; the model rather draws a more realistic picture of the interrelated processes, and consequently allows the application of the model to other problems in the nuclear field as well. From the investigations belonging to the plant-oriented analysis it appears, however, that the releases to be expected from postulated accidents are remarkably lower. Consequently, the risk is lower than assessed in Phase A of this study.