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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.
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Chicago, IL|Chicago Marriott Downtown
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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
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.
