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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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Article considers incorporation of AI into nuclear power plant operations
The potential application of artificial intelligence to the operation of nuclear power plants is explored in an article published in late December in the Washington Examiner. The article, written by energy and environment reporter Callie Patteson, presents the views of a number of experts, including Yavuz Arik, a strategic energy consultant.
Michael Langer, Manfred Wallner
Nuclear Technology | Volume 121 | Number 2 | February 1998 | Pages 199-211
Technical Paper | German Direct Disposal Project | doi.org/10.13182/NT98-A2832
Articles are hosted by Taylor and Francis Online.
Site-specific data of the Gorleben salt dome (e.g., the geological structure of the salt dome and the geomechanical properties of the evaporite) are presented in the form of a working model to optimize the various repository concepts discussed within the German research project "Direct Disposal of Spent Fuel" and to compare their long-term effects.A comparative evaluation of the different emplacement concepts was made on the basis of the following calculated results, which are considered decisive: temperatures in the repository, temperatures in the salt dome/overburden transition zone, tensile stresses at the top of the salt dome zone, and uplift at the ground surface.The thermal and thermomechanical consequences of four preselected emplacement concepts do not differ very much. The rock mechanical analyses of the far field do not indicate any particular concept as being clearly preferable.The following results of the parameter variations (creep capacity and width of the repository field) are significant. A reduction in the repository field width gives lower maximum temperatures for the same specific heat load. An evaporite formation with a high creep capacity leads to significantly lower stress reduction at the top of the salt dome; tensile stresses do not occur. The stress reductions at the top of the salt dome are also less, but the horizontal stress orthogonal to the repository still lies in the tensile zone, if a low creep capacity of the rock salt is assumed.