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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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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Latest News
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
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.