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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Constellation seeks rezone for property adjacent to Illinois plant
While no development details have been released, Constellation is asking to rezone 658.8 acres of land it owns around the Byron nuclear plant in Illinois for possible long-term use.
Ibrahim Jarrah, Rizwan uddin (Univ of Illinois)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 503-512
The spent fuel dry cask should remain subcritical under normal, abnormal, and accident conditions. The cask becomes susceptible to criticality if it is misloaded with assemblies that do not conform with the Certificate of Compliance (CoC). To avoid this scenario, the cask loading process involves several verification steps to make sure that all of the loaded assemblies satisfy the CoC requirements. However, most of loading and verification steps are carried out by humans with finite probabilities for errors, which need to be quantified. In this paper, the probability of misloading a cask with light water reactor (PWR and BWR) fuel is quantified using the event tree method. Probability distribution functions for all of the human errors are obtained using the SPAR-H human reliability analysis method. The Fussell-Vesely (FV) importance measure is performed to determine the tasks that contribute the most to the having a misloaded cask. The probability of misload is found to be 5.56E-06 for cask loaded with the PWR and 2.95E-05 for the cask loaded with the BWR fuel. Both of these are considered to be small.