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MARVEL team shares lessons learned through microreactor development
On June 1 at the American Nuclear Society’s Annual Conference in Denver, Colo., a team from Idaho National Laboratory presented a session titled “Lessons Learned from MARVEL Reactor Fabrication.” The presentation highlighted challenges that arose as they moved from design to manufacturing and assembly, with a focus on reactor part fabrication, Stirling engine implementation, and reactivity control system development.
Yean-Chuan Yeh, Jyh-Tong Teng
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 252-255
Technical Paper | Probabilistic Safety Assessment and Risk Management / Nuclear Safety | doi.org/10.13182/NT89-A34207
Articles are hosted by Taylor and Francis Online.
A quantified correlation process to assess those dynamic human error probabilities for which timing data can be sampled from generic occurrences and/or from plant-specific simulator training records is presented. The method is based on a comparison between two random variables, representing the critical time for system response and the action time for operator achievement capability. The maximum entropy estimator is employed to handle the sampled timing data. The operator action in performing rapid cooldown and depressurization following an initiating event of steam generator tube rupture is used to delineate this method. The resulting datum has been successfully applied in a risk analysis project.