Quantitative Phenomena Identification and Ranking Table (QPIRT) for Reactor Safety Analysis

Next generation reactor safety analysis codes are intended to make use of advanced numerical methods and higher fidelity models with built-in sensitivity analysis (SA) and uncertainty quantification (UQ) [1]. However, due to the complex nature of uncertainty propagation in thermal-hydraulic codes, i...

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Bibliographic Details
Main Authors: Yurko, Joseph P. (Contributor), Buongiorno, Jacopo (Contributor)
Other Authors: Massachusetts Institute of Technology. Department of Nuclear Science and Engineering (Contributor)
Format: Article
Language:English
Published: American Nuclear Society, 2014-05-19T19:47:55Z.
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