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...
| Main Authors: | , |
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| Format: | Article |
| Language: | en_US |
| Published: |
American Nuclear Society
2014
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| Online Access: | http://hdl.handle.net/1721.1/87057 https://orcid.org/0000-0001-6501-2836 |