Abstract
A Monte Carlo analysis of typical LWR cladding under LOCA conditions is performed. The thermal hydraulic model is greatly simplified, with more emphasis on thermomechanics. The model is three dimensional to capture azimuthal asymmetries. The fuel is ignored save for it's role in decreasing plenum size. The figures of merit are the burst temperature and pressure, as well as the maximum hoop strain and and percent length of clad with hoop strain in excess of 5 percent. Results include Pearson correlation coefficients as well as scatter plots with chromatic scales in order to elucidate relations between figures of merit.
| Original language | English |
|---|---|
| Pages | 463-468 |
| Number of pages | 6 |
| State | Published - 2020 |
| Event | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 - Seattle, United States Duration: Sep 22 2019 → Sep 27 2019 |
Conference
| Conference | 14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water Reactor Fuel Performance Conference, TOP FUEL 2019 |
|---|---|
| Country/Territory | United States |
| City | Seattle |
| Period | 09/22/19 → 09/27/19 |
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