2012
DOI: 10.1016/j.nucengdes.2011.11.016
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Uncertainty and sensitivity analysis in the neutronic parameters generation for BWR and PWR coupled thermal-hydraulic–neutronic simulations

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Cited by 11 publications
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“…Some other published researches on the sensitivity analysis for transient analysis of PWR reactor used a standalone neutronic and thermal-hydraulic codes which were coupled with other interface tools [9][10][11] while in the NODAL3 code, the neutronic and thermal-hydraulic modules are embedded in the code. Not found in those published works, in this study, the effects of axial zone width and time step width are also carried out.…”
Section: Introductionmentioning
confidence: 99%
“…Some other published researches on the sensitivity analysis for transient analysis of PWR reactor used a standalone neutronic and thermal-hydraulic codes which were coupled with other interface tools [9][10][11] while in the NODAL3 code, the neutronic and thermal-hydraulic modules are embedded in the code. Not found in those published works, in this study, the effects of axial zone width and time step width are also carried out.…”
Section: Introductionmentioning
confidence: 99%