Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition 2014
DOI: 10.1115/icone22-30716
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Cross-Comparison of One-Dimensional Thermal-Hydraulic Codes on Natural Circulation Analysis of NACIE Loop Test for Lead-Alloy Cooled Advanced Nuclear Energy Systems (LACANES)

Abstract: As one of the Generation-IV reactor concepts, lead-alloy-cooled advanced nuclear energy systems (LACANES) have been studied worldwide in order to utilize the advantages of good heat transfer properties, neutron transparency and chemical inertness with air and water. Since the Fukushima accident, the passive safety aspect of the LACANES is increasingly emphasized due to outstanding natural circulation capability. To investigate the thermal-hydraulic capability of LBE, an international cooperation has been perfo… Show more

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“…Table 1. Main characteristic of NACIE loop (Shin et al, 2014) Main dimensions of the loop Table 3. Main dimensions of the heat exchanger (Coccoluto et al, 2011) Main dimensions of the HX…”
Section: Nacie Facilitymentioning
confidence: 99%
“…Table 1. Main characteristic of NACIE loop (Shin et al, 2014) Main dimensions of the loop Table 3. Main dimensions of the heat exchanger (Coccoluto et al, 2011) Main dimensions of the HX…”
Section: Nacie Facilitymentioning
confidence: 99%