Results 1 to 10 of about 10,834 (265)
Applicability research of round tube CHF mechanistic model in rod bundle channel
Nuclear Engineering and Technology, 2021 In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bundle ...
Wei Liu +6 more
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Nuclear Engineering and Technology, 2021 The crossflow is the key phenomenon in turbulent flow inside rod bundles. In order to establish confidence on application of computational fluid dynamics (CFD) to simulate the crossflow in rod bundles, three Reynolds-Averaged Navier Stokes (RANS) models ...
Fabian Wiltschko +2 more
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A methodology for CHF prediction in VVER rod bundles
Nuclear Engineering and Design, 2022 The critical heat flux (CHF) is an important thermal-hydraulic parameter that must be determined during the design of water-cooled reactors to ensure safety of operation. In this paper, a methodology is proposed to predict the CHF in VVER rod bundles. A whole-reactor model of VVER-1000 is implemented in RELAP-SCDAPSIM, and, based on the bundle-average ...
AbdulHameed, Mohamed +3 more
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Thermal-hydraulic Assessment of Seven Wire-wrapped rod Bundle [PDF]
E3S Web of Conferences, 2020 Lead bismuth eutectic (LBE) is one of the most potential materials for coolant and spallation target for Accelerator Driven Systems (ADS). Thermal-hydraulic behavior of LBE in fuel assembly is a key issue for development of the systems.
Lyu Kefeng, Sheng Xuelei, Ma Xudan
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Thermo-Hydraulic Investigation of Nanofluid as a Coolant in VVER-440 Fuel Rod Bundle [PDF]
Transport Phenomena in Nano and Micro Scales, 2015 The main purpose of this study is to perform numerical simulation of nanofluids as the coolant in VVER-440 fuel rod bundle. The fuel rod bundle contains 60 fuel rods with length of 960 mm and 4 spacer grids. In VVER-440 fuel rod bundle the coolant fluid (
S. Jalili Palandi +2 more
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Mechanical Engineering Journal, 2021 The void fraction distribution of a fuel rod bundle in a boiling water reactor is a critical parameter for accurately predicting the optimal thermal margin in the design of a reactor core. The rod bundle configuration, such as a part-length rod (PLR) and
Takahiro ARAI +7 more
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Frontiers in Energy Research, 2021 For a water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow regime transition and interchannel mixing effect, the corresponding CHF can transition ...
Wei Liu +3 more
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Natural circulation in a short-enclosed rod bundle [PDF]
International Journal of Heat and Mass Transfer, 2021 Large Eddy Simulation (LES) is used to study natural circulation flow in a sealed rod bundle with a Rayleigh number (based on height) of approximately and a fluid Prandtl number of 0.74. Natural convection boundary layer development is observed on both the heating rods and cooling containment surfaces.
Chinembiri, K. +3 more
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CFD Analysis of Subcooled Flow Boiling in 4 × 4 Rod Bundle
Applied Sciences, 2020 Rod bundle flow is an important research field related to reactor cooling in nuclear power plants. Owing to the rapid development of computerized performance assessments, interest in coolant flow analysis using computational fluid dynamics has garnered ...
Ye-Bon Seo +4 more
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Frontiers in Energy Research, 2022 Helium flow in the rod bundle channel with an open lattice structure is an important phenomenon for the advanced gas-cooled nuclear core design. In this study, thermal analysis with helium flow in various channel designs is conducted based on CFD methods
Zhipeng Wang +11 more
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