Results 1 to 10 of about 11,086 (118)
Assessment of heat transfer correlations in the sub-channels of proposed rod bundle geometry for supercritical water reactor [PDF]
Heliyon, 2019 There are heat transfer correlations for heat transfer analysis in single tube geometries after several experimental and theoretical heat transfer studies in these single tube geometries.
Seth Kofi Debrah +3 more
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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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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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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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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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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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Analysis of Subchannel and Rod Bundle PSBT Experiments with CATHARE 3
Science and Technology of Nuclear Installations, 2012 This paper presents the assessment of CATHARE 3 against PWR subchannel and rod bundle tests of the PSBT benchmark. Noticeable measurements were the following: void fraction in single subchannel and rod bundle, multiple liquid temperatures at subchannel ...
M. Valette
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Uniform versus Nonuniform Axial Power Distribution in Rod Bundle CHF Experiments
Science and Technology of Nuclear Installations, 2014 Rod bundle experiments with axially uniform and nonuniform heat fluxes are examined to explore the potential limitations of using uniform rod bundle CHF data for CHF correlation development of light water reactors with nonuniform axial power distribution
Baowen Yang +5 more
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