Shuo Chen , Junsen Fu , Quanyi Gao , Yubo Sun , Yao Xiao , Tenglong Cong , Hanyang Gu
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引用次数: 0
Abstract
The tight-lattice fuel assembly is a key research area in the design of the high-performance water reactor, of which the thermal–hydraulic characteristics are significantly different from those used in the conventional pressurized water reactor because of its small pitch-to-diameter ratio. Under loss-of-flow accidents, the dryout and post-dryout heat transfer characteristics in the fuel assembly directly impact its safety. However, the relevant studies are limited, restricting the core design and safety analyzation. In this paper, a subchannel code suitable for post-dryout flow and heat transfer in the tight-lattice fuel assembly is developed based on MATRA program by introducing submodels specialized for various flow and heat transfer regimes. By comparing with experimental data of rod bundles, it is confirmed that the developed subchannel code can accurately predict the dry-out location and the heat transfer of mist flow after dryout in the tight lattice fuel assembly. Subsequently, the subchannel code is utilized to analyze the post-dryout heat transfer behavior in the tight lattice fuel assembly. The results indicate that the hydraulic diameter of subchannel significantly influences the flow field distribution. The corner subchannel with a small hydraulic diameter has the lowest flow rate, and thus the vapor void fraction and quality vary fastest along the axial direction. Though the central subchannel with the largest hydraulic diameter has the highest mass flux, but due to the large heating area, the vapor void fraction and quality still increase relatively high. The transverse flow between different subchannels follows the trend from the corner subchannel to the side subchannel, and then to the central subchannel. Due to the high mass flux and high quality in the corresponding subchannel, the dryout occurs earliest on the center rod, resulting in the largest wall temperature. Meanwhile, the spacer grids show stronger effects on post-dryout heat transfer enhancement in each subchannel. The research conclusions could provide reference to the thermal–hydraulic design of the tight-lattice fuel assembly.
期刊介绍:
Annals of Nuclear Energy provides an international medium for the communication of original research, ideas and developments in all areas of the field of nuclear energy science and technology. Its scope embraces nuclear fuel reserves, fuel cycles and cost, materials, processing, system and component technology (fission only), design and optimization, direct conversion of nuclear energy sources, environmental control, reactor physics, heat transfer and fluid dynamics, structural analysis, fuel management, future developments, nuclear fuel and safety, nuclear aerosol, neutron physics, computer technology (both software and hardware), risk assessment, radioactive waste disposal and reactor thermal hydraulics. Papers submitted to Annals need to demonstrate a clear link to nuclear power generation/nuclear engineering. Papers which deal with pure nuclear physics, pure health physics, imaging, or attenuation and shielding properties of concretes and various geological materials are not within the scope of the journal. Also, papers that deal with policy or economics are not within the scope of the journal.