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Sichao Tan
Harbin Engineering University
PhysicsBoilingHeat transferMechanicsClassical mechanics
71Publications
10H-index
294Citations
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Publications 81
Newest
#1Xing Li (HEU: Harbin Engineering University)H-Index: 2
#2Peiyao Qi (HEU: Harbin Engineering University)H-Index: 1
Last. Xiaoyu WangH-Index: 2
view all 6 authors...
Abstract Rod bundles are widely used in various devices and energy engineering including heat exchangers, nuclear fuel assembly and so on. The transient fluctuation of flow rate in the thermal devices is a common phenomenon under accident scenarios or ocean condition, the study of pulsatile flows has significant practical relevance for the design and safety of thermal devices. In order to determine the flow characteristics of pulsatile flows in rod bundles, the experimental investigations for tr...
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Abstract The application of passive safety systems (PSSs) can greatly improve the safety level of the Offshore Floating Nuclear Power Plants. As one of the important component of PSSs, the secondary passive residual heat removal system can be seen as the multiple natural circulation (NC) loops coupled system. The transient response characteristics between coupled natural circulation loops may affect the core decay heat removal progress under accident conditions. Besides, the ship motions caused ...
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#1Zahraddeen Abbati (HEU: Harbin Engineering University)H-Index: 1
#2Jiarui Chen (HEU: Harbin Engineering University)
Last. Sichao Tan (HEU: Harbin Engineering University)H-Index: 10
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Abstract In this research, an experiment was carried out in a multi-loop natural circulation system to study its response behaviors under single-phase and two-phase flow instability conditions. The experimental facility consists of primary and secondary natural circulation loops, as well as an external forced circulation loop, which serves as a final heat sink to the system. The secondary loop is meant to simulate passive residual heat removal system found in the advanced reactors and some small...
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Last. Sichao TanH-Index: 10
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Abstract Passive safety systems mostly working on the principles of natural circulation are given much priority in increasing the reliability of reactors’ inherent safety features. In view of this, many researchers carry out numerical and experimental studies in single-loop natural circulation model to study the natural circulation behaviors. In the present study, the experimental loop consists of three loops; two of which operate on natural circulation while the third on forced circulation. The...
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#1Peiyao QiH-Index: 1
#2Xing LiH-Index: 2
Last. Xiaoyu WangH-Index: 2
view all 6 authors...
Abstract The flow rate of the primary coolant in a nuclear reactor will fluctuate during accident conditions or in floating reactors that are affected by inertial forces in the ocean. These fluctuations may have a substantial impact on heat transfer by the primary coolant in the reactor. In the current research, the flow field distribution and turbulence structure at different planes of a 5 × 5 rod bundle under pulsating flow conditions were measured using phase-locked particle image velocimetry...
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#1Tao Meng (HEU: Harbin Engineering University)H-Index: 1
#2Kun ChengH-Index: 1
Last. Sichao Tan (HEU: Harbin Engineering University)H-Index: 10
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Abstract The computational simulations of 1/12 full core gas-cooled space nuclear reactor have been conducted using the STAR-CCM+ code. The reactor is cooled by the He-Xe mixture and coupled with direct Brayton turbo-machines. To analyze the flow and heat transfer characteristics of the reactor, a series of calculations with complex core structures under zero gravity condition are conducted. The influences of the bypass vessel cooling, surface radiation, flow channel blockage and the fuel rods a...
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#1Tao Meng (HEU: Harbin Engineering University)H-Index: 1
#2Fulong Zhao (HEU: Harbin Engineering University)H-Index: 1
Last. Sichao Tan (HEU: Harbin Engineering University)H-Index: 10
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ABSTRACTNeutronics analysis was conducted for a proposed megawatt-class gas cooled space nuclear reactor design. The reactor design has a high operating temperature of up to 1500 K. Annular UO2 fue...
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#1Qi Zhang (HEU: Harbin Engineering University)
Last. Sichao Tan (HEU: Harbin Engineering University)H-Index: 10
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Abstract The boron dilution transient may cause re-criticality during an emergency shutdown, and the mixing between de-borated slug and boric acid inside the annular down-comer and the lower plenum is the inherent mechanism against such accident. A visualization pressure vessel model was built to study the mixing phenomenon and analyze the mixing mechanism, the injection coolant with boric acid is represented by dye-sucrose solution, and the dye concentration distribution at longitudinal section...
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#1Fulong Zhao (HEU: Harbin Engineering University)H-Index: 1
#2Xiao Yan (THU: Tsinghua University)
Last. Sichao Tan (HEU: Harbin Engineering University)H-Index: 10
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Abstract The containment spray system is a vital part of the nuclear power plant to reduce the temperature and pressure within the containment during a hypothetical severe accident, which is bound up with the safety of the nuclear reactor. To investigate the performance of the containment spray system, the model coupling the multi-droplets motion and phase change model inducing the local gas parameters surrounding the droplets is formulated. The proposed model is utilized to simulate the droplet...
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