Search Results - "Hanyang Gu"

Experimental investigation of two-phase flow evolution in a tight lattice bundle using wire-mesh sensor by Zhang, Hengwei, Xiao, Yao, Gu, Hanyang

“…•The experiments of vertical co-current air-water two-phase flow in an up-scaled tight lattice bundle were carried out.•A 16 × 32 wire-mesh sensor was used to…”
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Study on bubbly and cap-bubbly flow in a square channel using dual wire-mesh sensors by Zhang, Hengwei, Xiao, Yao, Gu, Hanyang, Liu, Da

“…•The experiments of bubbly and cap-bubbly flow in a 66mm × 66mm square channel were carried out. A dual wire-mesh sensors (WMSs) was used to measure the…”
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Effects of surface orientation and heater material on heat transfer coefficient and critical heat flux of nucleate boiling by Mei, Yong, Shao, Yiqiong, Gong, Shengjie, Zhu, Yechen, Gu, Hanyang

“…•Surface orientation effect on the HTC and CHF is studied.•The corrosion of SA508 enhances the CHF.•Thermal effusivity effect on the CHF is investigated.•A new…”
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Flow pattern transition and void fraction prediction of gas–liquid flow in helically coiled tubes by Liu, Li, Zhang, Jiarong, Hu, Bing, Dai, Juntao, Wang, Ke, Gu, Hanyang

“…•Flow patterns in helically coiled tubes (HCTs) are classified by visual observation.•Flow-regime map is proposed and mechanisms of flow transitions are…”
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Recognition of gas-liquid flow regimes in helically coiled tube using wire-mesh sensor and KNN algorithm by Liu, Li, Hu, Bing, Liu, Shuai, Wang, Ke, Gu, Hanyang

“…•Flow patterns in helically coiled tube are classified by visual observation.•Void fraction for entire cross-section is measured by wire-mesh sensor.•k-Nearest…”
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Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests by Guo, Hui, Huo, Xingkai, Feng, Kuaiyuan, Gu, Hanyang

“…High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project…”
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Development of a refined helical fuel mixing model and application to a helical fuel rod bundle by Fu, JunSen, Xiao, Yao, Li, JunLong, Zhang, Qi, Cong, TengLong, Gu, HanYang

“…Fuel assemblies have a decisive impact on the performance and safety of nuclear reactors. Helical fuel has huge potential for application in small module…”
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Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis by Wu, Yiwei, Song, Qufei, Wang, Ruixiang, Xiao, Yao, Gu, Hanyang, Guo, Hui

“…With the rise of economic and safety standards for nuclear reactors, new concepts of Gen-IV reactors and modular reactors showed more complex designs that…”
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Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis by Wu, Yiwei, Song, Qufei, Feng, Kuaiyuan, Vidal, Jean-François, Gu, Hanyang, Guo, Hui

“…The development of fast reactors with complex designs and operation status requires more accurate and effective simulation. The Monte-Carlo method can generate…”
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Generating multi-group cross-sections using continuous-energy Monte Carlo method for fast reactor analysis by Guo, Hui, Shen, Yuyang, Wu, Yiwei, Song, Qufei, Gu, Hanyang

“…The deterministic two-step method, comprising multigroup cross-section generation and core calculation, is widely applied in fast reactor design and analysis…”
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Experimental and numerical investigation of turbulent convective heat transfer deterioration of supercritical water in vertical tube by Zhang, Ge, Zhang, Hao, Gu, Hanyang, Yang, Yanhua, Cheng, Xu

“…► We conduct supercritical heat transfer experiments on a new facilities of Shanghai Jiao Tong University (SJTU). ► An improved 4 equations model is proposed…”
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Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests by Guo, Hui, Jin, Xin, Huo, Xingkai, Gu, Hanyang, Wu, Haicheng

“…Nuclear data is the basis of reactor physics analysis. This paper aim at studying the influence of major evaluated nuclear data libraries, CENDL-3.2,…”
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Development and evaluation of fuel performance analysis code FuSPAC by Cong, Tenglong, Chen, Hao, Chen, Chao, Zhang, Shaohong, Gu, Hanyang

“…The nuclear fuel rod should maintain self-sustainable nuclear fission, as the first safety barrier to prevent the leakage of radioactive products. The fuel rod…”
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Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons by Feng, KuaiYuan, Hu, Jipu, Wang, Yihu, Cong, Tenglong, Gu, Hanyang, Guo, Hui

“…With the development of nuclear energy, microreactors have received increasing interest among researchers in recent years. In this paper, a megawatt heat pipe…”
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Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC by Guo, Hui, Peng, Xingjie, Wu, Yiwei, Jin, Xin, Feng, Kuaiyuan, Gu, Hanyang

“…The small modular liquid-metal fast reactor (SMFR) is an important component of advanced nuclear systems. SMFRs exhibit relatively low breeding capability and…”
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Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core by Liu, Maolong, Zeng, Chen, Luo, Zilin, Gu, Hanyang, Deng, Jian

“…The random distribution of TRISO fuel particles in the fuel elements may form local hotspots, thereby increasing the thermal stress on TRISO particle layers…”
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Modeling of bubble shape in horizontal and inclined tubes by Hanyang, Gu, Liejin, Guo

“…An experimental and theoretical study on the bubble shape of intermittent flow in the horizontal and inclined pipes has been carried out. The experiment…”
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Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis by Yiwei Wu, Qufei Song, Ruixiang Wang, Yao Xiao, Hanyang Gu, Hui Guo

“…With the rise of economic and safety standards for nuclear reactors, new concepts of Gen-IV reactors and modular reactors showed more complex designs that…”
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Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis by Yiwei Wu, Qufei Song, Kuaiyuan Feng, Jean-Francois Vidal, Hanyang Gu, Hui Guo

“…The development of fast reactors with complex designs and operation status requires more accurate and effective simulation. The Monte-Carlo method can generate…”
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Study on heat transfer behavior in rod bundles with spacer grid by Liu, Da, Gu, Hanyang

“…•Effect of spacer grid on heat transfer in rod bundles is experimentally investigated.•Buoyancy effect shows significant influence on the heat transfer…”
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