Search Results - "Qiu, S.Z"

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  1. 1

    A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti3SiC2 for ATF cladding by Qiu, Bowen, Wang, Jun, Deng, Yangbin, Wang, Mingjun, Wu, Yingwei, Qiu, S.Z.

    Published in Nuclear engineering and technology (01-01-2020)
    “…At present, the Department of Energy (DOE) in Unite State are directing the efforts of developing accident tolerant fuel (ATF) technology. As the first barrier…”
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    Journal Article
  2. 2

    The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head by Zhang, Y.P., Zhang, L.T., Zhou, Y.K., Tian, W.X., Qiu, S.Z., Su, G.H., Zhao, B., Yuan, Y.D., Ma, R.B.

    Published in Annals of nuclear energy (01-03-2016)
    “…•Establishing the first full-scale COPRA facility for Chinese PWR.•New experiments can be conducted using COPRA facility.•The first experimental results of…”
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    Journal Article
  3. 3

    Numerical investigation on coalescence of bubble pairs rising in a stagnant liquid by Chen, R.H., Tian, W.X., Su, G.H., Qiu, S.Z., Ishiwatari, Yuki, Oka, Yoshiaki

    Published in Chemical engineering science (01-11-2011)
    “…In the present study, we preformed a two-dimensional numerical simulation of the motion and coalescence of bubble pairs rising in the stationary liquid pool,…”
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  4. 4

    Effect of stratified interface instability on thermal focusing effect in two-layer corium pool by Ge, K., Zhang, Y.P., Tian, W.X., Su, G.H., Qiu, S.Z.

    “…•The relationship between thermal focusing effect and melting degree is obtained.•The unevenness of the crust highly intensifies the thermal focusing…”
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  5. 5

    Experimental investigation on steam-water two-phase flow boiling heat transfer in a staggered horizontal rod bundle under cross-flow condition by Zhang, K., Hou, Y.D., Tian, W.X., Zhang, Y.P., Su, G.H., Qiu, S.Z.

    Published in Experimental thermal and fluid science (01-09-2018)
    “…•A steam-water two-phase flow boiling heat transfer test loop is established.•The effect of row number on local flow boiling heat transfer in horizontal tube…”
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  6. 6

    Experimental investigation of entrainment effect on the countercurrent flow in the Hot Leg and Pressurizer Surge Line assembly of third-generation passive nuclear reactors by Yu, Jiangtao, Zhang, Dalin, Shi, Leitai, Tian, Wenxi, Su, G.H., Qiu, S.Z.

    Published in Nuclear engineering and design (15-08-2018)
    “…•Different flow regimes of CCF occur at different Hot Leg water levels.•CCF mechanisms are well analyzed from films and transient parameters.•Stratified-flow…”
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  7. 7

    Development of a multi-compartment containment code for advanced PWR plant by Chen, Yongzheng, Wu, Y.W., Wang, M.J., Zhang, Y.P., Tan, B., Zhang, D.L., Tian, W.X., Qiu, S.Z., Su, G.H.

    Published in Nuclear engineering and design (01-08-2018)
    “…•First attempt to develop a containment code for HPR1000 plant.•Sufficient coupled models were included for integral analysis.•Buoyant plume, counter-current…”
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  8. 8

    Effects of nitrogen and carbon monoxide on the detonation of hydrogen-air gaseous mixtures by Chen, Yongzheng, Liu, Bo, Zhang, Y.P., Zhang, D.L., Revankar, Shripad T., Tian, W.X., Qiu, S.Z., Su, G.H.

    Published in Nuclear engineering and design (01-03-2019)
    “…•Quantify the effects of N2 and CO on the detonation of H2-air mixtures.•Ion probes were designed to measure the detonation velocity.•Detailed chemical…”
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    Journal Article
  9. 9

    Analysis of safety margin of in-vessel retention for AP1000 by Zhang, Y.P., Qiu, S.Z., Su, G.H., Tian, W.X.

    Published in Nuclear engineering and design (01-08-2010)
    “…In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by most operating nuclear power plants and advanced light water…”
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  10. 10

    Experimental research on the characteristics of steam-water counter-current flow in the Pressurizer Surge Line assembly by Yu, Jiangtao, Zhang, Dalin, Shi, Leitai, Wang, Zhiwei, Tian, Wenxi, Su, G.H., Qiu, S.Z.

    Published in Experimental thermal and fluid science (01-09-2018)
    “…•Intermittent entrainment and flooding become severer at higher steam flow rate.•Predominant CCFL happened at the junction of the Pressurizer and Surge…”
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  11. 11

    A study on the dynamic characteristics of the secondary loop in nuclear power plant by Zhang, J., Yin, S.S., Chen, L., Ma, Y.C., Wang, M.J., Fu, H., Wu, Y.W., Tian, W.X., Qiu, S.Z., Su, G.H.

    Published in Nuclear engineering and technology (01-05-2021)
    “…To obtain the dynamic characteristics of reactor secondary circuit under transient conditions, the system analysis program was developed in this study, where…”
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  12. 12

    Preliminary study on FROBA-SCO2 with transient models and its application for Reactivity Initiated Accident and loss of flow accident by Yang, T.A., Zhang, K., Yang, H.K., Tian, W.X., Qiu, S.Z.

    “…As a coolant enabling the reactor with a high efficiency and low volume, the supercritical CO2 has becoming a hot topic nowadays. However, the fuel rod…”
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  13. 13

    Heat transfer characteristics of single-layer and two-layer corium pool in elliptical lower head by Zhang, Y.P., Zhu, D.H., Ge, K., Wu, Y.W., Tian, W.X., Su, G.H., Qiu, S.Z.

    “…In this study, we investigated the characteristics of natural convection heat transfer of single-layer and two-layer corium pool in the elliptical lower head…”
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  14. 14

    A 3-D simulation tool for hydrogen detonation during severe accident and its application by Huang, T., Zhang, Y.P., Tian, W.X., Su, G.H., Qiu, S.Z.

    Published in Annals of nuclear energy (01-06-2017)
    “…•DEST has been developed by using High resolution scheme, ASIRK-2B method and multi-blocking patching method.•The DEST is verified and applied to the…”
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  15. 15

    The code development and thermo-hydrodynamic analysis of the reflood during severe accident in PWR by Niu, S.P., Zhang, Y.P., Tian, W.X., Qiu, S.Z., Su, G.H.

    Published in Annals of nuclear energy (01-01-2017)
    “…•A thermo-hydraulic analysis model for the reflood phase is developed and presented.•A code module is developed for the thermo-hydraulic analysis of…”
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  16. 16

    A review on thermohydraulic and mechanical-physical properties of SiC, FeCrAl and Ti 3 SiC 2 for ATF cladding by Qiu, Bowen, Wang, Jun, Deng, Yangbin, Wang, Mingjun, Wu, Yingwei, Qiu, S.Z

    “…At present, the Department of Energy (DOE) in Unite State are directing the efforts of developing accident tolerant fuel (ATF) technology. As the first barrier…”
    Get full text
    Journal Article
  17. 17

    A study on the dynamic characteristics of the secondary loop in nuclear power plant by Zhang, J, Yin, S.S, Chen, L, Ma, Y.C, Wang, M.J, Fu, H, Wu, Y.W, Tian, W.X, Qiu, S.Z, Su, G.H

    “…To obtain the dynamic characteristics of reactor secondary circuit under transient conditions, the system analysis program was developed in this study, where…”
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    Journal Article
  18. 18

    A new method on fluid-to-fluid scaling for heat transfer in tubes at supercritical pressures by Yu, Guojun, Jiang, Chaofei, Wang, Liu, Su, G.H., Qiu, S.Z.

    “…•The requirements on fluid scaling at supercritical pressures were illustrated.•Comprehensive influence of experimental conditions and fluid types was…”
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  19. 19

    Experimental investigations on single-phase convection and steam-water two-phase flow boiling in a vertical rod bundle by Zhang, K., Hou, Y.D., Tian, W.X., Fan, Y.Q., Su, G.H., Qiu, S.Z.

    Published in Experimental thermal and fluid science (01-01-2017)
    “…•A new correlation was developed to predict Reynolds number at the transition from laminar region to turbulent region.•A new correlation was developed to…”
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  20. 20

    Numerical study on the condensation characteristics of vapor with non-condensable gas on inclined walls inside containment by Cai, J.Y., Zhang, K., Ma, X.R., Chen, T., Tian, W.X., Qiu, S.Z.

    Published in Annals of nuclear energy (01-09-2024)
    “…•On the basis of Dehbi diffusion model, the UDF program for condensation of vapor containing non-condensable gases is prepared by using CFD program…”
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