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8篇 您的检索式:作者名="Daogang LU"
    题名 作者 年代 出处 被引量
1Numerical investigation on temperature fluctuation of the parallel triple-jet显示文摘CAO Qiong LU Daogang L(U) Jing 2012Nuclear Engineering and Design2012,249,10:1
2Experimental study on three-dimensional temperature fluctuation caused by coaxial-jet flows显示文摘LU Daogang CAO Qiong LV Jing 0,,01:1
3Numerical investigation on temperature fluctuation of the parallel triple-jet显示文摘CAO Qiong LU Daogang LV Jing 0,,01:1
4Bonding Character and Formation Energy of Point Defects of He and Vacancy on (001) Surface of bcc Iron by First Principle Calculations显示文摘The structure and energy of He impurities and vacancy on (001) surface of bcc iron are investigated by an ab initio method. Three cases for stabilities of a He atom at the surface are found: some of He atoms at surface atomic layers (SAL) relax into vacuum gap; some of surface He atoms at octahedral interstitial site relax into more stable tetrahedral interstitial site; some of surface He atoms still stay at tetrahedral interstitial site. The un-stability of the He atom at the surface system can be explained by deformation mechanism of charge densities and electronic densities of states. It is found that formation energy of the point defects from the topmost SAL to bulk-like atomic layer increase gradually, for example, the formation energies of a monovacancy at the first five topmost SALs are equal to 0.33, 1.56, 2.04, 2.02 and 2.11 eV, respectively. The magnetic moments of Fe atoms in the surface atomic layers are also calculated.Jun CAI Daogang LU 2013Acta Metallurgica Sinica(English Letters)2013,26,1:1
5Experimental investiga- tion on flow-induced vibration of fuel rods in supercritical water reactor 显示文摘Wu Licun Lu Daogang Liu Yu 2014Science and Technology of Nuclear Installation2014,16,7:1
6Analysis of Thermal-hydraulic Behavior in the Upper Plenum of Fast Breeder Reactor 'Monju' during Reactor Scram Transient 显示文摘Daogang Lu Yasuhiro E PNC PN94100,,:1
7Stabil- ity analysis for single-phase liquid metal rectan- gular natural circulation loops显示文摘LU Daogang ZHANG Xun GUO Chao 2014Annals of Nu- clear Energy2014,73,:1
8Experimental study of primary and secondary side coupling natural convection heat transfer characteristics of the passive residual heat removal system in AP1000显示文摘Passive residual heat removal heat exchanger(PRHR HX),which is a newly designed equipment in the advanced reactors of AP1000 and CAP1400,plays an important role in critical accidental conditions.The primary and secondary side coupling heat transfer characteristics of the passive residual heat removal system(PRHRS)determine the capacity to remove core decay heat during the accidents.Therefore,it is necessary to investigate the heat transfer characteristics and develop applicable heat transfer formulas for optimized design.In the present paper,an overall scaled-down natural circulation loop of PRHRS in AP1000,which comprises a scaleddown in-containment refueling water storage tank(IRWST)and PRHR HX models and a simulator of the reactor core,is built to simulate the natural circulation process in residual heat removal accidents.A series of experiments are conducted to study thermal-hydraulic behaviors in both sides of the miniaturized PRHR HX which is simulated by 12 symmetric arranged C-shape tubes.For the local PRHR HX heat transfer performance,traditional natural convection correlations for both the horizontal and vertical bundles are compared with the experimental data to validate their applicability for the specific heat transfer condition.Moreover,the revised natural convection heat transfer correlations based on the present experimental data are developed for PRHR HX vertical and lower horizontal bundles.This paper provides essential references for the PRHRS operation and further optimized design.Zhimin QIU Daogang LU Jingpin FU Li FENG Yuhao ZHANG 2021Frontiers in Energy2021,15,4:0
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