433 results on '"Tian, Wenxi"'
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52. Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor
53. Phenomena identification and ranking table of station blackout accidents for China sodium cooled fast reactor
54. Numerical analysis of liquid fall type gas entrainment in pool-type fast reactor
55. Oxygen transport analysis in lead-bismuth eutectic coolant for solid-phase oxygen control
56. Thermal-hydraulic analysis of a lead–bismuth small modular reactor under moving conditions
57. Study on the systematic thermal-hydraulic characteristics of helical coil once-through steam generator
58. Numerical simulation of bubble transport during steam generator tube rupture accident of Lead-cooled Fast Reactor
59. CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel
60. Analysis of the natural circulation test of PHENIX reactor by the THACS code
61. Development of thermal hydraulic analysis code of annular fuel under flow blockage condition
62. CFD simulation of thermal hydraulic phenomena in enclosed cavity of nuclear power plants
63. Experimental study on heat transfer limit of high temperature potassium heat pipe for advanced reactors
64. Experimental and numerical investigation on flow characteristics of inter-wrapper channel in LMFBR
65. A porous medium model for simulating conjugate heat transfer between wire-wrapped fuel bundles under forced and mixed convection
66. Design research for the porous hexagonal prism shaped fuel element adopted in nuclear thermal propulsion reactor based on neutronics and thermal-hydraulics coupled method
67. Recent progress of CFD applications in PWR thermal hydraulics study and future directions
68. Study of boron diffusion models and dilution accidents in nuclear reactor: A comprehensive review
69. Numerical method development for oxidation particle formation during sodium spray fires in SFR containment
70. Theoretical study of steady-state characteristics of natural circulation system
71. Preliminary design of the I2S-LWR containment system
72. Development and application of MOQUICO code to study molten corium-concrete interaction
73. Conceptual design and analysis of a megawatt power level heat pipe cooled space reactor power system
74. Code development and analysis of heat pipe cooled passive residual heat removal system of Molten salt reactor
75. Three-dimensional numerical study on the effect of sidewall crust thermal resistance on transient MCCI by improved MPS method
76. Experimental and theoretical study on fluid-structure interaction and non-equilibrium of the flow through micro cracks
77. A critical heat flux model for unilateral heating rectangular narrow channel
78. Core thermal-hydraulic evaluation of a heat pipe cooled nuclear reactor
79. Transient analysis of tritium transport characteristics of thorium molten salt reactor with solid fuel
80. Code improvement, separate-effect validation, and benchmark calculation for thermal-hydraulic analysis of helical coil once-through steam generator
81. Numerical study on the thermal stratification characteristics in the upper plenum of sodium-cooled fast reactor (SFR)
82. Development and validation of thermo-mechanical analysis code of metallic fuel under steady-state conditions in LMFR
83. Experimental research on heat transfer behavior of large scale two-layer salt melt pool based on COPRA facility
84. RELAP5/MOD3.4 calculation and model evaluation based on upper plenum entrainment experiment in AP1000
85. Experimental investigation of steam-air condensation on containment vessel
86. Local effect model development for the steam generator three dimensional thermal hydraulics analysis code
87. Development of a three-field mechanistic model for dryout prediction in annular flow
88. Study on the water seal formation process in advanced PWR pressurizer using CFD method
89. Transient thermoelectric characteristics of the principle prototype for the heat pipe cooled nuclear Silent themoelectirc reactor (NUSTER)
90. Numerical and experimental analysis of LBE flow and heat transfer characteristics in hexagonal rod bundles
91. Flow and heat transfer characteristics in plate-type fuel channels after formation of blisters on fuel elements
92. Numerical study of bubble rising in quiescent liquid under rolling motion conditions using MPS – MAFL method
93. Steam condensation on a downward-facing plate in presence of air
94. Development and validation of boron diffusion model in nuclear reactor core subchannel analysis
95. Numerical study on the thermal stratification characteristics of AP1000 pressurizer surge line
96. Development of a subchannel analysis code and its application to annular fuel assemblies
97. Experimental and numerical study on helium flow characteristics in randomly packed pebble bed
98. Thermal-hydraulic analysis code development for sodium heated once-through steam generator
99. Experimental study and optimized design on electromagnetic pump for liquid sodium
100. Improvement of RELAP5 code for density wave instability analysis in parallel narrow rectangular channels
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