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Keyword [fuel assembly]
Result: 81 - 100 | Page: 5 of 6
81.
Heat Transfer Research Of Flow Blockage In The Inlet Of Plate-type Fuel Assembly Based On CFD Simulation
82.
Experimental Study On Heat Dissipation Of Sodium Fast Reactor Spent Fuel Assembly During In-containment Transfer
83.
Auxiliary Positioning System Of Nuclear Power Plant Refueling Based On Machine Vision
84.
Research On Adaptive Flexible Detection Device Of Nuclear Fuelassembly And Multi-source Error Cooperative Compensation Method
85.
Study On Structural Improvement Design Of PWR FA Hold-down Spring
86.
The Preparation Process Of The Expansion Tool For The M5 Guide Pipe And Annular Tube Of AFA3G Fuel Assembly
87.
Design And Application Of Multifunction X-ray Real-time Imaging System
88.
Investigations On Flow And Heat Transfer Characteristics Of Plate Fuel Assemblies Under Blockage Conditions
89.
Experimental And Numerical Study On Flow And Heat Transfer Characteristics Of Rod Bundle Fuel Assembly Under Pulsating Flow
90.
Research On Structure And Mechanical Properties Of Fuel Assembly For CiADS Lead Bismuth Fast Reactor
91.
Study On Shear Damage Constitutive Model And Mixed Mode Fracture Of Simulated Spent Fuel Assemblies
92.
Numerical Study On Flow And Heat Transfer Characteristics Of A Rectangular Fuel Assembly With Blocked Channels
93.
Investigation On Characterisitcs Of Flow Field And Flux Allocation In An Annulur Fuel Assembly
94.
Research On Ultrasonic Detection System For Damage Of Underwater Spent Fuel Component Based On LabVIEW
95.
Numerical Simulation Of Turbulent Heat Transfer Of Liquid Lead-bismuth Eutectic(LBE)in Rod Bundle Channel
96.
Study On The Flow And Heat Transfer Characteristics Of Liquid Lead-bismuth Eutectic In Plate-type Fuel Assembly And Upper Plenum
97.
Research On Keytechnologies For Deformationmeasurement Of Nuclear Fuelassemblies Based On Binocularstructured Light
98.
Study On Flow And Heat Transfer Characteristics Of Supercritical Carbon Dioxide Inside Helical Cruciform Fuel Assembly Channel
99.
Study On The Effect Of Positioning Mode On Thermal And Hydraulic Characteristics Of Lead Cooled Fast Reactor Fuel Assembly
100.
Analysis Of The Effect Of PWR Bowing Fuel Assembly On The Thermal-hydraulic Characteristics
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