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Keyword [nuclear reactor]
Result: 121 - 140 | Page: 7 of 8
121. METHODS AND CRITERIA FOR EVALUATION OF NUCLEAR REACTOR FIRE PROTECTION ALTERNATIVES AND MODIFICATIONS
122. OPTIMAL CONTROL THEORY FOR XENON SPATIAL OSCILLATIONS IN LOAD FOLLOW OF A NUCLEAR REACTOR
123. A coupled nuclear reactor thermal energy storage system for enhanced load following operation
124. Historical civilian nuclear accident based Nuclear Reactor Condition Analyzer
125. Experimental and computational investigation of flow of pebbles in a pebble bed nuclear reactor
126. Very high temperature measurements: Application to nuclear reactor safety tests
127. Spectral Cascade-Transport Turbulence Model Development for Two-Phase Flow
128. Numerical Simulation Of Liquid Metal Sodium Flow And Heat Transfer Characteristics In Rectangular Microchannels
129. Dynamic Characteristics Of Water-lubricated Guide Bearing And Optimization Design Of Rotor Dynamics For Reactor Coolant Pump
130. Failure Analysis Of The Latch Arm Of CRDM In Nuclear Reactor And Study On Its Typical Materials' Wear Mechanism
131. Numerical Study On Heat Transfer Enhancement Of The Steam Generator Tubes In Small Nuclear Reactor
132. Prediction Of Nuclear Fuel Rod Damage Based On Artificial Neural Network
133. Design Of The Thermal Conductivity Type Hydrogen Concentration Detector For Nuclear Reactor
134. Analysis Of Countercurrent Flow Limitation In PWR Downcomer Based On RELAP5 Program
135. Investigation On The Operation Characterustics Of 100kWe Brayton Cycle System Coupled With Lithium Cooled Space Fast Reactor
136. Research On Coordinated Control With Nuclear Reactor And Steam Turbine Of 200MW High Temperature Gas-cooled Raector Pebble-bed Module Power Palnt
137. Assessment And Validation Of Interfacial Drag Models Of Nuclear Reactor Thermal System Program
138. Design And Research On Segmented Monolithic Stud Tensioner Of Nuclear Reactor Pressure Vessel
139. Optimal Control For Nuclear Reactor Power Based On Adaptive Dynamic Programming
140. Auxiliary Positioning Method And System Implementation Of Nuclear Reactor Pressure Vessel Inspection Platform
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