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Keyword [Pressurized Water Reactor]
Result: 61 - 80 | Page: 4 of 5
61. Evaluation Of Gamma Radiation On PWR Primary Surfaces Based On TRIPOLI-4 Monte Carlo Code
62. Study On Project Schedule Plan For Pressurized Water Reactor Outage
63. Reactivity Management Strategy Development And Application In Pressurized Water Reactor Nuclear Power Plant
64. Numerical Study On Coupling Of Flow And Heat Transfer Of Rod Bundle Channel In Pressurized Water Reactor
65. Study On Fuel Loading Pattern Optimization For A Pressurized Water Reactor Based On NSGA-Ⅱ And Machine Learning
66. Design And Development Of Digital Rod Control System And Rod Position Indication System In Third Generation Pressurized Water Reactor
67. Numerical Simulation And Experimental Study Of Hydraulic Performance Of Main Coolant Pump For 300MW Pressurized Water Reactor Nuclear Power Plant
68. The Research Of Primary Loop Model Of Advanced Pressurized Water Reactor Based On Modular Modeling
69. Nuclear Reactor Power Control Based On A New Type Control Rod Driving Mechanism
70. Dynamic Modeling Of Pressurized Water Reactor And Its Interaction With The Grid
71. Neutron Interrogation Of Uranium In Fuel Rods Of Pressurized Water Reactor(PWR) Using Common Neutron Sources In The GEANT4 Monte Carlo Code
72. The effects of boric acid on corrosion of steels in simulated pressurized water reactor primary coolant
73. Thorium-based mixed oxide fuel in a pressurized water reactor: A feasibility analysis with MCNP
74. Research On The Small Pressurized Water Reactor Using Accident Tolerant Fuel
75. Research On Coupled Multi-scale Thermal-Hydraulic And Coupled Neutronic/Thermal-Hydraulic Methodology For Integral PWR
76. Study On Flow-induced Vibration Of Control Rods In The Pressurized Water Reactor
77. Research On Linear Active Disturbance Rejection Control Method And Pressurized Water Reactor Power Control
78. Study On The Fission Gas Release Mechanism And Inverse Method In Pressurized Water Reactor
79. Numerical Study On Flow And Boiling Heat Transfer Characteristics In Rod Bundle Fuel Assembly Of Pressurized Water Reactor
80. Numerical Simulation Of Flow Boiling And Critical Heat Flux In A PWR Fuel Assembly
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