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51. A Theoretical Critical Heat Flux Model for Rod Bundles Under Pressurized Water Reactor Conditions

52. Evaluations and Modifications of the EPRI-1 Correlation on PWR Critical Heat Flux Predictions Under Normal and Abnormal Fuel Conditions

53. Authors

54. An Improved Theoretical Critical Heat Flux Model for Low-Quality Flow

55. Identification of Two-Phase Flow Regimes by Neutron Noise Analysis

56. Identification of Two-Phase Flow Regimes by an Optimum Modeling Method

57. Identification of Two-Phase Flow Patterns by a Single Void Fraction Sensor

58. Reducing Scram Frequency by Relaxing Reactor Trip Setpoints at Maanshan Nuclear Power Station

59. Authors

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