Research Article

Prediction of Automatic Scram during Abnormal Conditions of Nuclear Power Plants Based on Long Short-Term Memory (LSTM) and Dropout

Table 1

The monitoring parameters used in the training and testing of the proposed prediction model.

No.ParametersUnit

V01Coolant flow rate of loop 1kg/s
V02Coolant flow rate of loop 2kg/s
V03Hot leg coolant temperature of loop 1°C
V04Hot leg coolant temperature of loop 2°C
V05Cold leg coolant temperature of loop 1°C
V06Cold leg coolant temperature of loop 2°C
V07Steam generator pressure of loop 1MPa
V08Steam generator pressure of loop 2MPa
V09Steam generator narrow range water level of loop 1m
V10Steam generator narrow range water level of loop 2m
V11Steam generator feed water flow rate of loop 1kg/s
V12Steam generator feed water flow rate of loop 2kg/s
V13Main feed water temperature of the steam generator 1°C
V14Main feed water temperature of the steam generator 2°C
V15Steam generator outlet steam flow rate of loop 1kg/s
V16Steam generator outlet steam flow rate of loop 2kg/s
V17Steam generator outlet steam temperature of loop 1°C
V18Steam generator outlet steam temperature of loop 2°C
V19Pressurizer pressureMPa
V20Pressurizer water levelm
V21Pressurizer steam temperature°C
V22Pressurizer water temperature°C