A Correlation-Based Feature Selection Algorithm for Operating Data of Nuclear Power Plants

Table 1

Original data.

Number	Condition	Initial condition	Criteria	Sample size
1	50% power	—	—	900
2	75% power	—	—	900
3	100% power	—	—	900
4	Loss of coolant accident (hot leg)	100% power	2/10/100 cm^2	300/300/300
5	Loss of coolant accident (cold leg)	100% power	2/10/100 cm^2	300/300/300
6	Steam generator A tube rupture	100% power	0.5/1/2 (^∗100%)	300/300/300
7	Steam generator B tube rupture	100% power	0.5/1/2 (^∗100%)	300/300/300
8	Steam line break inside containment	100% power	25/50/75 cm^2	300/300/300
9	Steam line break outside containment	100% power	25/50/75 cm^2	300/300/300
10	Loss of flow (locked rotor)	50%/75%/100% power	—	300/300/300
11	Turbine trip	50%/75%/100% power	—	300/300/300
12	Loss of feedwater accident	50%/75%/100% power	—	300/300/300
Total				10800