98
Z. Liu et al.
Table 8.3 The summary of correlation coefficient calculation
Transient Number
P3U_in
P3Sn1_in
P3Sn2_in
4
Temperature 1
0.00686
0.06615
−0.09945
Pressure
0.02431
0.02709
0.05680
Temperature 2
0.06089
0.00581
0.12589
7
Temperature 1
−0.00473
0.10689
−0.31247
Pressure
−0.00885
-0.04816
−0.03382
Temperature 2
0.33761
0.85050
0.44026
10
Temperature 1
−0.11815
-0.05421
0.22461
Pressure
0.00722
0.18774
−0.02298
Temperature 2
0.88492
0.23845
−0.13772
12
Temperature 1
−0.03692
-0.06088
0.01226
Pressure
0.02690
0.12920
−0.06825
Temperature 2
0.04568
0.16483
−0.14625
16
Temperature 1
−0.04783
0.02073
0.26300
Pressure
0.05657
0.12006
0.01626
Temperature 2
0.24098
0.11669
−0.10351
8.4 Conclusions
In this paper, the uncertainty is introduced into the transient load, and the uncertainty
quantification study of spray nozzle fatigue analysis is carried out. The results are as
follows:
(1) Based on the Optimus platform, this paper introduces the concept of uncertainty
quantification into the complete process of fatigue analysis and evaluation of
nuclear power equipment, establishes the fatigue strength reliability calculation process, and realizes the transition from the deterministic theory to the
fatigue probability evaluation of nuclear power equipment. The results of the
mechanical analysis are closer to the physical reality.
(2) This paper takes the pressurizer spray nozzle as the research object. The calculation results show that for the transient and cycle times of this paper, considering the fatigue design and ensuring the pressure bearing requirements, the
wall thickness of the section No. 3 should be appropriately thinned, which can
not only improve the economics of the structure, but also extend the life of the
equipment structure.
(3) In the design phase, the uncertainty quantification study of input parameters
can be used to further optimize the structure by considering the randomness of
the parameters more widely. The analysis method of this paper can be extended
to other equipment in the field of nuclear power, providing quantitative analysis
means and effective tools for the reliability of fatigue analysis.
Z. Liu et al.
Table 8.3 The summary of correlation coefficient calculation
Transient Number
P3U_in
P3Sn1_in
P3Sn2_in
4
Temperature 1
0.00686
0.06615
−0.09945
Pressure
0.02431
0.02709
0.05680
Temperature 2
0.06089
0.00581
0.12589
7
Temperature 1
−0.00473
0.10689
−0.31247
Pressure
−0.00885
-0.04816
−0.03382
Temperature 2
0.33761
0.85050
0.44026
10
Temperature 1
−0.11815
-0.05421
0.22461
Pressure
0.00722
0.18774
−0.02298
Temperature 2
0.88492
0.23845
−0.13772
12
Temperature 1
−0.03692
-0.06088
0.01226
Pressure
0.02690
0.12920
−0.06825
Temperature 2
0.04568
0.16483
−0.14625
16
Temperature 1
−0.04783
0.02073
0.26300
Pressure
0.05657
0.12006
0.01626
Temperature 2
0.24098
0.11669
−0.10351
8.4 Conclusions
In this paper, the uncertainty is introduced into the transient load, and the uncertainty
quantification study of spray nozzle fatigue analysis is carried out. The results are as
follows:
(1) Based on the Optimus platform, this paper introduces the concept of uncertainty
quantification into the complete process of fatigue analysis and evaluation of
nuclear power equipment, establishes the fatigue strength reliability calculation process, and realizes the transition from the deterministic theory to the
fatigue probability evaluation of nuclear power equipment. The results of the
mechanical analysis are closer to the physical reality.
(2) This paper takes the pressurizer spray nozzle as the research object. The calculation results show that for the transient and cycle times of this paper, considering the fatigue design and ensuring the pressure bearing requirements, the
wall thickness of the section No. 3 should be appropriately thinned, which can
not only improve the economics of the structure, but also extend the life of the
equipment structure.
(3) In the design phase, the uncertainty quantification study of input parameters
can be used to further optimize the structure by considering the randomness of
the parameters more widely. The analysis method of this paper can be extended
to other equipment in the field of nuclear power, providing quantitative analysis
means and effective tools for the reliability of fatigue analysis.