Chapter 8
Uncertainty Quantification of Spray
Nozzle Fatigue Analysis Under Transient
Load
Zhenyu Liu, Lijuan Li, Liping Zhang, Hui Li, Xuejiao Shao, Lu Jiang,
and Ying Zhang
Abstract In this paper, the randomness concept of input parameters is introduced
into the design of nuclear equipment, and the uncertainty analysis of input parameters is carried out for fatigue analysis. Taking the pressurizer spray nozzle as the
research object, considering the random fluctuation of temperature and pressure of
the transient load, the reliability and distribution of the fatigue usage are obtained
by performing fatigue analysis according to the fatigue analysis method of nuclear
power equipment with Monte Carlo sampling method. Taking section No.3 as an
example, the thermal analysis and stress analysis models are established. Through
the parameter sensitivity analysis, the relative sensitivity of the fatigue usage to
each input parameter is obtained. From the results, it is clear which parameters have
a significant impact on the results. The results can further optimize the structural
design of the nuclear power equipment and improve its fatigue resistance, which has
great application value to the life extension of nuclear power equipment.
Keywords Uncertainty quantification · Nuclear equipment · Parameter
sensitivity · Fatigue reliability · Reactor structural mechanics
8.1 Introduction
The main structures of the nuclear power equipment are very complicated, which
are subjected to the fluctuating load from various transient conditions during the
service life thus generating alternating stress. Damage occurs at one or some high
stress areas and then accumulates, resulting in performance degradation, crack initiation, expansion until complete fracture. As a result, fatigue damage occurs, causing
serious accidents. Due to severe safety requirements, the effects of these loads must
be fully considered in the reactor design, because fatigue damage can occur even
when the stress is much less than the yield strength of the material [1]. However,
Z. Liu (B) · L. Li · L. Zhang · H. Li · X. Shao · L. Jiang · Y. Zhang
Science and Technology On Reactor System Design Technology Laboratory, Nuclear Power
Institute of China, No. 328 Changshun Avenue, Chengdu 610200, Sichuan, P. R. China
e-mail: zhenyuliuchn@foxmail.com
© The Author(s), under exclusive license to Springer Nature Switzerland AG 2021
J. Xu and K. M. Pandey (eds.), Mechanical Engineering and Materials,
Mechanisms and Machine Science 100,
https://doi.org/10.1007/978-3-030-68303-0_8
91
Uncertainty Quantification of Spray
Nozzle Fatigue Analysis Under Transient
Load
Zhenyu Liu, Lijuan Li, Liping Zhang, Hui Li, Xuejiao Shao, Lu Jiang,
and Ying Zhang
Abstract In this paper, the randomness concept of input parameters is introduced
into the design of nuclear equipment, and the uncertainty analysis of input parameters is carried out for fatigue analysis. Taking the pressurizer spray nozzle as the
research object, considering the random fluctuation of temperature and pressure of
the transient load, the reliability and distribution of the fatigue usage are obtained
by performing fatigue analysis according to the fatigue analysis method of nuclear
power equipment with Monte Carlo sampling method. Taking section No.3 as an
example, the thermal analysis and stress analysis models are established. Through
the parameter sensitivity analysis, the relative sensitivity of the fatigue usage to
each input parameter is obtained. From the results, it is clear which parameters have
a significant impact on the results. The results can further optimize the structural
design of the nuclear power equipment and improve its fatigue resistance, which has
great application value to the life extension of nuclear power equipment.
Keywords Uncertainty quantification · Nuclear equipment · Parameter
sensitivity · Fatigue reliability · Reactor structural mechanics
8.1 Introduction
The main structures of the nuclear power equipment are very complicated, which
are subjected to the fluctuating load from various transient conditions during the
service life thus generating alternating stress. Damage occurs at one or some high
stress areas and then accumulates, resulting in performance degradation, crack initiation, expansion until complete fracture. As a result, fatigue damage occurs, causing
serious accidents. Due to severe safety requirements, the effects of these loads must
be fully considered in the reactor design, because fatigue damage can occur even
when the stress is much less than the yield strength of the material [1]. However,
Z. Liu (B) · L. Li · L. Zhang · H. Li · X. Shao · L. Jiang · Y. Zhang
Science and Technology On Reactor System Design Technology Laboratory, Nuclear Power
Institute of China, No. 328 Changshun Avenue, Chengdu 610200, Sichuan, P. R. China
e-mail: zhenyuliuchn@foxmail.com
© The Author(s), under exclusive license to Springer Nature Switzerland AG 2021
J. Xu and K. M. Pandey (eds.), Mechanical Engineering and Materials,
Mechanisms and Machine Science 100,
https://doi.org/10.1007/978-3-030-68303-0_8
91