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Research Papers: Materials and Fabrication

Development of Fatigue Crack Growth Prediction Model in Reactor Coolant Environment

[+] Author and Article Information
Terushi Ishizawa

Division of Sustainable Energy
and Environmental Engineering,
Osaka University,
2-1, Yamadaoka, Suita,
Osaka 565-0871, Japan
e-mail: t-ishizawa@ne.see.eng.osaka-u.ac.jp

Satoshi Takeda

Division of Sustainable Energy
and Environmental Engineering,
Osaka University,
2-1, Yamadaoka, Suita,
Osaka 565-0871, Japan
e-mail: takeda@see.eng.osaka-u.ac.jp

Takanori Kitada

Division of Sustainable Energy
and Environmental Engineering,
Osaka University,
2-1, Yamadaoka, Suita,
Osaka 565-0871, Japan
e-mail: kitada@see.eng.osaka-u.ac.jp

Takao Nakamura

Division of Sustainable Energy
and Environmental Engineering,
Osaka University,
2-1, Yamadaoka, Suita,
Osaka 565-0871, Japan
e-mail: nakamura@see.eng.osaka-u.ac.jp

Masayuki Kamaya

Institute of Nuclear Safety System, Inc.,
64 Sata, Mihama-cho,
Fukui 919-1205, Japan
e-mail: kamaya@inss.co.jp

1Corresponding author.

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received March 25, 2017; final manuscript received April 19, 2018; published online May 21, 2018. Assoc. Editor: David L. Rudland.

J. Pressure Vessel Technol 140(4), 041402 (May 21, 2018) (8 pages) Paper No: PVT-17-1061; doi: 10.1115/1.4040095 History: Received March 25, 2017; Revised April 19, 2018

In order to conduct effective and rational maintenance activity of components in nuclear power plants, it is proposed to manage fatigue degradation based on crack size corresponding to an extent of cumulative fatigue effect. This study is aimed at developing a prediction model for fatigue crack growth in simulated reactor coolant environment. In order to investigate influence of reactor coolant environment on crack initiation and crack growth, two-step replica observations were conducted for environmental fatigue test specimens (type 316 stainless steel) subjected to three kinds of strain range. Crack initiation, growth, and coalescence were observed in the experiments. It is clarified that crack coalescence is one of the dominant factors causing fatigue life reduction, and fatigue life reduction depends on crack size and distance of two coalescing cracks. Then, a model was developed for predicting statistical crack initiation and growth behavior. The relationship between dispersion of crack initiation life and strain range was approximated by the Weibull model to predict crack initiation. Then, the statistical crack growth was modeled using the relation of crack growth rate and strain intensity factor. Furthermore, the crack coalescence was taken into account to the crack growth prediction considering the distance between two cracks. Finally, the crack growth curve, which is the relationship between crack size and operation period, was derived through Monte Carlo simulation with the developed model. The crack growth behavior and residual life in the simulated reactor coolant environment can be reviewed by the crack growth curve obtained with crack initiation, and the growth model developed was compared with the fatigue test results.

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References

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Figures

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Fig. 1

Geometry of hollow specimen (unit: mm)

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Fig. 2

Dispersion of crack initiation and growth (five samples of cracks, Δε = 1.2%)

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Fig. 3

Distribution of crack initiation life in reactor coolant environment

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Fig. 4

Crack coalescence observed in experiments: (a) crack coalescence at the location of each crack tip and (b) crack coalescence at the location of crack tip and other part

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Fig. 5

Crack length distribution of longer crack in precoalescence: (a) Δε = 1.2%, (b) Δε = 0.8%, and (c) Δε = 0.6%

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Fig. 6

Distribution of crack initiation life in Weibull distribution paper

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Fig. 7

Relationship between two parameters and strain range in Weibull analysis: (a) relationship between shape parameter strain range and (b) relationship between scale parameter strain range

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Fig. 8

Comparison of cumulative probability of crack initiation between Eqs. (2) and (3) and experimental results: (a) Δε = 1.2%, (b) Δε = 0.8%, and (c) Δε = 0.6%

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Fig. 9

Distribution of crack growth rate in reactor coolant environment

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Fig. 10

Distribution of crack growth rate without crack coalescence in lognormal probability paper

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Fig. 11

Dispersion of crack growth rate without crack coalescence

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Fig. 12

Definition of crack coalescence parameter

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Fig. 13

Relationship between H/c1 ratio and c2/c1 ratio

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Fig. 14

Algorithm to simulate crack growth behavior in reactor coolant environment

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Fig. 15

Analytical geometry to simulate crack growth behavior

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Fig. 16

Crack growth curves derived thorough simulation analysis: (a) comparison of Crack growth curve and fatigue test results (Δε = 1.2%), (b) comparison of Crack growth curve and fatigue test results (Δε = 0.8%), and (c) comparison of Crack growth curve and fatigue test results (Δε = 0.6%)

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