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Research Papers: Materials and Fabrication

Visualization of Thermal Fatigue Damage Distribution With Simplified Stress Range Calculations

[+] Author and Article Information
Junya Miura

Graduate School of Science and Engineering,
Course of Advanced Mechatronics Systems,
Toyo University,
2100 Kujirai,
Kawagoe 350-8585, Saitama, Japan
e-mail: s36a01700082@toyo.jp

Terutaka Fujioka

Mem. ASME
Faculty of Science and Engineering,
Department of Mechanical Engineering,
Toyo University,
2100 Kujirai,
Kawagoe 350-8585, Saitama, Japan
e-mail: fujioka@toyo.jp

Yasuhiro Shindo

Faculty of Science and Engineering,
Department of Mechanical Engineering,
Toyo University,
2100 Kujirai,
Kawagoe 350-8585, Saitama, Japan
e-mail: shindo060@toyo.jp

Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received November 9, 2017; final manuscript received July 11, 2018; published online November 12, 2018. Assoc. Editor: Oreste S. Bursi.

J. Pressure Vessel Technol 140(6), 061403 (Nov 12, 2018) (7 pages) Paper No: PVT-17-1225; doi: 10.1115/1.4041057 History: Received November 09, 2017; Revised July 11, 2018

This paper proposes simplified methods to evaluate fatigue damage in a component subjected to cyclic thermal loads to visualize damage distribution by using typical computer-aided engineering systems. The objective is to perform the evaluations on a standard desktop PC within a reasonably short computation time. Three simplified methods for defining elastic stress ranges are proposed in place of the method in the ASME Subsection NH procedures. A thermal fatigue test that was previously performed using a type-304 stainless steel (304SS) cylinder is simulated to validate the proposed methods. Heat transfer and elastic analyses are conducted. Simultaneously with the analyses, fatigue usage factors are calculated using user subroutines formulated in this study, including the three simplified methods and the ASME NH-based method. The calculated values of the fatigue usage factor are visualized using a graphical user interface (GUI) incorporated into a commercial finite-element analysis (FEA) code. The fatigue usage factor distribution obtained using the simplified methods could be calculated without requiring large amounts of memory and long computation time. In addition, the distribution of the fatigue usage factor was consistent with the distribution of cracks observed in the test.

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References

Ishizaki, K. , Watashi, K. , Takahashi, N. , and Iwata, K. , 1989, “ Thermal Fatigue Test of SUS 304,” Japan Atomic Energy Agency, Tokyo, Japan, PNC-TN9410 89-101, pp. 1–112 (in Japanese).
Ando, M. , Hasebe, S. , Kobayashi, S. , Kasahara, N. , Toyoshi, A. , Ohmae, T. , and Enuma, Y. , 2013, “ Thermal Transient Test and Strength Evaluation of a Thick Cylinder Model Made of Mod.9Cr-1Mo Steel,” Nucl. Eng. Des., 255, pp. 296–309. [CrossRef]
ASME, 2014, “ Class 1 Components in Elevated Temperature Service,” Boiler and Pressure Vessels Code, Section III, Division1 Subsection NH, American Society of Mechanical Engineers, New York.
MSC Software, 2018, “ MSC Software,” Newport Beach, CA, accessed Aug. 14, 2018, http://www.mscsoftware.com/
Sakon, T. , Wada, H. , and Asada, Y. , 1987, “ Procedures of Creep-Fatigue Life Evaluation Applied to Inelastic Design Analysis,” Nineth International Conference on Structural Mechanics in Reactor Technology (SMiRT-9), Lausanne, Switzerland, Aug. 17–21, pp. 267–272. https://inis.iaea.org/search/search.aspx?orig_q=RN:19044180
Fujioka, T. , 2014, “ Elastic-Route Estimation of Strain Range in Notched Components Under Thermal Loading Without Performing Stress Linearization,” ASME J. Pressure Vessel Technol., 137(2), p. 021205.
Ando, M. , Hirose, Y. , Karato, T. , Watanabe, S. , Inoue, O. , Kawasaki, N. , and Enuma, Y. , 2014, “ Comparison and Assessment of the Creep-Fatigue Evaluation Methods With Notched Specimen Made of Mod.9Cr-1Mo Steel,” ASME J. Pressure Vessel Technol., 136(4), p. 041406.
PNC (currently JAEA), 1985, “ Structural Design Guide for Class 1 Components of Prototype Fast Breeder Reactor for Elevated Temperature; Standards for Strength of Materials,” Japan Atomic Energy Agencty, Report No. PNC-TN241 85-08 (in Japanese).
Wada, Y. , Kawakami, Y. , and Aoto, K. , 1987, “ Statistical Approach to Fatigue Life Prediction for SUS304, 316 and 321 Austenitic Stainless Steels,” ASME Pressure Vessels Piping, 123, pp. 37–42.

Figures

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Fig. 1

Dimensions and configuration of specimen

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Fig. 2

Temperature histories at two evaluation points

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Fig. 3

Sodium temperature history at specimen inlet

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Fig. 5

FEA model and mechanical boundary conditions

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Fig. 6

Flowchart of stress range calculation using methods 1(a) and 2(b): (a) method 1 and (b) method 2

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Fig. 7

Results of heat transfer analysis compared with measured temperatures [1]

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Fig. 8

Temperature distribution at 120 s after start of rapid heating

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Fig. 9

Stress histories on inner surface at point of maximum thickness: (a) rapid heating and (b) rapid cooling

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Fig. 10

Distribution of equivalent of von Mises stress at 80 s after start of rapid heating

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Fig. 11

Distribution of elastic stress range calculated using three proposed simplified methods: (a) method 1, (b) method 2, and (c) method 3

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Fig. 12

Comparison between crack observations [1] and present elastic analysis results

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Fig. 13

Distributions of fatigue usage factors calculated using four methods: (a) ASME NH-based method, (b) method 1, (c) method 2, and (d) method 3

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Fig. 14

Comparison between crack observations [1] and calculated fatigue usage factor

Tables

Errata

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