Although acceleration and cumulative absolute velocity (CAV) are used as seismic indexes, their relationship with the damage mechanism is not yet understood. In this paper, a simplified evaluation method for seismic fatigue damage, which can be used as a seismic index for screening, is derived from the stress amplitude obtained from CAV for one cycle in accordance with the velocity criterion in ASME Operation and Maintenance of Nuclear Power Plants 2012, and the linear cumulative damage due to fatigue can be obtained from the linear cumulative damage rule. To verify the performance of the method, the vibration response of a cantilever pipe is calculated for four earthquake waves, and the cumulative fatigue damage is evaluated using the rain flow method. The result is in good agreement with the value obtained by the method based on the relative response. When the response spectrum obtained by the evaluation method is considered, the value obtained by the evaluation method has a peak at the peak frequency of the ground motion, and the value decreases with increasing natural frequency above the peak frequency. A higher peak frequency of the base leads to a higher value obtained by the evaluation method.
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April 2019
Research-Article
Evaluation Method for Seismic Fatigue Damage of Plant Pipeline
Fumio Inada,
Fumio Inada
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
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Michiya Sakai,
Michiya Sakai
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
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Ryo Morita,
Ryo Morita
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
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Ichiro Tamura,
Ichiro Tamura
The Chugoku Electric Power Co.,
4-33, Komachi, Naka-ku, Hirosima-shi,
Hiroshima 730-8701, Japan
4-33, Komachi, Naka-ku, Hirosima-shi,
Hiroshima 730-8701, Japan
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Shin-ichi Matsuura,
Shin-ichi Matsuura
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
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Kiyoshi Saito,
Kiyoshi Saito
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan.
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan.
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Yasuki Ohtori
Yasuki Ohtori
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1-6-1, Otemachi, Chiyoda-ku,
Tokyo 100-8126, Japan
Central Research Institute of
Electric Power Industry,
1-6-1, Otemachi, Chiyoda-ku,
Tokyo 100-8126, Japan
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Fumio Inada
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Michiya Sakai
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Ryo Morita
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Central Research Institute of
Electric Power Industry,
2-6-1, Nagasaka,
Yokosuka-shi 240-0196, Kanagawa, Japan
Ichiro Tamura
The Chugoku Electric Power Co.,
4-33, Komachi, Naka-ku, Hirosima-shi,
Hiroshima 730-8701, Japan
4-33, Komachi, Naka-ku, Hirosima-shi,
Hiroshima 730-8701, Japan
Shin-ichi Matsuura
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan
Kiyoshi Saito
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan.
Central Research Institute of
Electric Power Industry,
1646, Abiko,
Abiko-shi 270-1194, Chiba, Japan.
Yasuki Ohtori
Nuclear Risk Research Center,
Central Research Institute of
Electric Power Industry,
1-6-1, Otemachi, Chiyoda-ku,
Tokyo 100-8126, Japan
Central Research Institute of
Electric Power Industry,
1-6-1, Otemachi, Chiyoda-ku,
Tokyo 100-8126, Japan
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received April 24, 2018; final manuscript received December 6, 2018; published online February 21, 2019. Assoc. Editor: Oreste S. Bursi.
J. Pressure Vessel Technol. Apr 2019, 141(2): 021801 (9 pages)
Published Online: February 21, 2019
Article history
Received:
April 24, 2018
Revised:
December 6, 2018
Citation
Inada, F., Sakai, M., Morita, R., Tamura, I., Matsuura, S., Saito, K., and Ohtori, Y. (February 21, 2019). "Evaluation Method for Seismic Fatigue Damage of Plant Pipeline." ASME. J. Pressure Vessel Technol. April 2019; 141(2): 021801. https://doi.org/10.1115/1.4042220
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