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다지점 진동대를 이용한 원자력발전소 배관계통의 내진 성능실험

Seismic Capacity Test of Nuclear Piping System using Multi-platform Shake Table

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10

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참고문헌

키워드

주제분류토목공학

초록

In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress(138 MPa) of the piping system even under the maximum excitation level of this test.

Abstract

In this study, dynamic characteristics and seismic capacity of the nuclear power plant piping system are evaluated by model test results using multi-platform shake table. The model is 21.2 m long and consists of straight pipes, elbows, and reducers. The stainless steel pipe diameters are 60.3 mm (2 in.) and 88.9 mm (3 in.) and the system was assembled in accordance with ASME code criteria. The dynamic characteristics such as natural frequency, damping and acceleration responses of the piping system were estimated using the measured acceleration, displacement and strain data. The natural frequencies of the specimen were not changed significantly before and after the testing and the failure and leakage of the piping system was not observed until the final excitation. The damping ratio was estimated in the range of 3.13 ~ 4.98 % and it is found that the allowable stress(345 MPa) according to ASME criteria is 2.5 times larger than the measured maximum stress(138 MPa) of the piping system even under the maximum excitation level of this test.

참고문헌 (16)

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  6. Cheung JH, "KOCED Seismic Simulation Test Center", Journal of the Korean Society of Civil Engineers, 57(8), pp.43~49 (2009)
  7. ASME B, "Pressure Vessel Code SectionⅪ", American Society of Mechanical Engineer, ~ (2007)
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  9. "MTS STEX Manual", University at Buffalo Job No. US1.17858, EQT, ~
  10. Seismic Analysis of Large-Scale Piping Systems for the JNES-NUPEC Ultimate Strength Piping Test Program, "DeGrassi G", NUREG, ~, pp.NUREG, CR-6983, BNL-NUREG-81548-2008
  11. ASCE Standard, "Seismic Analysis of Safety-Related Nuclear Structure and Commentary. ASCE 4-98", American Society of civil Engineers, ~ (1999)
  12. ASCE, "Seismic Analysis of Safety-Related Nuclear Structures and Commentary", ASCE Standard 4-98, ~ (1999)
  13. 조성국, "진동수준이 원자력발전소 전기 캐비닛의 동특성에 미치는 영향", 한국지진공학회논문집, 14(3), pp.23~30 (2010), 한국지진공학회
  14. 조성국, "가진기를 이용한 강제진동시험에 의한 전기 캐비닛의 실험적 모드특성 분석", 한국지진공학회논문집, 15(6), pp.11~18 (2011), 한국지진공학회
  15. "ASME CODE Section Ⅲ", DivisionⅠ, Subsection NB. ASME standard, ~ (2007)
  16. Chio SJ, "Loading Experiments of the damaged TP 316 Stainless Pipe", KSCE Conference of the Civil Engineering society of Korea, pp.69~72 (2011)

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