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원윤호(Youn-Ho Won),최병화(Byoung-Hwa Choi),전창빈(Chang-Been Jeon),박문백(Mun-Baek Park) 한국소음진동공학회 2016 한국소음진동공학회 학술대회논문집 Vol.2016 No.4
Integrity verification test of piping system in nuclear power plant also referred to as Piping Verification Test is a series of tests performed to verify integrity of piping system by checking movement of piping system to ensure it behaves as designed during hot functional and power ascension tests in initial tests. In other words, piping verification test verifies adequacy of safety-related and important piping systems by confirming compliance of installed condition of the piping and pipe supports with design, and by checking measured pipe movement due to vibration and thermal expansion against allowable design limits to ensure they are acceptable. Based on the experiences accumulated through technical support for the piping verification tests of Korea domestic nuclear power plants, this paper presents key point summary of the regulatory requirements and basis for the tests, piping systems to be tested, thermal expansion and vibration test procedures, and applicable Codes.
다중지지된 배관계통의 내진해석에 적용된 MIRS 방법의 Parametric Study
김대수(DAE SOO KIM),김수겸(SOO KYUM KIM),원윤호(YOUN HO WON),이대건(DAE GEON LEE),박문백(MUN BACK PARK) 한국소음진동공학회 2015 한국소음진동공학회 학술대회논문집 Vol.2015 No.4
The steam supply piping connected to the high pressure(HP) turbine of APR1400 (Korea’s advanced power plant 1400 MW-class) is a typical example of multi-supported piping system, and it is routed from the Containment building to the Turbine building via the Main Steam Isolation Valve House in the Auxiliary building. In the seismic analysis of this piping system, using the Enveloped Response Spectrum (ERS) method, a commonly used methodology for seismic analysis of piping systems in the nuclear industry, generates overly conservative analysis results. Therefore, Time History Method (THM) which applies excitation characteristic of each support attached to individual building was used to eliminate unnecessary conservatism. However, it was noticed that the Time History Method requires considerable amount of labor and time in generating combined time history equivalent to the spectrum applied for each support although it is regarded as the most exact and realistic method for seismic analysis. The nuclear industry has been making lots of efforts in finding out the mathematic logicality and practical applicability to resolve this issue. This paper deals with parametric research on combination effects of responses between support groups, damping effects, and modal combination method with close modes in applying the Multiple Input Response Spectrum (Independent Support Motion: ISM) method to the analysis model of the steam supply piping connected to the high pressure turbine of APR1400. Quantitative assessment and comparison with the analysis results of the ERS method and THM were also carried out. As a result, it is shown that the analysis results of the MIRS method together with the SRSS combination between support groups, 4% damping with ±15% spectrum peak broadening and grouping of modal combination are remarkably similar to those of THM.