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http://dx.doi.org/10.7734/COSEIK.2015.28.5.523

The Structural Integrity Test for a PSC Containment with Unbonded Tendons and Numerical Analysis I  

Noh, Sanghoon (Central Rearch Institute, Korea Hydro and Nuclear Power Co. LTD.)
Jung, Raeyoung (Structural Systems and Site Evaluation Dept., Korea Institute of Nuclear Safety)
Kim, Sung-Taek (Central Rearch Institute, Korea Hydro and Nuclear Power Co. LTD.)
Lim, Sang-Jun (Central Rearch Institute, Korea Hydro and Nuclear Power Co. LTD.)
Publication Information
Journal of the Computational Structural Engineering Institute of Korea / v.28, no.5, 2015 , pp. 523-533 More about this Journal
Abstract
A reactor containment acts as a final barrier to prevent leakage of radioactive material due to the possible reactor accidents into external environment. Because of the functional importance of the containment building, the SIT(Structural Integrity Test) for containments shall be performed to evaluate the structural acceptability and demonstrate the quality of construction. An initial numerical analysis was performed to simulate the results obtained from the SIT for a prestressed concrete(PSC) structure. But the analysis results by the initial model expected smaller displacements than the measured ones by 30% at some locations. Accordingly, the research and development to improve the initial model to corelate the measured results of the SIT more properly have been performed. In this paper, the effects of the loss of concrete due to duct for tendons and the contact of duct and tendons in un-bonded tendon system are mainly evaluated based on the preliminary analysis results. In addition, the importances of the proper definition of mesh connectivity among structural elements of concrete, liner plates, rebars and tendons are discussed.
Keywords
tendon; containment structure; prestressed concrete; structural integrity; internal pressure;
Citations & Related Records
Times Cited By KSCI : 1  (Citation Analysis)
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1 ACI-ASME Joint Technical Committee (1998) Code for Concrete Containments, ASME Boiler and Pressure Vessel Code, Section III, Division 2, American Society of Mechanical Engineers, New York.
2 Jung, R.Y., Cho, H.I., Ahn, S.M. (2013) The Structural Integrity Test for the Shin-Kori Unit 3 Containment and Acceptance Criteria, Transactions, SMiRT-22 Division VI.
3 KHNP TR (2013) Structural Integrity Test Report_Shin Kori 3, Korea Hydro and Nuclear Power Co. Ltd.
4 Kim, C., Pekka, V (2013) Simulation of PCCV with Grouted or Non-grouted Tendons, Transactions, SMiRT-22 Division V.
5 Noh, S.H., Jung, R.Y., Lee, B.S., Lim, S.J. (2015) The Structural Integrity Test for a PSC Containment with Unbonded Tendons and Numerical Analysis II, J. Comput. Struct. Eng. Inst. Korea, 28(5), pp.535-542.   DOI