Transactions of the Korean Society of Pressure Vessels and Piping (한국압력기기공학회 논문집)

Korean Society of Pressure Vessels and Piping (한국압력기기공학회)
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Study on Selection of Nuclear Seismic Fragile Equipment and Its Enhancement of Seismic Performance

주요기기 내진성능 상향을 위한 설비보강 및 취약부 도출연구

  • Received : 2018.10.10
  • Accepted : 2018.11.17
  • Published : 2018.12.30
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Abstract

In order to investigate the ways to enhance the seismic performance of APR1400 seismic fragile equipment by direct design changes, four equipment such as Reactor Vessel Support, Integrated Head Assembly, Remote Shutdown Console, and Pressurizer are reviewed using information of the main dimensions, seismic stress evaluation results, design FRS, etc. in this paper. In addition to the direct reinforcement of equipments, the feasibility of seismic isolation for the safety related cabinet is also investigated and the actual adaption plan of a commercial spring-damper system is briefly reviewed.

Keywords

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Fig. 1 Nuclear Steam Supply System

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Fig. 2 Reactor Vessel Support

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Fig. 3 Integrated Head Assembly

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Fig. 4 Remote Shutdown Console

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Fig. 5 Stress for Safe Shutdown Earthquake

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Fig. 6 Displacement for Safe Shutdown Earthquake

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Fig. 7 Result of RSC Functionality Evaluation(Forward to Backward Direction)

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Fig. 8 Result of RSC Functionality Evaluation(Left to Right Direction)

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Fig. 9 Concept of RSC with Isolation Device

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Fig. 10 Pressurizer

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Fig. 11 Cut Position of Bottom Head & Support Skirt

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Fig. 12 Cut Position of Spray Nozzle

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Fig. 13 Cabinet Door Reinforcement (Before / After)

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Fig. 14 Header Box Reinforcement (Before / After)

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Fig. 15 Cabinet-Base Bolt Reinforcement (Before / After)

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Fig. 16 Triangular Stiffener Reinforcement (Before /After)

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Fig. 17 Rectangular Steel Pipe Reinforcement (After)

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Fig. 18 Effect of Natural Frequency and Damping Coefficient

Table 1 Design Code & Limit Factor

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Table 2 Stress Margin for RV Support

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Table 3 Stress Margin for IHA

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Table 4 Stress Margin for Bottom Head & Support Skirt

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Table 4 Stress Margin for Spray Nozzle

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References

  1. IEEE 323, 2003,"Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations," IEEE.
  2. IEEE 344, 2004,"Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations," IEEE.
  3. IEEE 382, 2006,"Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations," IEEE.
  4. IEEE 649, 2006,"Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations," IEEE.
  5. IEEE Std. C37.98, 2013, "Standard For Seismic Testing of Relays," IEEE.
  6. Nawrotzi, P. and Siepe, D., 2014, "Structural Challenges of Power Plants in High Seismic Areas", Second European Conference on Earthquake Engineering and Seismology, Istanbul, Aug. 25-29.