Probabilistic seismic risk analysis of CANDU containment structure for near-fault earthquakes

Choi, In-Kil; Choun, Young-Sun; Ahn, Seong-Moon; Seo, Jeong-Moon

doi:10.1016/j.nucengdes.2007.11.001

Cited by 61 publications

(10 citation statements)

References 5 publications

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“…For our case, the first frequency for the CW obtained from the ambient vibration measurements is around 4.2 Hz. This value is in accordance with the results reported by Choi et al (2008).…”

Section: Ambient Vibration Measurement and Calibration Of The Finite supporting

confidence: 94%

“…For this CANDU (Wolsung Unit 2), Choi et al (2008) provided results of the free vibration analyses of the CW based on the nominal elastic values, and the first frequency is around 3.8 Hz. It is not obvious to understand the difference between the actual frequency from tests (8.09 Hz) and the one obtained from design data (3.8 Hz).…”

Section: Ambient Vibration Measurement and Calibration Of The Finite mentioning

confidence: 99%

“…For structures similar to the containment wall, recent studies conducted on the other CANDU NPP (Park et al, 1998;Lee and Song, 1999;Choi et al, 2008) showed that the most critical failure mode corresponds to the tangential shear at the base. It is found that this failure mode is governing as well, for the containment wall of the CANDU 6 reactor building in this case study (see Fig.…”

Section: Seismic Evaluation Of the Reactor Building Capacitymentioning

confidence: 99%

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Probabilistic seismic safety assessment of a CANDU 6 nuclear power plant including ambient vibration tests: Case study

Nour

Cherfaoui

Gocevski

et al. 2016

Nuclear Engineering and Design

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“…For our case, the first frequency for the CW obtained from the ambient vibration measurements is around 4.2 Hz. This value is in accordance with the results reported by Choi et al (2008).…”

Section: Ambient Vibration Measurement and Calibration Of The Finite supporting

confidence: 94%

Section: Ambient Vibration Measurement and Calibration Of The Finite mentioning

confidence: 99%

Section: Seismic Evaluation Of the Reactor Building Capacitymentioning

confidence: 99%

See 1 more Smart Citation

Probabilistic seismic safety assessment of a CANDU 6 nuclear power plant including ambient vibration tests: Case study

Nour

Cherfaoui

Gocevski

et al. 2016

Nuclear Engineering and Design

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“…These models will later be used in subsequent chapters to compare with the new damage model for concrete. The third part of this chapter presents the distinct characteristics of near-fault motions in comparison to far-fault ones: pulse-type, long pulse-type period [43][44][45], high energy at the onset of records [51,52], high peak ground acceleration [55], intense velocity [45,55,56], and large displacements (fling-step) [57,58]. This is followed by a number of models of near-fault ground motions.…”

Section: Discussionmentioning

confidence: 98%

“…Northridge 1994, Kobe 1995, Chi-Chi 1999 [51,52]. This high input energy leads to different responses of structures when subjected to near-fault motions compared to the far-fault records.…”

Section: Characteristics Of Near-fault Earthquakesmentioning

confidence: 99%

Seismic damage assessment and FRP retrofit of reinforced concrete structures

Cao¹

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Only a small percentage of existing buildings around the world have been designed and constructed based on modern seismic codes. Majority of these buildings were designed and built based on older codes and thus are now identified as potentially hazardous due to more stringent seismic requirements of newer seismic standards. Consequently, these structures are vulnerable to earthquakes as has become evident in the recent earthquake events. Mitigating the seismic hazards for these deficient structures, instead of replacement, has been increasingly looked at by the engineering community due to obvious economic reasons.An important first step towards this mitigation is called "Damage Assessment". Damage Assessment by definition is the evaluation of potential damage in a particular structure in a seismic event. There exist many indices such as drift based on which the extent of potential damage in a building can be described. Choosing the right index and understanding how a particular index would correlate with the seismic parameters or how sensitive it would be to a particular seismic event is quite important. Many structures, for example, are structurally sound under far fault earthquakes but may suffer from extensive damage if a near fault earthquake occurs.While many studies have been undertaken in the past towards methods of analysis that best simulate the damage and on the development of indices that better represent it, the efforts are isolated and in some instances contradictory. The current study thus attempts to address the gaps in the state of the art and presents a coherent and consistent understanding of the issue together with the introduction of a couple of damage mitigation methods.The main achievements of this thesis are as follows:A simplified model for inelastic analysis of RC structures subjected to earthquakes is developed.A new damage model that appropriately assesses the damage of RC structures is proposed. This new damage model is based on the single parameter of energy which naturally overrides and implicitly incorporates a number of parameters such as force, deformation and number of cycles.Damage assessment in RC structures using the new damage model is performed.Correlation between seismic parameters and damage indices of structures is investigated.A new definition for near-fault earthquakes is developed and regions with different damage potential are established.

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Method for evaluation of concrete containment structure subjected to earthquake excitation and internal pressure increase

Huang

Kwon

Bentz

et al. 2018

Earthq Engng Struct Dyn

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Summary This study evaluates capabilities of the VecTor4 computer program to assess the seismic performance of a concrete containment structure subjected to both design‐basis and beyond design‐basis earthquakes. Based on a detailed nonlinear finite element model of the nuclear power plant containment structure, the seismic performance in terms of stress and strain distributions, cracks, yielding of reinforcement bars and tendons, as well as overall failure mechanism, is thoroughly reviewed. In addition, the post‐seismic performance of the containment structure subjected to a subsequent pressure increase is also investigated. Consideration is also given to the time‐dependent parameters of creep, shrinkage, and relaxation of prestressing tendons. It is found that the time‐dependent parameters and earthquake have a non‐negligible impact on pressure‐induced structural performance but that this impact can be predicted for a given earthquake. The proposed method is useful for assessing the progressive failure behaviour of containment structure under chain events.

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Probabilistic seismic risk analysis of CANDU containment structure for near-fault earthquakes

Cited by 61 publications

References 5 publications

Probabilistic seismic safety assessment of a CANDU 6 nuclear power plant including ambient vibration tests: Case study

Probabilistic seismic safety assessment of a CANDU 6 nuclear power plant including ambient vibration tests: Case study

Seismic damage assessment and FRP retrofit of reinforced concrete structures

Method for evaluation of concrete containment structure subjected to earthquake excitation and internal pressure increase

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