Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure

Hu, Hsuan Teh; Lin, Yu Hon

doi:10.1016/j.ijpvp.2006.02.030

Cited by 39 publications

(9 citation statements)

References 12 publications

(11 reference statements)

Supporting

Mentioning

Contrasting

Order By: Relevance

“…In previous research, the results of [11] showed material nonlinearity would have an effect on the displacement of the PCCV when the internal pressure was beyond 0.886 MPa. According to the results in [15], the radial displacement, the tendon strain and concrete strain changed a little from the pressure 0 MPa to 0.585 MPa.…”

Section: Methodsmentioning

confidence: 92%

Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

Liao

Kong

et al. 2017

Applied Sciences

View full text Add to dashboard Cite

Abstract:As the last barrier of nuclear reactor, prestressed concrete containment vessels (PCCVs) play an important role in nuclear power plants (NPPs). To test the mechanical property of PCCV during the integrated leakage rate testing (ILRT), a fiber Bragg grating (FBG) sensor was used to monitor concrete strain. In addition, a finite element method (FEM) model was built to simulate the progress of the ILRT. The results showed that the strain monitored by FBG had the same trend compared to the inner pressure variation. The calculation results showed a similar trend compared with the monitoring results and provided much information about the locations in which the strain sensors should be installed. Therefore, it is confirmed that FBG sensors and FEM simulation are very useful in PCCV structure monitoring.

show abstract

Section: Methodsmentioning

confidence: 92%

Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

Liao

Kong

et al. 2017

Applied Sciences

View full text Add to dashboard Cite

show abstract

“…The PWR has a height of 85.8m, wall thickness of 1.5m and is partially embedded in the supporting ground. The reinforcement of the containment is composed of ∅40 mm bars at 80mm spacing, running both ways at the inner and outer faces of the cylindrical R/C wall, continuing within the spherical dome with an assumed effective concrete cover of 100mm (Hu and Lin, 2006). Material properties are summarized in (Hu and Liang, 2000) as well as in Table 1 and they are defined within the elastic region on the basis of the envisaged linear elastic response performance objective of the containment building.…”

Section: Overview Of the Npp Studiedmentioning

confidence: 99%

Seismically induced uplift effects on nuclear power plants. Part 1: Containment building rocking spectra

Sextos

Manolis

Athanasiou

et al. 2017

Nuclear Engineering and Design

View full text Add to dashboard Cite

General rightsThis document is made available in accordance with publisher policies. Please cite only the published version using the reference above. focusing primarily on the response of the containment structure of a nuclear power plant.However, in current state-of-practice and in most seismic regulations worldwide, the consideration of soil-structure interaction and potential development of geometrically nonlinear effects, such as rocking and sliding with uplift, is not taken into consideration. To explore this issue, a refined 3Dfinite element model of a typical nuclear power plant containment structure is developed, comprising solid elements for the soil and foundation, plus shell elements for the structure. The aim is identification of foundation-soil separation phenomena under a suite of ground motions with distinct frequency content. At first, harmonic excitations are used, for both cases of stiff sand and rock subsoil profiles, leading to rocking spectra that depict the displacement demand in connection with nonlinear separation. Clear influence zones can be distinguished, especially in the low frequency bands for the stiff sand case. Next, three subsets of 30 ground motion records are carefully selected and grouped in ensembles according to their frequency content, normalized to a PGA of 0.36g, which corresponds to the highest design acceleration in Europe. Ground motions with low mean frequency content are observed to lead to the onset of geometrically nonlinear phenomena, along with a higher displacement demand. The interplay between ground motion characteristics, dynamic properties of the containment structure and stiffness of the soil is also highlighted. More specifically, it is shown that stiff containment structures on soft soils are more prone to foundation uplift. This possibility is often neglected in design codes and the consequence is that under certain circumstances, damage may be caused to the internal power generation equipment..

show abstract

“…Another field where prestressing techniques are used is in the study of nuclear containments. For instance, Hu and Lin [13] conducted an analytical study also using ABAQUS finite element program to predict the ultimate pressure capacity of the PWR (Pressure Water Reactor) prestressed concrete containment at Maanshan nuclear power plant. The prestressing tendons and reinforcing steel were modelled as uni-axial materials that are smeared through the element section.…”

Section: Introduction and State Of The Artmentioning

confidence: 99%

Methodology for the analysis of post-tensioned structures using a constitutive serial-parallel rule of mixtures

Cornejo

Barbu

Escudero

et al. 2018

Composite Structures

View full text Add to dashboard Cite

The main purpose of this paper is to develop a reliable method based on a three-dimensional (3D) finiteelement (FE) model to simulate the constitutive behaviour of reinforced concrete structures strengthened with post-tensioned tendons taking into account the reduction of the pre-stressing stress due to the steel relaxation. The pre-tensioned concrete is modelled as a composite material whose behaviour is described with the serial-parallel rule of mixtures (S/P RoM) [1-3] whereas the stress relaxation of the steel is simulated using a viscoelastic model called Generalized Maxwell. A 3D FE model was used, where the nonlinear material behaviour and geometrical analysis based on incremental-iterative load methods were adopted. Validation by comparison with the analytic solution will be done for the case of a concrete beam with a parabolic pre-tensioned steel tendon embedded and some viscoelastic cases are performed in order to perceive the behaviour of the Generalized Maxwell model. Several examples are shown where the capabilities of the method on large scale structures are exhibited.

show abstract

Ultimate analysis of PWR prestressed concrete containment subjected to internal pressure

Cited by 39 publications

References 12 publications

Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

Seismically induced uplift effects on nuclear power plants. Part 1: Containment building rocking spectra

Methodology for the analysis of post-tensioned structures using a constitutive serial-parallel rule of mixtures

Contact Info

Product

Resources

About