Contribution to the Design of Concrete Columns Reinforced With Externally Fiber Polymers

2009 ◽  
Author(s):  
Ferran Prats Bella ◽  
Ramo´n Gonza´lez-Drigo ◽  
Adrina Bachiller San˜a
Keyword(s):  
Structural Design ◽  
Nuclear Power ◽  
Power Plants ◽  
Pushover Analysis ◽  
Concrete Columns ◽  
Seismic Evaluation ◽  
Modal Pushover Analysis ◽  
Nuclear Domain ◽  
Concrete Building ◽  
The Subject

In the design of seismic category 1 buildings in nuclear power plants (NPP) or, outside the nuclear domain, in the conventional structural design of buildings, the seismic evaluation of these buildings may be done. In the occurrence of an earthquake in a NPP or in the case of changing the use of a conventional building, the seismic levels are modified. Then a new analysis need to be performed. This paper focusses on the situation where reinforcing the concrete building is needed and it also analyses how an extern reinforcement performed using polymers can be carried out to fulfill the new seismic requeriments. We present two main results: a) the resulting momentum-curvature diagrams obtained reinforcing standard segments embraced with polymers; b) the evaluation of the structure capacity on the basis of the modified diagrams. Finally, a modal pushover analysis is selected to perform the seismic evaluation of two types of concrete columns, those having a polymer reinforcement and those without it. This paper presents the basis of the subject in a theoretical form.

Seismic Evaluation of Existing Reinforced Concrete Building Columns

1996 ◽  
Vol 12 (4) ◽  
pp. 715-739 ◽  
Author(s):  
Abraham C. Lynn ◽  
Jack P. Moehle ◽  
Stephen A. Mahin ◽  
William T. Holmes
Keyword(s):  
Reinforced Concrete ◽  
Axial Load ◽  
Lateral Displacement ◽  
Concrete Columns ◽  
Vertical Load ◽  
Seismic Evaluation ◽  
Severe Damage ◽  
Reinforced Concrete Columns ◽  
Concrete Building ◽  
Constant Axial Load

Past earthquakes have emphasized the vulnerability of reinforced concrete columns having details typical of those built before the mid-1970's. These columns are susceptible to axial-flexural, shear, and bond failures, which subsequently may lead to severe damage or collapse of the building. Research was undertaken to investigate the lateral and vertical load-resisting behavior of reinforced concrete columns typical of pre-1970's construction. Eight full-scale specimens were constructed and were loaded with constant axial load and increasing cyclic lateral displacement increments until failure. Test data are presented and compared with behavior estimated by using various evaluation methods.

Using Limit Analysis for Seismic Evaluation of Component Located in Nuclear Power Plants

2002 ◽  
Author(s):  
Petr Zeman
Keyword(s):  
Limit Analysis ◽  
Nuclear Power ◽  
Power Plants ◽  
Evaluation Method ◽  
Static Load ◽  
Seismic Load ◽  
Plastic Behavior ◽  
Seismic Evaluation ◽  
Perfectly Plastic ◽  
American Society

Using limit analysis for evaluation of the seismic resistance of the components located in NPPs is compared with the standard evaluation method. This comparison is based on the procedure specified in American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section III. Subsection NC, version 1992 standard. The limit analysis uses perfectly plastic behavior of the material. The seismic load is restricted when using limit analysis to the pseudo-static load. The possibility of building of more realistic non-linear model including contacts is another advantage of limit analysis. Using limit analysis is the way to move the evaluation method closer to the real collapse load and to reduce conservatism.

Review of Pipe Wall Thinning and Seismic Evaluation in Japan

2009 ◽  
Author(s):  
Hiroshi Miyano ◽  
Katsuji Maeda ◽  
Masayuki Takizawa ◽  
Naoto Sekimura
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Pipe Wall ◽  
High Reliability ◽  
Fiscal Year ◽  
Accident Risk ◽  
Seismic Evaluation ◽  
Wall Thinning ◽  
Piping Systems ◽  
The Government

For nuclear power plants, the four major requirements are 1) high safety, 2) high reliability, 3) good economical acceptability, and 4) as few as possible environmental impact. However, it is still difficult to completely avoid problems for structural materials as structural stress corrosion cracking (SCC) and for piping systems as flow accelerated corrosion (FAC), liquid drop impulsion erosion (LDI). Especially FAC and LDI are uncertainty phenomenon as pipe wall thinning, so there is the piping rupture accident risk on all of piping systems under the specific conditions. In Japan, after in August 2004, the accident of the secondary pipe rupture in Mihama Power Plant Unit 3, The Kansai Electric Power Co., Inc. (KEPCO), R&D projects about pipe wall thinning phenomenon and mechanism had been promoted in many organizations. The other hand it is requested to evaluate the safety and reliability of piping systems of long term operating plant and with on special case of seismic condition. It was requested to be able to evaluate pipe wall thinning and its reliability with more accurate. This project had programmed under the government budget from 2006 planed until 2010 fiscal year [1]. At the mile stone of half span, the project had these fruits, 1) Computer program for FAC simulation, 2) Droplet phenomena for LDI simulation, 3) Simplified calculation model of pipe wall thinning for seismic evaluation.

Seismic Re-Evaluation of the Tarapur Atomic Power Plants 1 and 2

2004 ◽  
Author(s):  
S. M. Ingole ◽  
B. Santosh Kumar ◽  
Sushil Gupta ◽  
U. P. Singh ◽  
K. Giridhar ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Support Systems ◽  
Free Field ◽  
Heat Removal ◽  
Boiling Water Reactors ◽  
Seismic Evaluation ◽  
Heavy Water Reactor ◽  
Water Reactors ◽  
Safety Systems

Two Boiling Water Reactors (BWR) of 210 MWe each at Tarapur Atomic Power Station, Units-1&2 (TAPS-1&2) were commissioned in the year 1969. The safety related civil structures at TAPS had been designed for a seismic coefficient of 0.2g and other structures for 0.1g. The work of seismic re-evaluation of the TAPS-1&2 has been taken up in the year 2002. As two new Pressurized Heavy Water Reactor (PHWR) plants of 540 MWe each, Tarapur Atomic Power Project Units-3&4 (TAPP-3&4), are coming up in the vicinity of TAPS-1&2, detailed geological and seismological studies of the area around TAPS-1&2 are available. The same free-field ground motion as generated for TAPP-3&4 has been used for TAPS-1&2. The seismic re-evaluation of the plant has been performed as per the procedure given in IAEA, Safety Reports Series entitled “Seismic Evaluation of Existing Nuclear Power Plants”, and meeting the various codes & standards, viz., ASME, ASCE, IEEE standards etc. The Safety Systems (SS) and Safety Support Systems (SSS) are qualified by adopting detailed analysis and testing methods. The equipment in the SS and SSS have been qualified by conducting a walkdown as per the procedure given in Generic Implementation Procedure, Dept. of Energy (GIP–DOE), USA. The safety systems include the systems required for safe shutdown of the plant, one chain of decay heat removal and containment of activity. The safety support systems viz., Electrical, Instrumentation & Control and systems other than SS & SSS have been qualified by limited analysis, testing and mostly by following the procedure of walkdown. The paper brings out the details of the work accomplished during seismic re-evaluation of the two units of BWR at Tarapur.

Results of Regulatory Investigations as a Basis for Safety Improvements of Nuclear Power Plants

1996 ◽  
Vol 210 (5) ◽  
pp. 345-350
Author(s):  
H P Berg ◽  
U Volland ◽  
L Weil
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Safety ◽  
Technical Development ◽  
Regulatory State ◽  
Safety Level ◽  
Public Issue ◽  
State Authority ◽  
The Subject

Nuclear safety is not only a matter of technical development but is also an important public issue. Therefore it is mandatory that the responsible regulatory state authority performs its own investigation programme in order to enhance the safety level. The purpose and main objectives of this German regulatory investigation programme as well as the subject of some investigations are presented.

Sign in / Sign up

Export Citation Format

Share Document