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Featured researches published by M. K. Agrawal.


Nuclear Engineering and Design | 2002

Evaluation of Seismic Fragility of Structures - A Case Study

Kapilesh Bhargava; A.K. Ghosh; M. K. Agrawal; R Patnaik; S. Ramanujam; H. S. Kushwaha

The present paper attempts to evaluate the seismic fragility for a typical elevated water-retaining structure. The structure is analysed for two cases: (i) empty tank; and (ii) tank filled with water. The various parameters that could affect the seismic structural response include material strength of concrete and reinforcing steel, effective prestress available in the tank, ductility ratio and structural damping available within the structure, normalised ground motion response spectral shape, foundation and surrounding soil parameters and the total height of water available in the tank. Based on this case study, the seismic fragility of the structure is developed. The results are presented as families of conditional probability curves plotted against peak ground acceleration (PGA) at two critical locations. The procedure adopted, incorporates the various randomness and uncertainty associated with the parameters under consideration.


Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy | 2006

Finite Element Simulation of Dynamic Behavior of Pressurized Piping System Under Large Seismic Load

A. Ravi Kiran; M. K. Agrawal; G. R. Reddy; A. K. Ghosh; H. S. Kushwaha

The nuclear power plant piping systems are often subjected to the cyclic loading conditions due to transients, seismic or other unexpected events. During these events, the probable mode of failure for piping component is fatigue-ratcheting. Earlier the design of piping subjected to seismic excitation was based on the principle of static collapse. Later on, it was postulated that the cause of failure of piping components is fatigue ratcheting and not plastic collapse. The 1995 ASME Boiler & Pressure Vessel code, Section-III, has incorporated the reverse dynamic loading and ratcheting into the code. An Analytical study is carried out to investigate the behavior of the pressurized piping system under large seismic loading. The analysis is performed using equivalent inertial forces. Chaboche nonlinear kinematic hardening model is used for ratcheting simulation. The capability of the model to simulate the ratcheting response of the piping system is of particular interest. Comparison of analysis results against test results are presented in the paper.Copyright


Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy | 2006

Effect of Opening on the Response of Containment Model to Pressure Loading

M. K. Agrawal; A. Ravi Kiran; A. K. Ghosh; H. S. Kushwaha

The Containment Studies Facility (CSF) is being set up in BARC for studying various containment related thermal hydraulic and other phenomena which occur during simulated accident conditions in Nuclear power Plants. The facility consists of a concrete containment model having a volumetric scale ratio of 200:1 with respect to the actual containment of Indian Pressurized Heavy Water Reactor. The structure is designed for pressure of 1.73 Kg/cm2 for specified leak tightness. Adequacy to withstand design pressure is checked by test as well as numerical analysis before commissioning of the facility. Accordingly Containment building model has been analyzed by finite element method for internal design pressure and dead weight. Analysis has been carried out for the structure with and without the opening in the containment. Effect of opening on the response of containment has been studied. The paper includes the modeling methodology, maximum deflection and stress amplification around the opening for various models.© 2006 ASME


Journal of Pressure Vessel Technology-transactions of The Asme | 2013

Evaluation of Inelastic Seismic Response of a Piping System Using a Modified Iterative Response Spectrum Method

A. Ravikiran; P. N. Dubey; M. K. Agrawal; G. R. Reddy; K. K. Vaze


Journal of Pressure Vessel Technology-transactions of The Asme | 2017

Fatigue-Ratcheting Behavior of 6 in Pressurized Carbon Steel Piping Systems Under Seismic Load: Experiments and Analysis

A. Ravi Kiran; G. R. Reddy; P. N. Dubey; M. K. Agrawal


Nuclear Engineering and Design | 2015

Experiments and analytical studies related to blowdown and containment thermal hydraulics on CSF

Anu Dutta; I. Thangamani; V.M. Shanware; K.S. Rao; B. Gera; A. Ravi Kiran; P. Goyal; Vishnu Verma; Pavan K. Sharma; M. K. Agrawal; S. Ganju; R. K. Singh


Journal of Pressure Vessel Technology-transactions of The Asme | 2015

Experimental and Numerical Studies of Ratcheting in a Pressurized Piping System Under Seismic Load

A. Ravikiran; P. N. Dubey; M. K. Agrawal; G. R. Reddy; R. K. Singh; K.K. Vaze


Thin-walled Structures | 2018

Experimental and numerical studies of inelastic behavior of thin walled elbow and tee joint under seismic load

A. Ravi Kiran; G.R. Reddy; M. K. Agrawal


Journal of Pressure Vessel Technology-transactions of The Asme | 2018

Experimental and Numerical Studies on Inelastic Dynamic Behaviour of Stainless Steel Elbow under Harmonic Base excitation

A. Ravi Kiran; G. R. Reddy; M. K. Agrawal


Procedia Engineering | 2016

Seismic Retrofitting of a Process Column Using Friction Dampers

A. Ravi Kiran; M. K. Agrawal; G. R. Reddy

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A. Ravi Kiran

Bhabha Atomic Research Centre

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G. R. Reddy

Bhabha Atomic Research Centre

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R. K. Singh

Bhabha Atomic Research Centre

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A. K. Ghosh

Bhabha Atomic Research Centre

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G.R. Reddy

Bhabha Atomic Research Centre

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H. S. Kushwaha

Bhabha Atomic Research Centre

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K. K. Vaze

Bhabha Atomic Research Centre

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P. N. Dubey

Bhabha Atomic Research Centre

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A. Ravikiran

Bhabha Atomic Research Centre

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A.K. Ghosh

Bhabha Atomic Research Centre

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