Search Results - "Obaidurrahman, K."

An implicit finite difference method for solving the corrected fractional neutron point kinetics equations by Roul, Pradip, Madduri, Harshita, Obaidurrahman, K.

“…It is well known that Espinosa-parades et al. (Espinosa-Paredes et al., 2011) proposed a fractional neutron point kinetic (FNPK) model with multi-group of…”
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Optimal Main Heat Transport system configuration for a nuclear power plant by Gaikwad, Avinash J., Maheshwari, Naresh K., Obaidurrahman, K., Gupta, Aniket, Pradhan, Santosh K.

“…•Selection of an optimal Main Heat Transport (MHT) system configuration for a nuclear power plant (NPP) is an activity of high significance, as it influences…”
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Solution of PHWR 3D kinetics benchmark using TRIKIN code by Kumar, Rakesh, K, Obaidurrahman, Doshi, J.B., Gaikwad, Avinash J.

“…Scaling up of core sizes beyond present generation has rendered renewed topicality to space-time kinetics and relevant safety research. Detailed computational…”
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Spatial instability analysis in pressurized water reactors by Obaidurrahman, K., Doshi, J.B.

“…A simple methodology has been developed to assess the spatial dynamic behavior of large PWRs against xenon spatial instability in different modes. Method of…”
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Towards an efficient multiphysics model for nuclear reactor dynamics by Obaidurrahman, K., Gaikwad, Avinash

“…Availability of fast computer resources nowadays has facilitated more in-depth modeling of complex engineering systems which involve strong multiphysics…”
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Linear stability analysis of a nuclear reactor using the lumped model by Kale, Vivek, Kumar, Rakesh, Obaidurrahman, K., Gaikwad, Avinash

“…The stability analysis of a nuclear reactor is an important aspect in the design and operation of the reactor. A stable neutronic response to perturbations is…”
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Spatial neutronic coupling aspects in nuclear reactors by Obaidurrahman, K., Singh, Om Pal

“…In this paper, an effort is made to gain insights about neutronic coupling and decoupling phenomena of nuclear reactors and its consequences on their safety…”
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Development and benchmarking of space-time kinetics solver in REDAC by Kale, Vivek A., Obaidurrahman, K.

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Numerical approximation of a fractional neutron diffusion equation for neutron flux profile in a nuclear reactor by Roul, Pradip, Rohil, Vikas, Espinosa-Paredes, Gilberto, Obaidurrahman, K.

“…This paper focuses on development of an efficient numerical technique for approximation of a fractional neutron diffusion equation with delayed neutrons for…”
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An efficient computational technique for solving a fractional-order model describing dynamics of neutron flux in a nuclear reactor by Roul, Pradip, Rohil, Vikas, Espinosa-Paredes, Gilberto, Obaidurrahman, K.

“…This paper focuses on the development of a computational technique for numerical solution of the time-fractional neutron diffusion (FND) equation, which…”
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Numerical approximation of a two-dimensional fractional neutron diffusion model describing dynamics of neutron flux in a nuclear reactor by Roul, P., Rohil, Vikas, Espinosa-Paredes, Gilberto, Obaidurrahman, K.

“…The goal of this work is to develop a high-order numerical technique to solve a two-dimensional fractional neutron diffusion (FND) model describing dynamical…”
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Forward sensitivity analysis procedure (FSAP) with improved quasi static method for the estimation of dynamic uncertainty in reactor transients by Mohideen Abdul Razak, M., Obaidurrahman, K.

“…•Forward sensitivity analysis procedure (FSAP) with IQS method is developed to estimate the dynamic uncertainty in reactor transient caused by uncertainties in…”
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Numerical simulation of two-dimensional fractional neutron diffusion model describing dynamical behaviour of sodium-cooled fast reactor by Roul, Pradip, Rohil, Vikas, Espinosa-Paredes, Gilberto, Obaidurrahman, K.

“…•A novel numerical method is developed for solving 2D FND model.•Neutron flux distributions are computed in the sodium-cooled fast reactor.•Influence of…”
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An efficient numerical method for fractional neutron diffusion equation in the presence of different types of reactivities by Roul, Pradip, Rohil, Vikas, Espinosa-Paredes, Gilberto, Obaidurrahman, K.

“…•Numerical analysis of fractional neutron diffusion equation.•Anomalous diffusion behavior with step, ramp and sinusoidal reactivity effects.•Application of L1…”
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Semi wavelet-based improved quasi static method for the analysis of PHWR transients by Mohideen Abdul Razak, M., Obaidurrahman, K.

“…•A new computational method is presented here using wavelet to estimate the transient.•The concept of micro time step and macro time step does not arise here…”
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Design and analysis of a numerical method for fractional neutron diffusion equation with delayed neutrons by Roul, Pradip, Rohil, Vikas, Espinosa-Paredes, Gilberto, Prasad Goura, V.M.K., Gedam, R.S., Obaidurrahman, K.

“…The main purpose of this work is to construct and analyze an efficient numerical scheme for solving the fractional neutron diffusion equation with delayed…”
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Design and stability analysis of an implicit non-standard finite difference scheme for fractional neutron point kinetic equation by Roul, Pradip, Prasad Goura, V.M.K., Madduri, Harshita, Obaidurrahman, K.

“…This paper is concerned with the construction of a new numerical technique to obtain approximate solution for an extended fractional neutron point kinetic…”
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Simulations for worth determination of CPSARs in VVER-1000 reactor using EXCEL and TRIHEX-FA code system by Thilagam, L., Mohapatra, D.K., Obaidurrahman, K., Jagannathan, V.

“…•Prediction capability of EXCEL & TRIHEX-FA codes for worth of CPSARs in VVER -1000.•Employs JEFF-3.1 based high temperature nuclear data library processed…”
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Reactor core heterogeneity effects on radionuclide inventory by Obaidurrahman, K., Gupta, S.K.

“…► Reactor core heterogeneity effects on radionuclide inventory are studied. ► A methodology for inventory estimation of individual fuel assembly is developed…”
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Development, validation and application of multi-point kinetics model in RELAP5 for analysis of asymmetric nuclear transients by Pradhan, Santosh K., Obaidurrahman, K., Iyer, Kannan N., Gaikwad, Avinash J.

“…•A multi-point kinetics model is developed for RELAP5 system thermal hydraulics code.•Model is validated against extensive 3D kinetics code.•RELAP5 multi-point…”
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