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Dive into the research topics where Tanay Mazumdar is active.

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Featured researches published by Tanay Mazumdar.


Nuclear Science and Engineering | 2018

Application of Krylov Acceleration Technique in Method of Characteristics–Based Neutron Transport Code

Tanay Mazumdar; Anurag Gupta

Abstract In our earlier work, a computer code based on Method of Characteristics (MOC) was developed to solve the neutron transport equation for mainly assembly-level lattice calculations with reflective and periodic boundary conditions and to some extent core-level calculation with a vacuum boundary condition. Performance of the MOC code was also demonstrated with flat and linear flux approximations. Since neutron transport calculations involve extensive computation, an attempt is made to develop an efficient numerical recipe that will reduce the computation time. First, a conventional MOC solution of the neutron transport equation is transformed into a matrix equation to apply the Krylov subspace iteration method for accelerating the solution. It is found that even in the most sophisticated and compact formats, forming the matrix equation explicitly by storing its nonzero elements requires extremely large computer memory. Hence, an alternate way to apply the Krylov iteration is demonstrated by incorporating the effect of the matrix-based approach into the solution without storing the matrix elements. This computationally viable and novel acceleration technique is used in combination with the existing formalism of flat as well as linear flux approximation to solve a number of benchmark problems. Results show significant improvement in terms of faster convergence of the solution over the conventional inner-outer iteration without compromising accuracy.


Annals of Nuclear Energy | 2014

NEMSQR: A 3-D multi group diffusion theory code based on nodal expansion method for square geometry

Tej Singh; Tanay Mazumdar; Paritosh Pandey


Annals of Nuclear Energy | 2013

Development of neutronics and thermal hydraulics coupled code – SAC-RIT for plate type fuel and its application to reactivity initiated transient analysis

Tej Singh; Jainendra Kumar; Tanay Mazumdar; V.K. Raina


Annals of Nuclear Energy | 2015

Solution of neutron transport equation by Method of Characteristics

Tanay Mazumdar; S.B. Degweker


Annals of Nuclear Energy | 2012

RITAC: Reactivity Initiated Transient Analysis Code – An overview

Tanay Mazumdar; Tej Singh; H.P. Gupta; Kanchhi Singh


Annals of Nuclear Energy | 2017

Solution of the neutron transport equation by the Method of Characteristics using a linear representation of the source within a mesh

Tanay Mazumdar; S.B. Degweker


Life Cycle Reliability and Safety Engineering | 2017

NEMHEX solution of benchmark problems on thermal and fast breeder reactor cores with hexagonal lattice

Tej Singh; Paritosh Pandey; Tanay Mazumdar


Annals of Nuclear Energy | 2017

Development of a Nodal Expansion Method based space-time kinetics code for hexagonal geometry

Tej Singh; Tanay Mazumdar


Annals of Nuclear Energy | 2013

Physics design of 2 MW upgraded Apsara research reactor

Tej Singh; Paritosh Pandey; Tanay Mazumdar; Kanchhi Singh; V.K. Raina


Life Cycle Reliability and Safety Engineering | 2018

Risk-based approach towards design evaluation and re-assessment of shutdown safety margin

P. V. Varde; Tej Singh; Tanay Mazumdar; Arihant Jain

Collaboration


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Tej Singh

Bhabha Atomic Research Centre

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Paritosh Pandey

Bhabha Atomic Research Centre

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H.P. Gupta

Bhabha Atomic Research Centre

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Kanchhi Singh

Bhabha Atomic Research Centre

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S.B. Degweker

Bhabha Atomic Research Centre

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V.K. Raina

Bhabha Atomic Research Centre

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Anurag Gupta

Bhabha Atomic Research Centre

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Arihant Jain

Bhabha Atomic Research Centre

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Jainendra Kumar

Bhabha Atomic Research Centre

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P. V. Varde

Bhabha Atomic Research Centre

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