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Featured researches published by V. Vinod.


Archive | 2017

Numerical Simulation and Experimental Validation of Future FBR Surge Tank Hydraulics

P. Lijukrishnan; D. Ramdasu; V. Vinod; G. Padmakumar; K.K. Rajan

Surge tank is provided in the secondary sodium circuit of Sodium cooled Fast Reactors (SFR) to protect the secondary sodium circuit components from the pressure surges due to sodium water reaction in Steam Generator (SG). The pressurized argon gas inside the surge tank above sodium will act as a cushion and absorb the pressure surges. The entrainment of argon gas into the sodium due to free level fluctuations, turbulence etc. can cause operational difficulties in reactor. It is necessary to develop effective gas entrainment mitigating devices which keeps the sodium free surface calm but the development only through experiments is difficult and time consuming. Therefore a CFD model of surge tank is developed to predict the surge tank hydraulics and it is validated through experiments. Velocity measurement in the model at different directions and different elevations has been carried out using Ultrasonic Velocity Profiler (UVP).


Annals of Nuclear Energy | 2013

Experimental evaluation of sodium to air heat exchanger performance

V. Vinod; Satya Pathak; Vishal Paunikar; V.A. Suresh Kumar; I.B. Noushad; K.K. Rajan


14th International Conference on Nuclear Engineering | 2006

Performance Assessment of Sodium to Air Finned Heat Exchanger for FBR

V. Vinod; V. A. Suresh Kumar; I.B. Noushad; T. R. Ellappan; Krishna Rajan; M. Rajan; G. Vaidyanathan


Annals of Nuclear Energy | 2015

Effect of geometric factors on performance of a sodium to air heat exchanger in a fast breeder reactor

K. Kannan; V. Vinod; G. Padmakumar; R. Rudramoorthy; K.K. Rajan


Nuclear Engineering and Design | 2014

Experimental study on the transient response of passive decay heat removal system

V. Vinod; S. Chandramouli; G. Padmakumar; B.K. Nashine; K.K. Rajan


Nuclear Engineering and Design | 2014

Experimental evaluation of the heat transfer performance of sodium heated once through steam generator

V. Vinod; L.S. Sivakumar; V.A. Suresh Kumar; I.B. Noushad; G. Padmakumar; K.K. Rajan


Nuclear Engineering and Design | 2017

Performance evaluation of decay heat removal system of PFBR with partial availability of air side dampers

V. Vinod; S. Sathishkumar; R.K. Mourya; S. Chandramouli; G. Padmakumar; B.K. Nashine; P. Selvaraj


Annals of Nuclear Energy | 2013

Behaviour of steam generator bolted flange joints at elevated temperatures

V. Vinod; R.K. Mourya; B.K. Sreedhar; I.B. Noushad; K.K. Rajan


Annals of Nuclear Energy | 2017

Evaluation of hydraulic characteristics of core flow monitoring mechanism for PFBR

N.S. Shivakumar; Nagaraju Bekkenti; S. Suresh Kumar; N. Ravichandran; V. Vinod; G. Padmakumar; K.K. Rajan


Progress in Nuclear Energy | 2016

Process optimisation of a liquid sodium economiser circuit

S. Sathishkumar; V. Vinod; G. Padmakumar; K.K. Rajan

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K.K. Rajan

Indira Gandhi Centre for Atomic Research

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G. Padmakumar

Indira Gandhi Centre for Atomic Research

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I.B. Noushad

Indira Gandhi Centre for Atomic Research

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V.A. Suresh Kumar

Indira Gandhi Centre for Atomic Research

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B.K. Nashine

Indira Gandhi Centre for Atomic Research

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L.S. Sivakumar

Indira Gandhi Centre for Atomic Research

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R.K. Mourya

Indira Gandhi Centre for Atomic Research

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S. Chandramouli

Indira Gandhi Centre for Atomic Research

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S. Sathishkumar

Indira Gandhi Centre for Atomic Research

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B.K. Sreedhar

Indira Gandhi Centre for Atomic Research

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