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Featured researches published by V.P. Sinha.


Nuclear Technology | 2015

Study on Chemical Interaction of U 3 Si 2 Dispersoid and Aluminum Matrix in Plate Fuel Elements and Its Influence on the Mechanical Properties

V.P. Sinha; D. Kohli; R. Rakesh; P. V. Thakar; Aniruddha Kumar

Abstract Dispersion-type plate fuel elements are being fabricated with U3Si2 dispersoid (prepared by an innovative powder processing route) in aluminum matrix and clad in Al alloy for the modified core of the APSARA reactor by a standard picture frame technique followed by hot roll bonding operation at the Bhabha Atomic Research Centre Metallic Fuels Division. The fabrication regime allows the fuel elements to be exposed at 500°C for almost 5 h (total duration including hot roll bonding and blister test operation). Therefore, it is expected that during hot roll bonding and blister test operation, U3Si2 will chemically interact with aluminum and form an intermediate phase. Hence, the chemical interaction behavior of fuel dispersoid (U3Si2, prepared by powder metallurgy route) and matrix (aluminum) in plate fuel elements and its effect on mechanical properties is studied in the present paper. Therefore, a comparative study between an actual plate fuel element (i.e., U3Si2 dispersed in aluminum matrix and with Al alloy clad) and a sandwich plate with chemically inert material (i.e., Y2O3) as dispersed in aluminum matrix with Al alloy clad was carried out. The roll bonded samples were investigated through pull and peel tests, microhardness, tensile test, optical microscopy, scanning electron microscopy, electron probe microanalysis, and X-ray diffraction for various metallurgical examinations. During the course of study, it was observed that U3Si2 dispersoids in actual plate fuel elements were enveloped by a different phase while the dispersoid of Y2O3 remained inert in the surrogate plate under a similar fabrication history. The study concludes that limited exposure of the actual fuel plate at 500°C for 5 h results in improvement of bond strength mainly due to chemical interaction between fuel dispersoid and aluminum. The study also concludes that the tensile strength and ductility of the fuel plates did not show any adverse effects during dispersoid-matrix chemical interaction; however, the modulus of elasticity was found lower than the theoretically estimated value calculated by composite theory. The observations derived in the study are critical from the viewpoint that a decrease in the elastic modulus of the plate would adversely affect its flow-induced vibration properties during reactor operation. It may also be concluded that exposing the plate fuel elements at 500°C for longer duration (i.e., 30 h) will result in excessive swelling because of the accelerated interaction between dispersoid and matrix, which will eventually deteriorate the desired properties.


Research in Nondestructive Evaluation | 2013

Quantitative Analysis of Uranium Distribution in Plate Fuel Element Using Real Time Digital X-Ray Radiography

V.P. Sinha; R. Rakesh; P.V. Hegde; G.J. Prasad; S. Pal; G.P. Mishra

Dispersion type plate fuel elements were fabricated with U3Si2 dispersoids in aluminium matrix and clad in Al-alloy for the modified core of APSARA reactor by standard picture framing technique followed by hot roll bonding operation. In general around 85% reduction in thickness was carried out in fabricating the finished fuel plates. These fuel plates were then characterized by digital X-ray radiography technique to outline fuel meat boundary and also for the quantitative analysis of surface uranium metal density in the fuel meat. In order to evaluate the surface uranium density a non destructive technique was developed in which X-ray radiography image was digitized and gray value was calibrated in terms of uranium metal density. In addition, fuel meat and clad thickness of fuel plate was determined along longitudinal section by optical microscopy.


Journal of Alloys and Compounds | 2010

Phase transformation of metastable cubic γ-phase in U-Mo alloys

V.P. Sinha; P.V. Hegde; G.J. Prasad; G.K. Dey; H.S. Kamath


Journal of Alloys and Compounds | 2009

Development, preparation and characterization of uranium molybdenum alloys for dispersion fuel application

V.P. Sinha; G.J. Prasad; P.V. Hegde; R. Keswani; Chandra Bhanu Basak; S. Pal; G.P. Mishra


Journal of Alloys and Compounds | 2010

Effect of molybdenum addition on metastability of cubic γ-uranium

V.P. Sinha; P.V. Hegde; G.J. Prasad; G.K. Dey; H.S. Kamath


Journal of Nuclear Materials | 2008

Development of powder metallurgy technique for synthesis of U3Si2 dispersoid

V.P. Sinha; G.P. Mishra; S. Pal; K.B. Khan; P.V. Hegde; G.J. Prasad


Journal of Nuclear Materials | 2014

Fabrication of simulated plate fuel elements: Defining role of stress relief annealing

D. Kohli; R. Rakesh; V.P. Sinha; G.J. Prasad; I. Samajdar


Journal of Nuclear Materials | 2012

Development of UO2/PuO2 dispersed in uranium matrix CERMET fuel system for fast reactors

V.P. Sinha; P.V. Hegde; G.J. Prasad; S. Pal; G.P. Mishra


Journal of Nuclear Materials | 2014

Fabrication of simulated plate fuel elements: Defining role of out-of-plane residual shear stress

R. Rakesh; D. Kohli; V.P. Sinha; G.J. Prasad; I. Samajdar


Transactions of The Indian Institute of Metals | 2008

Development of high density uranium compounds and alloys as dispersion fuel for research and test reactors

V.P. Sinha; P.V. Hegde; G.J. Prasad; G.P. Mishra; S. Pal

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G.J. Prasad

Bhabha Atomic Research Centre

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P.V. Hegde

Bhabha Atomic Research Centre

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G.P. Mishra

Bhabha Atomic Research Centre

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S. Pal

Bhabha Atomic Research Centre

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R. Rakesh

Bhabha Atomic Research Centre

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D. Kohli

Bhabha Atomic Research Centre

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G.K. Dey

Bhabha Atomic Research Centre

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H.S. Kamath

Bhabha Atomic Research Centre

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I. Samajdar

Indian Institute of Technology Bombay

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K.B. Khan

Bhabha Atomic Research Centre

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