Search Results - "VRINDA DEVI, K. V"

Investigative studies of alpha irradiated PADC films: application to plutonium sources by Ramkumar, Jayshree, Vrinda Devi, K. V., Chandramouleeswaran, S.

“…Analytical evaluation of the effect of alpha fluence and energy on the properties of the irradiated PADC polymers was carried out. The images obtained by alpha…”
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Characterisation of nuclear fuel by spectroscopic evaluation of alpha autoradiographs by Vrinda Devi, K. V., Ramkumar, Jayshree, Sengupta, Arijit, Somayajulu, P. S., Dubey, J. N., Shaikh, I. H., Chandramouleeswaran, S.

“…New methods for estimation of concentration and distribution of plutonium in (Th,Pu)O 2 MOX fuel samples have been attempted by spectroscopic analysis of SSNTD…”
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A novel method for assessment of crowded plutonium alpha tracks by Ramkumar, Jayshree, Vrinda Devi, K. V.

“…Nuclear fuel fabrication facilities often require quick characterization of plutonium bearing samples which may contain high concentrations of plutonium…”
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Quantification of plutonium heterogeneity in (U, Pu) mixed oxide fuel using Passive Gamma Scanning by Vrinda Devi, K.V., Panakkal, J.P.

“…► Analysis of passive gamma scans of MOX fuel. ► Quantitative estimation of plutonium rich agglomerates. ► Use of through well geometry for Passive Gamma…”
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Plutonium heterogeneity in MOX fuel: A quantitative analysis by Vrinda Devi, K.V., Ramkumar, Jayshree, Biju, K., Sathe, D.B.

“…(U,Pu)O2 mixed oxide (MOX) fuel has been irradiated in thermal as well as fast reactors in India for Pu utilization. MOX fuels are conventionally fabricated…”
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Fissile worth of MOX fuel: A non destructive study by Vrinda Devi, K.V., Sathe, D.B., Soreng, T.

“…Quality of (U,Pu)O2 mixed oxide (MOX) fuels for fast reactor is judged by its fissile worth; quantified as Pu239 equivalence which is governed by the isotopic…”
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Non destructive determination of PuO2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning by VRINDA DEVI, K. V, SORENG, T, MUKHERJEE, D, PANAKKAL, J. P, KAMATH, H. S

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Structural degradation of polyallyl diglycol carbonate (PADC) polymer: analytical characterization and simulation studies by Ramkumar, Jayshree, K. V., Vrinda Devi, Sundararajan, Mahesh, K., Biju

“…A comprehensive study has been carried out to understand the details of structural modifications of polyallyl diglycol carbonate (PADC) polymer under the…”
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Wavelet transform of autoradiographs: Analysis of MOX fuel heterogeneity by Dixit, Rajashree, Vrinda Devi, K.V., Biju, K., Kumar, Nagendra, Hinge, A.K., Vetal, Hema, Mukhopadhyay, S.

“…Radiation imaging is extensively applied in nuclear industry for various purposes including fuel characterization. Accurate quantitative evaluation of these…”
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Monte carlo simulations of gamma images: application to plutonium rich mixed carbide fuel by Devi, K. V. Vrinda, Biju, K.

“…A novel approach for quantitave characterisation of nuclear fuel for homogeneity based on comparison of autoradiographs with simulated standards is proposed…”
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Analysis of auto gamma images of plutonium bearing fuels: a comparative study of experimental and simulation methods by Vrinda Devi, K. V., Ramkumar, Jayshree, Biju, K., Sathe, D. B.

“…Image analysis and spectroscopic method of evaluation are applied on Gamma auto radiographs (GAR) to assess the effect of plutonium concentration in (U,Pu)O 2…”
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TRISO fuel volume fraction and homogeneity: a nondestructive characterization by Vrinda Devi, K. V., Dubey, J. N., Gupta, Jyoti, Shaikh, I. H.

“…A new nondestructive method to estimate the volume fraction and homogeneity of tristructural isotropic (TRISO)-coated fuel particles in fuel compacts designed…”
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A non destructive technique for determination of U233 and Pu content in MOX fuel pins for fast reactors by VRINDA DEVI, K. V, SORENG, T, PANAKKAL, J. P, KAMATH, H. S

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