Concepedia

Author

Pavel Medvedev

Idaho National LaboratoryORCID

Also Known As

Medvedev, P, Medvedev, Pavel, Medvedev, Pavel G [Idaho National Laboratory]; Ozaltun, Hakan [Idaho National Laboratory]; Robinson, Adam Brady [Idaho National Laboratory]; Rabin, Barry H [Idaho National Laboratory], Medvedev, Pavel G., P. G. Medvedev, P. Medvedev, P.G. Medvedev, PAVEL MEDVEDEV, Pavel G. Medvedev, Pavel Medvedev

101

Publications

859

Citations

15

H-Index

39

Concepts

All Affiliations

Idaho National LaboratoryArgonne National LaboratoryAustralian Nuclear Science and Technology OrganisationThe Ohio State University
PM

About

Pavel Medvedev is an author at Idaho National Laboratory specializing in engineering, materials science, and mechanical engineering.

Top Concepts

#ConceptH-IndexPublicationsCitations

1

Engineering

15

22

631

2

Applied Physics

6

6

212

3

Chemical Engineering

3

3

57

4

Chemistry

1

1

19

5

Industrial Engineering

1

1

15

Pavel Medvedev

×

25

Publications

672

Citations

15

H-Index

YearCitations

Microstructural development in irradiated U-7Mo/6061 Al alloy matrix dispersion fuel

Dennis D. Keiser, Adam Robinson, Jan‐Fong Jue,

Journal of Nuclear Materials

2009

70

TEM characterization of U–7Mo/Al–2Si dispersion fuel irradiated to intermediate and high fission densities

Jian Gan, Dennis D. Keiser, Brandon Miller,

Journal of Nuclear Materials

2012

69

Assessment of residual stresses on U10Mo alloy based monolithic mini-plates during Hot Isostatic Pressing

Hakan Ozaltun, M.-H. Herman Shen, Pavel Medvedev

Journal of Nuclear Materials

2011

58

Dual phase MgO–ZrO2 ceramics for use in LWR inert matrix fuel

Pavel Medvedev, S. M. Frank, T. P. O’Holleran,

Journal of Nuclear Materials

2005

54

Transmission electron microscopy characterization of the fission gas bubble superlattice in irradiated U–7 wt%Mo dispersion fuels

Brandon Miller, Jian Gan, Dennis D. Keiser,

Journal of Nuclear Materials

2014

50

Microstructural characterization of irradiated U–7Mo/Al–5Si dispersion fuel to high fission density

Jian Gan, Brandon Miller, Dennis D. Keiser,

Journal of Nuclear Materials

2014

36

Thermal conductivity and acid dissolution behavior of MgO–ZrO2 ceramics for use in LWR inert matrix fuel

Pavel Medvedev, Marsha J. Lambregts, M. K. Meyer

Journal of Nuclear Materials

2005

36

Microstructure of the irradiated U3Si2/Al silicide dispersion fuel

Jian Gan, Dennis D. Keiser, Brandon Miller,

Journal of Nuclear Materials

2011

35

Effects of irradiation on the microstructure of U–7Mo dispersion fuel with Al–2Si matrix

Dennis D. Keiser, Jan‐Fong Jue, Adam Robinson,

Journal of Nuclear Materials

2012

30

Modeling porosity migration in LWR and fast reactor MOX fuel using the finite element method

Stephen Novascone, Pavel Medvedev, John W. Peterson,

Journal of Nuclear Materials

2018

25

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