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In situ study of hydride precipitation kinetics and re-orientation in Zircaloy using synchrotron radiation

Acta materialia, 2010-12, Vol.58 (20), p.6575-6583

2010

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The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)

Journal of nuclear materials, 2011-05, Vol.412 (2), p.250-267

2011

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Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium

Journal of materials research, 1998-06, Vol.13 (6), p.1434-1484

1998

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Void shrinkage in 21Cr32Ni austenitic model alloy during in-situ ion irradiation

Journal of nuclear materials, 2021-01, Vol.543 (C), p.152636, Article 152636

2021

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Measurement of chlorine concentration on steel surfaces via fiber-optic laser-induced breakdown spectroscopy in double-pulse configuration

Spectrochimica acta. Part B: Atomic spectroscopy, 2018-03, Vol.141 (C), p.44-52

2018

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A thermal spike model of grain growth under irradiation

Journal of applied physics, 2008-10, Vol.104 (7), p.073525-073525-13

2008

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Experimental determination of zirconium hydride precipitation and dissolution in zirconium alloy

Journal of nuclear materials, 2018-10, Vol.509 (C), p.162-167

2018

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Microstructural evolution of the 21Cr32Ni model alloy under irradiation

Journal of nuclear materials, 2018-11, Vol.510 (C), p.297-311

2018

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The role of hydrogen in zirconium alloy corrosion

Journal of nuclear materials, 2017-12, Vol.496 (C), p.301-312

2017

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The influence of hydride blisters on the fracture of Zircaloy-4

Journal of nuclear materials, 2003-10, Vol.322 (1), p.21-35

2003

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Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction

Journal of nuclear materials, 2009-08, Vol.392 (3), p.453-463

2009

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Transmission electron microscopy of oxide development on 9Cr ODS steel in supercritical water

Journal of nuclear materials, 2009-07, Vol.392 (2), p.280-285

2009

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Characterization of in-situ ion irradiated Fe-21Cr-32Ni austenitic model alloy and alloy 800H at low doses

Journal of nuclear materials, 2021-11, Vol.555, p.153149, Article 153149

2021

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Investigation of breakaway corrosion observed during oxide growth in pure and low alloying element content Zr exposed in water at 360°C

Journal of nuclear materials, 2022-01, Vol.558, p.153358, Article 153358

2022

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In-situ ion irradiation induced grain growth in nanocrystalline ceria

Journal of nuclear materials, 2021-03, Vol.545 (C), p.152688, Article 152688

2021

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Robotic delivery of laser-induced breakdown spectroscopy for sensitive chlorine measurement in dry cask storage systems

Progress in nuclear energy (New series), 2018-11, Vol.109 (C), p.188-194

2018

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Influence of alloying elements on grain-growth in Zr(Fe) and Cu(Fe) thin-films under in situ ion-irradiation

Journal of nuclear materials, 2008-12, Vol.382 (2), p.184-189

2008

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Neutronic and mechanical evaluation of rare earth doped and undoped nitride-based coatings for accident tolerant fuels

Journal of nuclear materials, 2019-05, Vol.518 (C), p.419-430

2019

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Soft tissue response to mandibular advancement using 3D CBCT scanning

International journal of oral and maxillofacial surgery, 2011-04, Vol.40 (4), p.353-359

2011

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Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate

Journal of nuclear materials, 2004-01, Vol.324 (1), p.6-22

2004

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Determination of the alloying content in the matrix of Zr alloys using synchrotron radiation microprobe X-ray fluorescence

Journal of nuclear materials, 2003-09, Vol.321 (2), p.221-232

2003

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Failure of Zircaloy cladding under transverse plane-strain deformation

Nuclear engineering and design, 1998-12, Vol.186 (3), p.379-394

1998

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Tensile specimen geometry and the constitutive behavior of Zircaloy-4

Journal of nuclear materials, 2003-02, Vol.312 (2), p.257-261

2003

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Void shrinkage in 21Cr32Ni austenitic model alloy during in-situ ion irradiation

Journal of nuclear materials, 2020-10, Vol.543 (C)

2020

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Microstructural evolution of the 21Cr32Ni model alloy under irradiation

Journal of nuclear materials, 2018-11, Vol.510 (C)

2018

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In situ study of hydride precipitation kinetics and re-orientation in Zircaloy using synchrotron radiation

The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)

Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium

Void shrinkage in 21Cr32Ni austenitic model alloy during in-situ ion irradiation

Measurement of chlorine concentration on steel surfaces via fiber-optic laser-induced breakdown spectroscopy in double-pulse configuration

A thermal spike model of grain growth under irradiation

Experimental determination of zirconium hydride precipitation and dissolution in zirconium alloy

Microstructural evolution of the 21Cr32Ni model alloy under irradiation

The role of hydrogen in zirconium alloy corrosion

The influence of hydride blisters on the fracture of Zircaloy-4

Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction

Transmission electron microscopy of oxide development on 9Cr ODS steel in supercritical water

Characterization of in-situ ion irradiated Fe-21Cr-32Ni austenitic model alloy and alloy 800H at low doses

Investigation of breakaway corrosion observed during oxide growth in pure and low alloying element content Zr exposed in water at 360°C

In-situ ion irradiation induced grain growth in nanocrystalline ceria

Robotic delivery of laser-induced breakdown spectroscopy for sensitive chlorine measurement in dry cask storage systems

Influence of alloying elements on grain-growth in Zr(Fe) and Cu(Fe) thin-films under in situ ion-irradiation

Neutronic and mechanical evaluation of rare earth doped and undoped nitride-based coatings for accident tolerant fuels

Soft tissue response to mandibular advancement using 3D CBCT scanning

Structure of zirconium alloy oxides formed in pure water studied with synchrotron radiation and optical microscopy: relation to corrosion rate

Determination of the alloying content in the matrix of Zr alloys using synchrotron radiation microprobe X-ray fluorescence

Failure of Zircaloy cladding under transverse plane-strain deformation

Tensile specimen geometry and the constitutive behavior of Zircaloy-4

Void shrinkage in 21Cr32Ni austenitic model alloy during in-situ ion irradiation

Microstructural evolution of the 21Cr32Ni model alloy under irradiation

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