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Nuclear fuels – Present and future

Journal of nuclear materials, 2009-05, Vol.389 (1), p.1-22

Olander, D.

2009

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Re-solution of fission gas – A review: Part I. Intragranular bubbles

Journal of nuclear materials, 2006-08, Vol.354 (1), p.94-109

2006

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Radiation heat loss from a PWR core during a severe accident

Nuclear engineering and design, 2012-09, Vol.250, p.284-286

Olander, D.

2012

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Redox condition in molten fluoride salts: Definition and control

Journal of nuclear materials, 2002-02, Vol.300 (2), p.270-272

Olander, D

2002

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The kinetics of hydrogen desorption from and adsorption on zirconium hydride

Journal of nuclear materials, 2010-02, Vol.397 (1), p.61-68

2010

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Growth of the interaction layer around fuel particles in dispersion fuel

Journal of nuclear materials, 2009, Vol.383 (3), p.201-208

Olander, D.

2009

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Point-defects in irradiated UO2

Journal of nuclear materials, 2010-04, Vol.399 (2-3), p.236-239

OLANDER, D

2010

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Uranium–zirconium hydride fuel properties

Nuclear engineering and design, 2009-08, Vol.239 (8), p.1406-1424

2009

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Fission-enhanced diffusion in dispersion fuels

Journal of nuclear materials, 2008-01, Vol.372 (1), p.94-105

Olander, D.

2008

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Vapor pressure of Buckminsterfullerene

Applied physics letters, 1992-03, Vol.60 (11), p.1313-1314

1992

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On the role of grain boundary diffusion in fission gas release

Journal of nuclear materials, 2001-02, Vol.288 (2), p.137-147

2001

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Hydride fuel for LWRs—Project overview

Nuclear engineering and design, 2009-08, Vol.239 (8), p.1374-1405

2009

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Point-defects in irradiated UO sub(2)

Journal of nuclear materials, 2010-04, Vol.399 (2-3), p.236-239

Olander, D

2010

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Thermodynamics of the LiF-NaF-BeF2 system at high temperatures

Fluid phase equilibria, 2007-07, Vol.255 (1), p.1-10

2007

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Point-defects in irradiated UO 2

Journal of nuclear materials, 2010, Vol.399 (2), p.236-239

Olander, D.

2010

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High-pressure hydriding of Zircaloy cladding by the thermogravimetry and tube-burst techniques

Journal of nuclear materials, 2005-01, Vol.336 (1), p.113-119

2005

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Oxidation of Zircaloy by steam

Journal of nuclear materials, 1991-05, Vol.182, p.170-194

1991

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Thermodynamics of the Zr-H System

Journal of the American Ceramic Society, 1995-12, Vol.78 (12), p.3323-3328

1995

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Thermodynamics of urania volatization in steam

Journal of nuclear materials, 1999-04, Vol.270 (1), p.187-193

Olander, D.R

1999

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Mechanistic interpretations of UO2 oxidation

Journal of nuclear materials, 1998, Vol.252 (1-2), p.121-130

OLANDER, D. R

1998

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Measurement of hydriding susceptibility of Zircaloy cladding by the tube-burst technique at high pressure and high temperature

Journal of nuclear materials, 2001-08, Vol.297 (2), p.107-112

2001

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Nuclear Fuels – Present and Future

MRS proceedings, 2010, Vol.1264 (1), Article 1264-Z04-01

2010

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Fission product release from trace irradiated UO2+X

Journal of nuclear materials, 1998-03, Vol.254 (1), p.22-33

1998

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Reaction of atomic hydrogen with crystalline silicon

Surface science, 1989-03, Vol.209 (3), p.291-313

1989

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Review of the materials-chemistry models in the VICTORIA code

Journal of nuclear materials, 1999-04, Vol.270 (1), p.1-10

1999

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Nuclear fuels – Present and future

Re-solution of fission gas – A review: Part I. Intragranular bubbles

Radiation heat loss from a PWR core during a severe accident

Redox condition in molten fluoride salts: Definition and control

The kinetics of hydrogen desorption from and adsorption on zirconium hydride

Growth of the interaction layer around fuel particles in dispersion fuel

Point-defects in irradiated UO2

Uranium–zirconium hydride fuel properties

Fission-enhanced diffusion in dispersion fuels

Vapor pressure of Buckminsterfullerene

On the role of grain boundary diffusion in fission gas release

Hydride fuel for LWRs—Project overview

Point-defects in irradiated UO sub(2)

Thermodynamics of the LiF-NaF-BeF2 system at high temperatures

Point-defects in irradiated UO 2

High-pressure hydriding of Zircaloy cladding by the thermogravimetry and tube-burst techniques

Oxidation of Zircaloy by steam

Thermodynamics of the Zr-H System

Thermodynamics of urania volatization in steam

Mechanistic interpretations of UO2 oxidation

Measurement of hydriding susceptibility of Zircaloy cladding by the tube-burst technique at high pressure and high temperature

Nuclear Fuels – Present and Future

Fission product release from trace irradiated UO2+X

Reaction of atomic hydrogen with crystalline silicon

Review of the materials-chemistry models in the VICTORIA code

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