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Status of reduced activation ferritic/martensitic steel development

Journal of nuclear materials, 2007-08, Vol.367, p.33-41

2007

Volltextzugriff (PDF)

Ferritic/martensitic steels – overview of recent results

Journal of nuclear materials, 2002-12, Vol.307, p.455-465

2002

Volltextzugriff (PDF)

Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957

Journal of nuclear materials, 2004-08, Vol.329, p.352-355

2004

Volltextzugriff (PDF)

Progress and critical issues of reduced activation ferritic/martensitic steel development

Journal of nuclear materials, 2000-12, Vol.283-287, p.52-59

2000

Volltextzugriff (PDF)

Microstructural examination of commercial ferritic alloys at 200 dpa

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.293-298

Gelles, D.S.

1996

Volltextzugriff (PDF)

Low-activation ferritic and martensitic steels for fusion application

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.138-147

1996

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Current status and future R&D for reduced-activation ferritic/martensitic steels

Journal of nuclear materials, 1998-10, Vol.258, p.193-204

1998

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The transport and fate of helium in martensitic steels at fusion relevant He/dpa ratios and dpa rates

Journal of nuclear materials, 2007-08, Vol.367, p.417-422

2007

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Synergistic influence of displacement rate and helium/dpa ratio on swelling of Fe–(9, 12)Cr binary alloys in FFTF at ∼400 °C

Journal of nuclear materials, 2004-08, Vol.329, p.1008-1012

2004

Volltextzugriff (PDF)

On quantification of helium embrittlement in ferritic/martensitic steels

Journal of nuclear materials, 2000-12, Vol.283, p.838-840

Gelles, D.S

2000

Volltextzugriff (PDF)

Microstructural examination of irradiated and unirradiated V–4Cr–4Ti pressurized creep tubes

Journal of nuclear materials, 2002-12, Vol.307, p.393-397

Gelles, D.S.

2002

Volltextzugriff (PDF)

Using CrAlN Multilayer Coatings to Improve Oxidation Resistance of Steel Interconnects for Solid Oxide Fuel Cell Stacks

Journal of materials engineering and performance, 2004-06, Vol.13 (3), p.295-302

2004

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Comments on “Embrittlement of CrMo steels after low fluence irradiation in high flux isotope reactor”

Journal of nuclear materials, 1996-06, Vol.230 (2), p.187-190

Gelles, D.S.

1996

Volltextzugriff (PDF)

Microstructural examination of irradiated V–(4–5%)Cr–(4–5%)Ti

Journal of nuclear materials, 1998-10, Vol.258, p.1380-1385

1998

Volltextzugriff (PDF)

Fatigue performance and cyclic softening of F82H, a ferritic-martensitic steel

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.331-335

1996

Volltextzugriff (PDF)

Microstructural examination of low activation ferritic steels following irradiation in ORR at 330 and 400 °C to ∼10 dpa

Journal of nuclear materials, 2004-08, Vol.329, p.304-308

Gelles, D.S

2004

Volltextzugriff (PDF)

Development of oxide dispersion strengthened ferritic steels for fusion

Journal of nuclear materials, 1998-10, Vol.258, p.1209-1215

1998

Volltextzugriff (PDF)

Irradiation creep mechanisms: An experimental perspective

Journal of nuclear materials, 1988-10, Vol.159, p.286-309

1988

Volltextzugriff (PDF)

Radiation effects in beryllium used for plasma protection

Journal of nuclear materials, 1994-09, Vol.212, p.29-38

1994

Volltextzugriff (PDF)

A review of some effects of helium on charpy impact properties of ferritic/martensitic steels

Journal of nuclear materials, 1998-10, Vol.258, p.1216-1221

1998

Volltextzugriff (PDF)

Irradiation response of a reduced activation Fe-8Cr-2W martensitic steel (F82H) after FFTF irradiation

Journal of nuclear materials, 1992-09, Vol.191, p.868-873

1992

Volltextzugriff (PDF)

The influence of neutron irradiation in FFTF on the microstructural and microchemical development of Mo–41Re at 470–730 °C

Journal of nuclear materials, 2008-04, Vol.375 (3), p.370-381

2008

Volltextzugriff (PDF)

Microstructural examination of neutron-irradiated simple ferritic alloys

Journal of nuclear materials, 1982-01, Vol.108, p.515-526

Gelles, D.S.

1982

Volltextzugriff (PDF)

Thermal creep mechanisms in V–4Cr–4Ti pressurized tube specimens

Journal of nuclear materials, 2007-08, Vol.367, p.869-875

2007

Volltextzugriff (PDF)

Development of ferritic steels for reduced activation: The US program

Journal of nuclear materials, 1986-11, Vol.141, p.1081-1087

1986

Volltextzugriff (PDF)

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Status of reduced activation ferritic/martensitic steel development

Ferritic/martensitic steels – overview of recent results

Irradiation creep and swelling from 400 to 600 °C of the oxide dispersion strengthened ferritic alloy MA957

Progress and critical issues of reduced activation ferritic/martensitic steel development

Microstructural examination of commercial ferritic alloys at 200 dpa

Low-activation ferritic and martensitic steels for fusion application

Current status and future R&D for reduced-activation ferritic/martensitic steels

The transport and fate of helium in martensitic steels at fusion relevant He/dpa ratios and dpa rates

Synergistic influence of displacement rate and helium/dpa ratio on swelling of Fe–(9, 12)Cr binary alloys in FFTF at ∼400 °C

On quantification of helium embrittlement in ferritic/martensitic steels

Microstructural examination of irradiated and unirradiated V–4Cr–4Ti pressurized creep tubes

Using CrAlN Multilayer Coatings to Improve Oxidation Resistance of Steel Interconnects for Solid Oxide Fuel Cell Stacks

Comments on “Embrittlement of CrMo steels after low fluence irradiation in high flux isotope reactor”

Microstructural examination of irradiated V–(4–5%)Cr–(4–5%)Ti

Fatigue performance and cyclic softening of F82H, a ferritic-martensitic steel

Microstructural examination of low activation ferritic steels following irradiation in ORR at 330 and 400 °C to ∼10 dpa

Development of oxide dispersion strengthened ferritic steels for fusion

Irradiation creep mechanisms: An experimental perspective

Radiation effects in beryllium used for plasma protection

A review of some effects of helium on charpy impact properties of ferritic/martensitic steels

Irradiation response of a reduced activation Fe-8Cr-2W martensitic steel (F82H) after FFTF irradiation

The influence of neutron irradiation in FFTF on the microstructural and microchemical development of Mo–41Re at 470–730 °C

Microstructural examination of neutron-irradiated simple ferritic alloys

Thermal creep mechanisms in V–4Cr–4Ti pressurized tube specimens

Development of ferritic steels for reduced activation: The US program

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