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Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids

Journal of nuclear materials, 2006-09, Vol.356 (1), p.122-135

2006

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The Influence of lithium environment on tensile behavior and microstructure of V–4Cr–4Ti

Journal of nuclear materials, 2009-07, Vol.392 (2), p.364-370

2009

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Effects of post-weld heat treatment conditions on hardness, microstructures and impact properties of vanadium alloys

Journal of nuclear materials, 2002-12, Vol.307, p.1595-1599

2002

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Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures

Journal of nuclear materials, 1998-10, Vol.258, p.1275-1279

1998

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Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.202-206

1996

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Irradiation creep of the US Heat 832665 of V–4Cr–4Ti

Journal of nuclear materials, 2009-04, Vol.386, p.618-621

2009

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Threshold helium concentration required to initiate cracking during welding of irradiated stainless steel

Journal of nuclear materials, 1995-08, Vol.225 (1-3), p.59-68

1995

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1.05 - Effect of Radiation on Strength and Ductility of Metals and Alloys

Comprehensive Nuclear Materials, 2020, p.130-152

Grossbeck, M.L.

Second Edition, 2020

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Biaxial thermal creep of two heats of V4Cr4Ti at 700 and 800 °C in a liquid lithium environment

Journal of nuclear materials, 2007-08, Vol.367 (1), p.788-793

2007

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Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773 K up to 5 dpa

Journal of nuclear materials, 2007-08, Vol.367, p.122-126

2007

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Modeling of strengthening mechanisms in irradiated fusion reactor first wall alloys

Journal of nuclear materials, 1992-09, Vol.191, p.808-812

1992

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Influence of details of reactor history on microstructural development during neutron irradiation

Journal of nuclear materials, 1993-10, Vol.205, p.206-218

1993

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Stress-strain relations of irradiated stainless steels below 673 K

Journal of nuclear materials, 1992-09, Vol.191, p.790-794

1992

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Impurity effects on reduced-activation ferritic steels developed for fusion applications

Journal of nuclear materials, 2000-08, Vol.280 (3), p.353-359

2000

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Empirical relations for tensile properties of austenitic stainless steels irradiated in mixed-spectrum reactors

Journal of nuclear materials, 1991-03, Vol.179, p.568-571

Grossbeck, M.L.

1991

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Low-temperature irradiation creep of fusion reactor structural materials

Journal of nuclear materials, 1991-03, Vol.179, p.130-134

1991

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Fracture toughness of candidate materials for ITER first wall, blanket, and shield structures

Journal of nuclear materials, 1994-09, Vol.212, p.442-447

1994

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Radiation effects at fusion reactor He : dpa ratios: Overview of US/Japan spectrally tailored experiments

Journal of nuclear materials, 1991-03, Vol.179, p.125-129

1991

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Creep of V–4Cr–4Ti in a lithium environment

Journal of nuclear materials, 2002-12, Vol.307, p.615-619

Grossbeck, M.L

2002

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Gas tungsten arc welding of vanadium alloys with impurity control

Journal of nuclear materials, 2002-12, Vol.307, p.1590-1594

2002

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Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773K up to 5dpa

Journal of nuclear materials, 2007-08, Vol.367-370, p.122-126

2007

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The response of austenitic steels to radiation damage

Journal of nuclear materials, 1984-05, Vol.122 (1), p.181-190

1984

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Post irradiation tensile and fatigue behavior of austenitic PCA stainless steels irradiated in HFIR

Journal of nuclear materials, 1988-07, Vol.155-157, p.957-962

1988

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Microstructure–fracture toughness relationship of vanadium alloy/stainless steel brazed joints

Journal of nuclear materials, 2001-11, Vol.299 (2), p.157-164

2001

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Furnace brazing type 304 stainless steel to vanadium alloy (V–5Cr–5Ti)

Journal of nuclear materials, 2000-12, Vol.283, p.1224-1228

2000

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Retention of hydrogen in fcc metals irradiated at temperatures leading to high densities of bubbles or voids

The Influence of lithium environment on tensile behavior and microstructure of V–4Cr–4Ti

Effects of post-weld heat treatment conditions on hardness, microstructures and impact properties of vanadium alloys

Fracture toughness and tensile behavior of ferritic–martensitic steels irradiated at low temperatures

Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels

Irradiation creep of the US Heat 832665 of V–4Cr–4Ti

Threshold helium concentration required to initiate cracking during welding of irradiated stainless steel

1.05 - Effect of Radiation on Strength and Ductility of Metals and Alloys

Biaxial thermal creep of two heats of V4Cr4Ti at 700 and 800 °C in a liquid lithium environment

Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773 K up to 5 dpa

Modeling of strengthening mechanisms in irradiated fusion reactor first wall alloys

Influence of details of reactor history on microstructural development during neutron irradiation

Stress-strain relations of irradiated stainless steels below 673 K

Impurity effects on reduced-activation ferritic steels developed for fusion applications

Empirical relations for tensile properties of austenitic stainless steels irradiated in mixed-spectrum reactors

Low-temperature irradiation creep of fusion reactor structural materials

Fracture toughness of candidate materials for ITER first wall, blanket, and shield structures

Radiation effects at fusion reactor He : dpa ratios: Overview of US/Japan spectrally tailored experiments

Creep of V–4Cr–4Ti in a lithium environment

Gas tungsten arc welding of vanadium alloys with impurity control

Creep behavior of reduced activation ferritic/martensitic steels irradiated at 573 and 773K up to 5dpa

The response of austenitic steels to radiation damage

Post irradiation tensile and fatigue behavior of austenitic PCA stainless steels irradiated in HFIR

Microstructure–fracture toughness relationship of vanadium alloy/stainless steel brazed joints

Furnace brazing type 304 stainless steel to vanadium alloy (V–5Cr–5Ti)

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