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Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions

Journal of nuclear materials, 2013-02, Vol.433 (1-3), p.431-448

2013

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High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110

Journal of nuclear materials, 2009-09, Vol.393 (3), p.433-448

2009

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Thermal Creep of Irradiated Zircaloy Cladding

Journal of ASTM International, 2006-01, Vol.3 (1), p.1-16

2006

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Materials integration issues for high performance fusion power systems

Journal of nuclear materials, 1998-10, Vol.258, p.65-73

1998

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Vanadium-base alloys for fusion first-wall/blanket applications

International journal of refractory metals & hard materials, 2000, Vol.18 (4), p.213-224

2000

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Irradiation creep of vanadium-base alloys

Journal of nuclear materials, 1998-10, Vol.258, p.1471-1475

1998

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Determination of actinide and fission-product isotopes in very-high-burnup spent nuclear fuel

Journal of radioanalytical and nuclear chemistry, 2008-07, Vol.277 (1), p.59-64

2008

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Revision of the tensile database for V–Ti and V–Cr–Ti alloys tested at ANL

Journal of nuclear materials, 1998-10, Vol.258, p.1523-1527

1998

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Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Journal of Nuclear Materials, 1992-03, Vol.187 (1), p.1-31

1992

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Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding

Journal of nuclear science and technology, 2006-09, Vol.43 (9), p.1054

2006

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Modeling the behavior of metallic fast reactor fuels during extended transients

Journal of nuclear materials, 1993-09, Vol.204, p.203-211

1993

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Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

Journal of nuclear materials, 1993-09, Vol.204, p.194-202

1993

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Progress in tritium retention and release modeling for ceramic breeders

Fusion engineering and design, 1995-03, Vol.28 (1-2), p.240-251

1995

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Effects of low-temperature neutron irradiation on mechanical properties of vanadium-base alloys

Journal of nuclear materials, 2000-12, Vol.283-287, p.362-366

2000

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High temperature oxidation behavior of Zr-1Nb cladding alloy E110

Journal of nuclear materials, 2009-09, Vol.393 (3 ; Sep. 15, 2009)

2009

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Thermal and tritium transport in Li2O and Li2ZrO3

Journal of nuclear materials, 1996-10, Vol.233-237, p.1462-1466

Billone, M.C.

1996

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Tensile and impact properties of V–4Cr–4Ti alloy heats 832665 and 832864

Journal of nuclear materials, 2000-12, Vol.283-287, p.633-636

2000

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Diffusion/desorption of tritium from irradiated beryllium

Journal of nuclear materials, 1994-09, Vol.212, p.948-953

1994

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Examination of Spent Pressurized Water Reactor Fuel Rods After 15 Years in Dry Storage

Nuclear technology, 2003-11, Vol.144 (2), p.186-200

2003

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Materials for breeding blankets

Journal of nuclear materials, 1996-10, Vol.233, p.72-81

1996

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The influence of surface desorption on tritium recovery and inventory in fusion solid breeders

Journal of nuclear materials, 1986-11, Vol.141, p.316-320

Billone, M.C.

1986

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Advancements in the behavioral modeling of fuel elements and related structures

Nuclear engineering and design, 1992-05, Vol.134 (1), p.23-36

1992

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Status of beryllium development for fusion applications

Fusion engineering and design, 1995-03, Vol.27 (1-2), p.179-190

1995

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Cochlear Inner and Outer Hair Cells: Functional Differences

Science (American Association for the Advancement of Science), 1972-07, Vol.177 (4046), p.356-358

1972

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TIARA analysis of tritium inventory in Li2O

Fusion engineering and design, 1995-03, Vol.28 (1-2), p.313-318

BILLONE, M. C

1995

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Ductile-to-brittle transition temperature for high-burnup cladding alloys exposed to simulated drying-storage conditions

High-temperature steam-oxidation behavior of Zr-1Nb cladding alloy E110

Thermal Creep of Irradiated Zircaloy Cladding

Materials integration issues for high performance fusion power systems

Vanadium-base alloys for fusion first-wall/blanket applications

Irradiation creep of vanadium-base alloys

Determination of actinide and fission-product isotopes in very-high-burnup spent nuclear fuel

Revision of the tensile database for V–Ti and V–Cr–Ti alloys tested at ANL

Modeling of tritium release from ceramic breeders: Status and some implications for next-step devices

Radial-hydride Embrittlement of High-burnup Zircaloy-4 Fuel Cladding

Modeling the behavior of metallic fast reactor fuels during extended transients

Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests

Progress in tritium retention and release modeling for ceramic breeders

Effects of low-temperature neutron irradiation on mechanical properties of vanadium-base alloys

High temperature oxidation behavior of Zr-1Nb cladding alloy E110

Thermal and tritium transport in Li2O and Li2ZrO3

Tensile and impact properties of V–4Cr–4Ti alloy heats 832665 and 832864

Diffusion/desorption of tritium from irradiated beryllium

Examination of Spent Pressurized Water Reactor Fuel Rods After 15 Years in Dry Storage

Materials for breeding blankets

The influence of surface desorption on tritium recovery and inventory in fusion solid breeders

Advancements in the behavioral modeling of fuel elements and related structures

Status of beryllium development for fusion applications

Cochlear Inner and Outer Hair Cells: Functional Differences

TIARA analysis of tritium inventory in Li2O

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