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Tritium permeability in polycrystalline tungsten

Fusion engineering and design, 2019-09, Vol.146 (PB), p.1988-1992

2019

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Tritium permeability measurement in hydrogen-tritium system

Fusion engineering and design, 2018-04, Vol.129, p.134-139

2018

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Low tritium partial pressure permeation system for mass transport measurement in lead lithium eutectic

Fusion engineering and design, 2016-01, Vol.102 (C), p.8-13

2016

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TPE upgrade for enhancing operational safety and improving in-vessel tritium inventory assessment in fusion nuclear environment

Fusion engineering and design, 2016-11, Vol.109-111 (PB), p.1077-1081

2016

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Lessons learned in several laboratory upgrades

ACS Chemical Health & Safety., 2018-11, Vol.25 (6), p.3-5

2018

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Initial studies of tritium behavior in flibe and flibe-facing material

Fusion engineering and design, 2002-11, Vol.61, p.783-788

2002

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Deuterium/tritium behavior in Flibe and Flibe-facing materials

Journal of nuclear materials, 2004-08, Vol.329, p.1327-1331

2004

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The impact of specific surface area on the retention of deuterium in carbon fiber composite materials

Fusion engineering and design, 2009-06, Vol.84 (2), p.1068-1071

2009

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Deuterium retention in W, W1%La, C-coated W and W2C

Journal of nuclear materials, 2001-03, Vol.290-293, p.38-41

2001

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Deuterium retention in W, W1%La, C-coated W and W 2C

Journal of nuclear materials, 2001, Vol.290, p.38-41

2001

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Oxygen reactivity of a carbon fiber composite

Fusion engineering and design, 2003-09, Vol.69 (1), p.663-667

2003

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Steam oxidation of PFC materials for advanced tokamaks

Journal of nuclear materials, 2002-12, Vol.307, p.1375-1379

2002

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Steam-chemical reactivity for irradiated beryllium

Journal of nuclear materials, 1998-10, Vol.258, p.750-756

1998

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The Safety and Tritium Applied Research (STAR) Facility: Status-2004

Fusion science and technology, 2005-08, Vol.48 (1), p.243-249

2005

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Steam chemical reactivity of Be pebbles and Be powder

Journal of nuclear materials, 2000-12, Vol.283, p.1463-1467

2000

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Oxidation and volatilization from tungsten brush high heat flux armor during steam exposure

Fusion engineering and design, 2001-04, Vol.54 (3), p.583-591

2001

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Deuterium transport in Cu, CuCrZr, and Cu/Be

Journal of nuclear materials, 1999-03, Vol.266 (1-3), p.761-765

1999

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Flibe-D{sub 2} Permeation Experiment and Analysis

Fusion science and technology, 2003-09, Vol.44 (2)

2003

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Chemical reactivity and mobilization of beryllium exposed to steam

Fusion engineering and design, 1997-11, Vol.37 (4), p.543-552

1997

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Hydrogen permeation properties of plasma-sprayed tungsten

Journal of nuclear materials, 1994-09, Vol.212, p.1416-1420

1994

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Hydrogen transport behavior of beryllium

Journal of nuclear materials, 1992-12, Vol.196, p.986-991

1992

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Steam-chemical reactivity studies for irradiated beryllium

Journal of fusion energy, 1997-06, Vol.16 (1-2), p.101-108

1997

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Implanted deuterium retention and release in carbon-coated beryllium

Journal of fusion energy, 1997-06, Vol.16 (1-2), p.95-100

1997

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Deuterium Transport and Trapping in Polycrystalline Tungsten

Fusion Technology; (United States), 1992-03, Vol.21 (2P2), p.745-752

1992

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BET surface area measurements of materials for fusion safety studies

17th IEEE/NPSS Symposium Fusion Engineering (Cat. No.97CH36131), 1997, Vol.1, p.183-187 vol.1

1997

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Tritium permeability in polycrystalline tungsten

Tritium permeability measurement in hydrogen-tritium system

Low tritium partial pressure permeation system for mass transport measurement in lead lithium eutectic

TPE upgrade for enhancing operational safety and improving in-vessel tritium inventory assessment in fusion nuclear environment

Lessons learned in several laboratory upgrades

Initial studies of tritium behavior in flibe and flibe-facing material

Deuterium/tritium behavior in Flibe and Flibe-facing materials

The impact of specific surface area on the retention of deuterium in carbon fiber composite materials

Deuterium retention in W, W1%La, C-coated W and W2C

Deuterium retention in W, W1%La, C-coated W and W 2C

Oxygen reactivity of a carbon fiber composite

Steam oxidation of PFC materials for advanced tokamaks

Steam-chemical reactivity for irradiated beryllium

The Safety and Tritium Applied Research (STAR) Facility: Status-2004

Steam chemical reactivity of Be pebbles and Be powder

Oxidation and volatilization from tungsten brush high heat flux armor during steam exposure

Deuterium transport in Cu, CuCrZr, and Cu/Be

Flibe-D{sub 2} Permeation Experiment and Analysis

Chemical reactivity and mobilization of beryllium exposed to steam

Hydrogen permeation properties of plasma-sprayed tungsten

Hydrogen transport behavior of beryllium

Steam-chemical reactivity studies for irradiated beryllium

Implanted deuterium retention and release in carbon-coated beryllium

Deuterium Transport and Trapping in Polycrystalline Tungsten

BET surface area measurements of materials for fusion safety studies

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