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First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S667-S671

2011

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The deuterium depth profile in neutron-irradiated tungsten exposed to plasma

Physica scripta, 2011-12, Vol.2011, p.014051

2011

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Comparative assessment of hypothalamic-pituitary-adrenal axis suppression secondary to intrabursal injection of different glucocorticoids: a pilot study

Journal of endocrinological investigation, 2019-09, Vol.42 (9), p.1117-1124

2019

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Development of advanced hydrogen permeation sensors to measure Q2 concentration in lead-lithium eutectic alloy

Fusion engineering and design, 2017-11, Vol.124, p.735-739

2017

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Evaluation of Low Dose Silicon Carbide Temperature Monitors

IEEE transactions on nuclear science, 2020-04, Vol.67 (4), p.585-591

2020

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THALLIUM: An experimental facility for simulation of HCLL In-box LOCA and validation of RELAP5-3D system code

Fusion engineering and design, 2017-11, Vol.123, p.102-106

2017

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Current design of the European TBM systems and implications on DEMO breeding blanket

Fusion engineering and design, 2016-11, Vol.109-111, p.1326-1330

2016

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The biological acetabular reconstruction with bone allografts in hip revision arthroplasty

Musculoskeletal surgery, 2019-08, Vol.103 (2), p.173-179

2019

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Control of molten salt corrosion of fusion structural materials by metallic beryllium

Journal of nuclear materials, 2009-04, Vol.386, p.1102-1106

2009

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Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.1469-1475

2014

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Evaluation of Low Dose Silicon Carbide Temperature Monitors

EPJ Web of Conferences, 2020-01, Vol.225, p.4002

2020

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Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE

Journal of nuclear materials, 2009-06, Vol.390, p.709-712

2009

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Overview of the US–Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten

Fusion engineering and design, 2012-08, Vol.87 (7-8), p.1166-1170

2012

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Tritium transport modeling for breeding blanket: State of the art and strategy for future development in the EU fusion program

Fusion engineering and design, 2012-08, Vol.87 (5-6), p.793-797

2012

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Measurement of tritium permeation in flibe (2LiF–BeF 2)

Fusion engineering and design, 2008-12, Vol.83 (7), p.1331-1334

2008

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Application of tritium imaging plate technique to examine tritium behaviors on the surface and in the bulk of plasma-exposed materials

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S769-S772

2011

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Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems

Fusion engineering and design, 2015-10, Vol.96-97, p.56-63

2015

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Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop

Fusion engineering and design, 2015-10, Vol.96-97, p.212-216

2015

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Strategy for the development of EU Test Blanket Systems instrumentation

Fusion engineering and design, 2013-10, Vol.88 (9-10), p.2440-2443

2013

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Tritium Processing for the European Test Blanket Systems: Current Status of the Design and Development Strategy

Fusion science and technology, 2015-04, Vol.67 (3), p.543-546

2015

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An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.1336-1340

2011

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The F4E programme on nuclear data validation and nuclear instrumentation techniques for TBM in ITER

Fusion engineering and design, 2014-10, Vol.89 (9-10), p.2169-2173

2014

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Implementation of Tritium Permeation Models in the CFD Code Fluent

Fusion science and technology, 2011-11, Vol.60 (4), p.1564-1567

2011

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An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

Fusion engineering and design, 2006-02, Vol.81 (1), p.461-467

2006

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Overview of Recent Tritium Experiments in TPE

Fusion science and technology, 2011-11, Vol.60 (4), p.1495-1498

2011

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First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE

The deuterium depth profile in neutron-irradiated tungsten exposed to plasma

Comparative assessment of hypothalamic-pituitary-adrenal axis suppression secondary to intrabursal injection of different glucocorticoids: a pilot study

Development of advanced hydrogen permeation sensors to measure Q2 concentration in lead-lithium eutectic alloy

Evaluation of Low Dose Silicon Carbide Temperature Monitors

THALLIUM: An experimental facility for simulation of HCLL In-box LOCA and validation of RELAP5-3D system code

Current design of the European TBM systems and implications on DEMO breeding blanket

The biological acetabular reconstruction with bone allografts in hip revision arthroplasty

Control of molten salt corrosion of fusion structural materials by metallic beryllium

Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO

Evaluation of Low Dose Silicon Carbide Temperature Monitors

Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE

Overview of the US–Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten

Tritium transport modeling for breeding blanket: State of the art and strategy for future development in the EU fusion program

Measurement of tritium permeation in flibe (2LiF–BeF 2)

Application of tritium imaging plate technique to examine tritium behaviors on the surface and in the bulk of plasma-exposed materials

Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems

Development of a model for the thermal-hydraulic characterization of the He-FUS3 loop

Strategy for the development of EU Test Blanket Systems instrumentation

Tritium Processing for the European Test Blanket Systems: Current Status of the Design and Development Strategy

An overview of research activities on materials for nuclear applications at the INL Safety, Tritium and Applied Research facility

The F4E programme on nuclear data validation and nuclear instrumentation techniques for TBM in ITER

Implementation of Tritium Permeation Models in the CFD Code Fluent

An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design

Overview of Recent Tritium Experiments in TPE

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