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Functional materials for breeding blankets-status and developments

Nuclear fusion, 2017-08, Vol.57 (9), p.92014

2017

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Overview of the ITER TBM Program

Fusion engineering and design, 2012-08, Vol.87 (5-6), p.395-402

2012

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Compact DEMO, SlimCS: design progress and issues

Nuclear fusion, 2009-07, Vol.49 (7), p.075029-075029 (10)

2009

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Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas conditions

Fusion engineering and design, 2008-05, Vol.83 (4), p.580-587

2008

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Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication

Fusion engineering and design, 2006-02, Vol.81 (1), p.645-651

2006

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High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel

Journal of nuclear materials, 2013-07, Vol.438, p.S905-S908

2013

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Search for reality of solid breeder blanket for DEMO

Fusion engineering and design, 2010-12, Vol.85 (7), p.1342-1347

2010

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Reduced activation martensitic steels as a structural material for ITER test blanket

Journal of nuclear materials, 2004-08, Vol.329, p.243-247

2004

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Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

Journal of nuclear materials, 2014-12, Vol.455 (1-3), p.431-435

2014

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Design study of fusion DEMO plant at JAERI

Fusion engineering and design, 2006-02, Vol.81 (8), p.1151-1158

2006

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Torus configuration and materials selection on a fusion DEMO reactor, SlimCS

Journal of nuclear materials, 2009-04, Vol.386, p.888-892

2009

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Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module

Journal of nuclear materials, 2007-08, Vol.367, p.1361-1365

2007

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Corrosion and stress corrosion cracking of ferritic/martensitic steel in super critical pressurized water

Journal of nuclear materials, 2007-08, Vol.367, p.1185-1189

2007

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Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Nuclear fusion, 2003-12, Vol.43 (12), p.1837-1844

2003

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Status and perspective of the R&D on ceramic breeder materials for testing in ITER

Journal of nuclear materials, 2007-08, Vol.367, p.1281-1286

2007

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Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA

Fusion engineering and design, 2010-12, Vol.85 (7), p.1255-1260

2010

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Determination of Hydrogen Diffusion Coefficients in F82H by Hydrogen Depth Profiling with a Tritium Imaging Plate Technique

Fusion science and technology, 2015-03, Vol.67 (2), p.379-381

2015

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R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA

Nuclear fusion, 2009-05, Vol.49 (5), p.055021-055021 (6)

2009

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SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid

Nuclear fusion, 2007-08, Vol.47 (8), p.892-899

2007

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Release behavior of bred tritium from LiAlO2

Journal of nuclear materials, 2004-10, Vol.335 (1), p.70-76

2004

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Chemical form of released tritium from solid breeder materials under the various purge gas conditions

Fusion engineering and design, 2007-10, Vol.82 (15), p.2147-2151

2007

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Interfacial properties of HIP joints between beryllium and reduced activation ferritic/martensitic steel

Fusion engineering and design, 2010-08, Vol.85 (5), p.809-812

2010

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Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles

Journal of nuclear materials, 2011-10, Vol.417 (1-3), p.607-611

2011

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Must we use ferritic steel in TBM?

Fusion engineering and design, 2010-12, Vol.85 (10), p.1896-1902

2010

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Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials

Fusion engineering and design, 2006-02, Vol.81 (1), p.573-577

2006

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Functional materials for breeding blankets-status and developments

Overview of the ITER TBM Program

Compact DEMO, SlimCS: design progress and issues

Tritium diffusivity in crystal grain of Li2TiO3 and tritium release behavior under several purge gas conditions

Joining technologies of reduced activation ferritic/martensitic steel for blanket fabrication

High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel

Search for reality of solid breeder blanket for DEMO

Reduced activation martensitic steels as a structural material for ITER test blanket

Corrosion behavior of F82H exposed to high temperature pressurized water with a rotating apparatus

Design study of fusion DEMO plant at JAERI

Torus configuration and materials selection on a fusion DEMO reactor, SlimCS

Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module

Corrosion and stress corrosion cracking of ferritic/martensitic steel in super critical pressurized water

Design and technology development of solid breeder blanket cooled by supercritical water in Japan

Status and perspective of the R&D on ceramic breeder materials for testing in ITER

Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA

Determination of Hydrogen Diffusion Coefficients in F82H by Hydrogen Depth Profiling with a Tritium Imaging Plate Technique

R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA

SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid

Release behavior of bred tritium from LiAlO2

Chemical form of released tritium from solid breeder materials under the various purge gas conditions

Interfacial properties of HIP joints between beryllium and reduced activation ferritic/martensitic steel

Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles

Must we use ferritic steel in TBM?

Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials

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