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High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities

Journal of nuclear materials, 2007-08, Vol.367, p.1422-1431

2007

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Technological challenges at ITER plasma facing components production in Russia

Fusion engineering and design, 2016-11, Vol.109-111, p.1028-1034

2016

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Overview of JSC “NIKIET” activity on ITER Procurement Arrangements

Fusion engineering and design, 2016-11, Vol.109-111, p.61-72

2016

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High heat flux components with beryllium armour: From the small-scale mock-ups to the full-scale prototype of the ITER first wall panel

Fusion engineering and design, 2024-06, Vol.203, p.114473, Article 114473

2024

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Fabrication and thermal tests of SS/Cu bimetal plate for the use in the concept of flowing liquid lithium layer in tokamak limiters and divertors

Fusion engineering and design, 2022-11, Vol.184, p.113313, Article 113313

2022

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Overview of manufacturing technologies under development in Russia for ITER plasma facing components

Fusion engineering and design, 2018-11, Vol.136, p.527-533

2018

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Analyses results of the EHF FW Panel with welded fingers

Fusion engineering and design, 2014-10, Vol.89 (7-8), p.937-948

2014

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Preparation to manufacturing of ITER plasma facing components in Russia

Fusion engineering and design, 2011-10, Vol.86 (6), p.576-579

2011

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Erosion of a-C:H films deposited on W, Mo, and stainless steel under interaction with air glow discharge

Journal of nuclear materials, 2011-08, Vol.415 (1), p.S129-S132

2011

Volltextzugriff (PDF)

Thermal mechanical analysis of the Enhanced Heat Flux First Wall panel

Fusion engineering and design, 2012-08, Vol.87 (7-8), p.1146-1160

2012

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Development of fabrication technology and investigation of properties of steel-to-bronze joints suggested for ITER HHF components

Journal of nuclear materials, 2009-04, Vol.386, p.927-930

2009

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Analysis of a beryllium—copper diffusion joint after HHF test

Journal of nuclear materials, 1996-10, Vol.233 (1-3), p.616-619

1996

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ITER FW cooling by a flat channel, adapted to low flow rate and high pressure drop

Fusion engineering and design, 2011-12, Vol.86 (12), p.2971-2982

2011

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Erosion of a-C:H films under interaction with nitrous oxide afterglow discharge

Journal of nuclear materials, 2009-06, Vol.390, p.639-642

2009

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Increased recombination of CH3 radicals on stainless steel

Journal of nuclear materials, 2005-03, Vol.337-339, p.892-896

2005

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Status of international collaborative efforts on selected ITER materials

Journal of nuclear materials, 2000-12, Vol.283, p.962-967

2000

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Experimental modeling of transport and deposition of hydrocarbon radicals on ITER-FEAT cold trap

Journal of nuclear materials, 2003-03, Vol.313, p.342-347

2003

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Optimization of armour geometry and bonding techniques for tungsten-armoured high heat flux components

Fusion Engineering and Design, 2002-11, Vol.61, p.185-190

2002

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Laboratory study of the transport and condensation of hydrocarbon radicals and its consequences for mitigating the tritium inventory in the ITER-FEAT divertor

Journal of nuclear materials, 2001-03, Vol.290, p.394-397

2001

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Deuterium retention in codeposited layers and carbon materials exposed to high flux D-plasma

Journal of nuclear materials, 1999-05, Vol.271, p.418-422

1999

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Some engineering aspects of high heat flux components for volumetric neutron source based on spherical torus

Fusion engineering and design, 1999, Vol.45 (3), p.303-316

1999

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Deuterium trapping by carbon materials for tokamak plasma-facing components

Fusion engineering and design, 1998-12, Vol.43 (2), p.129-145

1998

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Swelling, strengthening and embrittlement of beryllium under neutron irradiation to a fluence of 1.72 × 1021 n/cm2 (E ≥ 0.85 MeV) at a temperature of 330–350°C. The role of main structure factors

Journal of nuclear materials, 1996-10, Vol.233-237, p.891-897

1996

Volltextzugriff (PDF)

Swelling, strengthening and embrittlement of beryllium under neutron irradiation to a fluence of 1.72 × 10 21 n/cm 2 ( E ≥ 0.85 MeV) at a temperature of 330–350°C. The role of main structure factors

Journal of nuclear materials, 1996, Vol.233, p.891-897

1996

Volltextzugriff (PDF)

Metallographic analysis and strength investigation of different BeCu joints in the temperature range RT—350°C

Journal of nuclear materials, 1996-10, Vol.233, p.626-631

1996

Volltextzugriff (PDF)

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High heat flux testing of plasma facing materials and components – Status and perspectives for ITER related activities

Technological challenges at ITER plasma facing components production in Russia

Overview of JSC “NIKIET” activity on ITER Procurement Arrangements

High heat flux components with beryllium armour: From the small-scale mock-ups to the full-scale prototype of the ITER first wall panel

Fabrication and thermal tests of SS/Cu bimetal plate for the use in the concept of flowing liquid lithium layer in tokamak limiters and divertors

Overview of manufacturing technologies under development in Russia for ITER plasma facing components

Analyses results of the EHF FW Panel with welded fingers

Preparation to manufacturing of ITER plasma facing components in Russia

Erosion of a-C:H films deposited on W, Mo, and stainless steel under interaction with air glow discharge

Thermal mechanical analysis of the Enhanced Heat Flux First Wall panel

Development of fabrication technology and investigation of properties of steel-to-bronze joints suggested for ITER HHF components

Analysis of a beryllium—copper diffusion joint after HHF test

ITER FW cooling by a flat channel, adapted to low flow rate and high pressure drop

Erosion of a-C:H films under interaction with nitrous oxide afterglow discharge

Increased recombination of CH3 radicals on stainless steel

Status of international collaborative efforts on selected ITER materials

Experimental modeling of transport and deposition of hydrocarbon radicals on ITER-FEAT cold trap

Optimization of armour geometry and bonding techniques for tungsten-armoured high heat flux components

Laboratory study of the transport and condensation of hydrocarbon radicals and its consequences for mitigating the tritium inventory in the ITER-FEAT divertor

Deuterium retention in codeposited layers and carbon materials exposed to high flux D-plasma

Some engineering aspects of high heat flux components for volumetric neutron source based on spherical torus

Deuterium trapping by carbon materials for tokamak plasma-facing components

Swelling, strengthening and embrittlement of beryllium under neutron irradiation to a fluence of 1.72 × 1021 n/cm2 (E ≥ 0.85 MeV) at a temperature of 330–350°C. The role of main structure factors

Swelling, strengthening and embrittlement of beryllium under neutron irradiation to a fluence of 1.72 × 10 21 n/cm 2 ( E ≥ 0.85 MeV) at a temperature of 330–350°C. The role of main structure factors

Metallographic analysis and strength investigation of different BeCu joints in the temperature range RT—350°C

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