T-REX: Numerical tool for tungsten damage assessment for DEMO

Structural lifetime assessment for the DEMO divertor targets: Design-by-analysis approach and outstanding issues

(2021) Jeong-Ha You et al.   FUSION ENGINEERING AND DESIGN

Fracture-mechanical properties of neutron irradiated ITER specification tungsten

(2021) E. Gaganidze et al.   JOURNAL OF NUCLEAR MATERIALS

In situ observation of tungsten plasma-facing components after the first phase of operation of the WEST tokamak

(2021) M. Diez et al.   NUCLEAR FUSION

High heat flux testing of newly developed tungsten components for WEST

(2021) G. Pintsuk et al.   FUSION ENGINEERING AND DESIGN

Nuclear analyses for the design of the ITER-like plasma facing components vertical targets of the DEMO divertor

(2020) Simone Noce et al.   FUSION ENGINEERING AND DESIGN

Recrystallization at high temperature of two tungsten materials complying with the ITER specifications

(2020) M. Richou et al.   JOURNAL OF NUCLEAR MATERIALS

Mechanical properties of tungsten: Recent research on modified tungsten materials in Japan

(2020) Shuhei Nogami et al.   JOURNAL OF NUCLEAR MATERIALS

Tensile properties of powder-metallurgical-processed tungsten alloys after neutron irradiation near recrystallization temperatures

(2020) Takeshi Miyazawa et al.   JOURNAL OF NUCLEAR MATERIALS

An Attempt to Assess Recovery/Recrystallization Kinetics in Tungsten at High Temperature Using Statistical Nanoindentation Analysis

(2020) Liz Karanja et al.   Crystals

Neutron irradiation hardening across ITER diverter tungsten armor

(2020) D. Terentyev et al.   INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS

High-heat-flux technologies for the European demo divertor targets: State-of-the-art and a review of the latest testing campaign

(2020) J.H. You et al.   JOURNAL OF NUCLEAR MATERIALS

Inverse identification of tungsten static recrystallization kinetics under high thermal flux

(2019) A. Durif et al.   FUSION ENGINEERING AND DESIGN

Towards reliable design-by-analysis for divertor plasma facing components – Guidelines for inelastic assessment (part 1: Unirradiated)

(2019) M. Fursdon et al.   FUSION ENGINEERING AND DESIGN

Neutron irradiation effects on the mechanical properties of powder metallurgical processed tungsten alloys

(2019) Takeshi Miyazawa et al.   JOURNAL OF NUCLEAR MATERIALS

Effects of neutron irradiation on the brittle to ductile transition in single crystal tungsten

(2019) R.G. Abernethy et al.   JOURNAL OF NUCLEAR MATERIALS

Thermal diffusivity of tungsten irradiated with protons up to 5.8 dpa

(2018) Jemila Habainy et al.   JOURNAL OF NUCLEAR MATERIALS

Impact of tungsten recrystallization on ITER-like components for lifetime estimation

(2018) A. Durif et al.   FUSION ENGINEERING AND DESIGN

Degradation of tungsten monoblock divertor under cyclic high heat flux loading

(2017) Shuhei Nogami et al.   FUSION ENGINEERING AND DESIGN

Progress in the initial design activities for the European DEMO divertor: Subproject “Cassette”

(2017) J.H. You et al.   FUSION ENGINEERING AND DESIGN

Thermal conductivity reduction of tungsten plasma facing material due to helium plasma irradiation in PISCES using the improved 3-omega method

(2017) Shuang Cui et al.   JOURNAL OF NUCLEAR MATERIALS

Materials testing facilities and programmes for fission and ion implantation damage

(2017) S.M. González de Vicente et al.   NUCLEAR FUSION

Towards a programme of testing and qualification for structural and plasma-facing materials in ‘fusion neutron’ environments

(2017) D. Stork et al.   NUCLEAR FUSION

European DEMO design strategy and consequences for materials

(2017) G. Federici et al.   NUCLEAR FUSION

Irradiation hardening of pure tungsten exposed to neutron irradiation

(2016) Xunxiang Hu et al.   JOURNAL OF NUCLEAR MATERIALS

Predicting the performance of tungsten in a fusion environment: a literature review

(2016) R.G. Abernethy   MATERIALS SCIENCE AND TECHNOLOGY

Progress of ITER full tungsten divertor technology qualification in Japan

(2015) K. Ezato et al.   FUSION ENGINEERING AND DESIGN

Interpretation of the deep cracking phenomenon of tungsten monoblock targets observed in high-heat-flux fatigue tests at 20 MW/m 2

(2015) Muyuan Li et al.   FUSION ENGINEERING AND DESIGN

Fatigue behavior of rolled and forged tungsten at 25°, 280° and 480 °C

(2015) J. Habainy et al.   JOURNAL OF NUCLEAR MATERIALS

Recrystallization kinetics of warm-rolled tungsten in the temperature range 1150–1350 °C

(2014) A. Alfonso et al.   JOURNAL OF NUCLEAR MATERIALS

The WEST programme: Minimizing technology and operational risks of a full actively cooled tungsten divertor on ITER

(2013) André Grosman et al.   FUSION ENGINEERING AND DESIGN

Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading

(2013) G. Pintsuk et al.   FUSION ENGINEERING AND DESIGN

A full tungsten divertor for ITER: Physics issues and design status

(2013) R.A. Pitts et al.   JOURNAL OF NUCLEAR MATERIALS

High heat flux testing of mock-ups for a full tungsten ITER divertor

(2011) P. Gavila et al.   FUSION ENGINEERING AND DESIGN

Microscopic damage of tungsten exposed to deuterium–helium mixture plasma in PISCES and its impacts on retention property

(2011) M. Miyamoto et al.   JOURNAL OF NUCLEAR MATERIALS