Innovative tokamak DEMO first wall and divertor material concepts

Wong, C.P.C.

doi:10.1016/j.jnucmat.2009.01.274

Cited by 16 publications

(6 citation statements)

References 21 publications

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“…Laser heating of Be-coated W supports the simple threshold concept for Be layer removal based on the Be heat of formation. If the arrival rate of Be at the W divertor is sufficiently large, a surface layer of Be could form which might protect the W substrate during transient events [14]. However, there are two problems if relying on Be coatings as a protective measure for W in ITER: 1) the Be layer thickness required to protect the underlying substrate from the expected ELM energy is larger than the expected layer thickness in ITER [15], and 2) the concept of a sacrificial Be layer is undermined by Be-W alloying.…”

Section: Discussionmentioning

confidence: 99%

Transient heating effects on tungsten: Ablation of Be layers and enhanced fuzz growth

Baldwin

Doerner

et al. 2015

Journal of Nuclear Materials

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A pulsed laser in the PISCES-B facility is used to simulate transient heating events such as ELMs and disruptions on W. The first study of enhanced nano-scale W tendril growth ("fuzz") due to cyclic fast transient heating of W exposed to low energy (+ He E~30 eV) He + ions is presented. Fuzz due to transient heating is up to ~10x thicker than the steady state fuzz thickness with no laser heating. A general thermal activation model yields higher values for the activation energy and pre-exponential factor than previously reported in steady state experiments with + He E~60 eV. Transient heating of W exposed to D plasma with Be seeding shows that the removal threshold of Be follows simple energy considerations based on the heat of formation of Be.

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Section: Discussionmentioning

confidence: 99%

Transient heating effects on tungsten: Ablation of Be layers and enhanced fuzz growth

Baldwin

Doerner

et al. 2015

Journal of Nuclear Materials

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“…For the plasma facing components, tungsten is proposed as the main material [8,97], particularly because of its low erosion and tritium retention. For the first wall, heat flux about 0.5 MW m −2 is expected.…”

Section: Demo and New Developmental Materialsmentioning

confidence: 99%

Materials for Fusion Applications

Matějíček¹

2013

Acta Polytech

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An overview of materials foreseen for use or already used in fusion devices is given. The operating conditions, material requirements and characteristics of candidate materials in several specific application segments are briefly reviewed. These include: construction materials, electrical insulation, permeation barriers and plasma facing components. Special attention will be paid to the latter and to the issues of plasma-material interaction, materials joining and fuctionally graded interlayers.

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“…Critical issues include the need for real time boronization or siliconization to maintain the surface coating. Material samples of this low-Z material W surface are being fabricated and will be tested in DIII-D [51].…”

Section: Plasma Materials Interactionmentioning

confidence: 99%

High heat flux components—Readiness to proceed from near term fusion systems to power plants

Raffray¹,

Nygren²,

Whyte³

et al. 2010

Fusion Engineering and Design

125

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A present topic of high interest in magnetic fusion is the "gap" between near-term and longterm concepts for high heat flux components (HHFC), and in particular their application in divertors. This paper focuses on this issue with the aim of characterizing the international status of current HHFC design concepts for ITER and describing the different technologies needed in the designs being developed for fusion power plants. Critical corresponding material and physics aspects are highlighted while evaluating the current readiness level of long-term concepts, identifying the design and R&D gaps, and discussing ways to bridge them.2

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Innovative tokamak DEMO first wall and divertor material concepts

Cited by 16 publications

References 21 publications

Transient heating effects on tungsten: Ablation of Be layers and enhanced fuzz growth

Transient heating effects on tungsten: Ablation of Be layers and enhanced fuzz growth

Materials for Fusion Applications

High heat flux components—Readiness to proceed from near term fusion systems to power plants

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