ITER tungsten divertor design development and qualification program

Hirai, T.; Escourbiac, F.; Carpentier-Chouchana, S.; Fedosov, A. M.; Ferrand, L.; Jokinen, Tommi; Komarov, V.; Kukushkin, A.S.; Merola, M.; Mitteau, R.; Pitts, R.A.; Shu, W. M.; Sugihara, M.; Riccardi, B.; Suzuki, Satoshi; Villari, R.

doi:10.1016/j.fusengdes.2013.05.010

Cited by 194 publications

(82 citation statements)

References 5 publications

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“…This is obtained by the installation of electromagnetic coils in the vacuum vessel in order to create an upper and lower X-point while adapting the plasma environment to this new configuration. After a commissioning phase, the lower divertor will be fully metallic and actively cooled, with ITER-like tungsten (W) monoblocks [2,3]. The upper divertor target (Fig.…”

Section: Introductionmentioning

confidence: 99%

Design and preliminary thermal validation of the WEST actively cooled upper divertor

Richou

Missirlian

Guilhem

et al. 2015

Fusion Engineering and Design

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Section: Introductionmentioning

confidence: 99%

Design and preliminary thermal validation of the WEST actively cooled upper divertor

Richou

Missirlian

Guilhem

et al. 2015

Fusion Engineering and Design

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“…In all the experiments, polished double-forged tungsten (DFW) samples of dimensions (12 × 12 × 5) mm 3 were used as targets. The material was prepared for experiments by PLANSEE and supplied by IAEA (International Atomic Energy Agency) for Round-Robin tests in different facilities.…”

Section: Experimental Set-upmentioning

confidence: 99%

“…In construction of magnetic confi nement fusion facilities, tungsten (W) is currently considered as the most perspective material for use as a plasma--facing component due to its high melting point, The experimental and theoretical investigations of damage development and distribution in double-forged tungsten under plasma irradiation-initiated extreme heat loads detachment properties, and low retention of D and T [3,4]. Nevertheless, tungsten has several disadvantages, which may limit the use of it as an armour material -brittleness, poor creep strength and re--crystallisation.…”

Section: Introductionmentioning

confidence: 99%

The experimental and theoretical investigations of damage development and distribution in double-forged tungsten under plasma irradiation-initiated extreme heat loads

et al. 2016

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Abstract. The infl uence of extreme heat loads, as produced by a multiple pulses of non-homogeneous fl ow of slow plasma (0.1-1 keV) and fast ions (100 keV), on double-forged tungsten (DFW) was investigated. For generation of deuterium plasma and fast deuterons, plasma-focus devices PF-12 and PF-1000 are used. Depending on devices and conditions, the power fl ux density of plasma varied in a range of 10 7 -10 10 W/cm 2 with pulse duration of 50-100 ns. Power fl ux density of fast ions was 10 10 -10 12 W/cm 2 at the pulse duration of 10-50 ns. To achieve the combined effect of different kind of plasmas, the samples were later irradiated with hydrogen plasma (10 5 W/cm 2 , 0.25 ms) by a QSPA Kh-50 plasma generator. Surface modifi cation was analysed by scanning electron microscopy (SEM) and microroughness measurements. For estimation of damages in the bulk of material, an electrical conductivity method was used. Investigations showed that irradiation of DFW with multiple plasma pulses generated a mesh of micro-and macrocracks due to high heat load. A comparison with single forged tungsten (W) and tungsten doped with 1% lanthanum-oxide (WL10) reveals the better crack-resistance of DFW. Also, sizes of cells formed between the cracks on the DFW's surface were larger than in cases of W or WL10. Measurements of electrical conductivity indicated a layer of decreased conductivity, which reached up to 500 m. It depended mainly on values of power fl ux density of fast ions, but not on the number of pulses. Thus, it may be concluded that bulk defects (weakening bonds between grains and crystals, dislocations, point-defects) were generated due to mechanical shock wave, which was generated by the fast ions fl ux. Damages and erosion of materials under different combined radiation conditions have also been discussed.

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“…R&D and technology integration of high performance materials for plasma facing components (PFCs) and first wall are essential for the early realization of fusion reactor. The advantages of tungsten in high heat flux components (HHFCs) are low plasma sputtering rate, high melting point and low hydrogen retention [1].…”

Section: Introductionmentioning

confidence: 99%

Microstructural modification of W–SiC bonded plate during high temperature exposure

Asakura

Kishimoto

Nakazato

et al. 2016

Fusion Engineering and Design

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ITER tungsten divertor design development and qualification program

Cited by 194 publications

References 5 publications

Design and preliminary thermal validation of the WEST actively cooled upper divertor

Design and preliminary thermal validation of the WEST actively cooled upper divertor

The experimental and theoretical investigations of damage development and distribution in double-forged tungsten under plasma irradiation-initiated extreme heat loads

Microstructural modification of W–SiC bonded plate during high temperature exposure

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