Manufacturing and high heat flux testing of flat-type W/Cu/CuCrZr mock-up by HIP assisted brazing process

Mou, Nanyu; Han, Lijun; Yao, Damao; Pan, Zhiwei; Li, Lei; Cao, Lei; Duan, Mianjun

doi:10.1016/j.fusengdes.2021.112670

Cited by 35 publications

(12 citation statements)

References 18 publications

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“…This subsection establishes a method for simulating fatigue crack propagation of the W-Cu interface at multiple scales. The W-Cu bimetallic composite used for the fusion divertor components need to pass severe high heat flux tests, meeting the requirement to withstand steady-state heat fluxes of up to 10 MW/m 2 over thousands of cycles without any significant damage [17] [41] [42]. During the test, the W-Cu interface suffers a huge cyclic stress at the interface due to the inconsistent coefficient of thermal expansion during the heating and cooling process, which in turn leads to interface cracking and failure.…”

Section: Fatigue Crack Propagation Of the W-cu Interface At Multiple ...mentioning

confidence: 99%

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Multi-scale simulations of the mechanical behaviors of the W-Cu joint interface with a diffusion layer

Chen

Xie

Huang

2023

Preprint

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At the interface of W-Cu after direct jointing, diffusion layers with a thickness of approximately 22 nm are present but often overlooked in simulations of mechanical properties. This study establish an interface model with a W-Cu diffusion layer using molecular dynamics (MD). The influence of the diffusion layer on the elastic-plastic behaviors, dissipation mechanisms and fracture properties of the interface is analyzed under mode-I (perpendicular to the interface) and mode-II (parallel to the interface). The results demonstrate that the interface model with a diffusion layer exhibits superior mechanical properties under mode-I and mode-II loading when compared to the model without a diffusion layer. Furthermore, a multi-scale method based on the classical Paris law is then proposed, which combines molecular dynamics (MD) and finite element methods to investigate the fatigue crack propagation of W-Cu bimetallic composites under cyclic loading and predict their fatigue life. The findings of this study are meaningful for improving the mechanical properties of W-Cu interface materials, predicting the material's lifespan, and guiding related engineering applications.

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Section: Fatigue Crack Propagation Of the W-cu Interface At Multiple ...mentioning

confidence: 99%

“…The top tungsten surface exerts a periodic 10 MW/m 2 heat fluw, and Fig. 12(a) shows the heat flux loading curve at the tungsten surface (2s to reach a steady state of target heat flux, 15 s loading with constant target heat flux, 2 s rapid cooling to a steady state and 15 s stop loading [17]).…”

Section: Molecular Dynamics Simulation Of Fatigue Crack Propagationmentioning

confidence: 99%

Multi-scale simulations of the mechanical behaviors of the W-Cu joint interface with a diffusion layer

Chen

Xie

Huang

2023

Preprint

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“…Mitteau et al proposed thermal time constant to characterize the delay before the thermal steady state, which allows the state of the component to be assessed. It is based on the observation of the surface temperature of the toroidal pumping limiter (TPL) in Tore Supra [1][2][3][4]. Higher thermal time constants in degraded structures compared to intact structures.…”

Section: Introductionmentioning

confidence: 99%

A new method for characterizing the heat transfer capacity of the divertor and high heat flux components

et al. 2023

Self Cite

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The divertor is usually exposed to extreme incident heat flux conditions in nuclear fusion engineering and its ability to remove the heat is extremely crucial for the safe operation of magnetic confinement nuclear fusion device. The evaluation of the heat removal capacity of the divertor has been always based on high heat flux (HHF) tests. Yet such methods are only available for the small size of experimental components, it is more difficult to compare under different loading and cooling conditions. In order to assess the heat removal capacity in real time and accurately, a new method was developed to characterize the heat removal capacity of the divertor and other high heat load components based on the cooling water thermal decay time constant, the time constants model has also been established. The thermal decay time constant was obtained by fitting the characteristic curves of the water temperature differences with time during the cooling phase of different components under HHF tests. This index is used to quantitatively analyze, characterize and evaluate the heat transfer capacity of the system of the divertor.

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“…In order to compare the heat-exhaust performance between the ITER-like monoblock PFUs and the flat-type PFUs as target plates [31], the monoblock PFUs are used in toroidally 3/4 of the lower divertor and the flat-type PFUs are used in toroidally 1/4 of the lower divertor. In addition, the flat-type PFUs are used in the dome and end boxes, as shown in figure 5.…”

Section: Introduction To the New Lower Divertor Designmentioning

confidence: 99%

“…The stainless-steel back plates are slotted for water channels. The newly developed flat-type PFUs have passed high-heat-flux test with 1000 load cycles at 20 MW m −2 [31]. The heat exhaust capability appears to be better than that of the monoblock PFUs.…”

Section: Introduction To the New Lower Divertor Designmentioning

confidence: 99%

Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST

Wang

Yao

et al. 2021

Nucl. Fusion

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A new lower tungsten divertor has been developed and installed in the EAST superconducting tokamak to replace the previous graphite divertor with power handling capability increasing from <2 MW m−2 to ∼10 MW m−2, aiming at achieving long-pulse H-mode operations in a full metal wall environment with the steady-state divertor heat flux of ∼10 MW m−2. A new divertor concept, ‘corner slot’ (CS) divertor, has been employed. By using the ‘corner effect’, a strongly dissipative divertor with the local buildup of high neutral pressure near the corner can be achieved, so that stable detachment can be maintained across the entire outer target plate with a relatively lower impurity seeding rate, at a separatrix density compatible with advanced steady-state core scenarios. These are essential for achieving efficient current drive with low-hybrid waves, a low core impurity concentration and thus a low loop voltage for fully non-inductive long-pulse operations. Compared with the highly closed small-angle-slot divertor in DIII-D, the new divertor in EAST exhibits the following merits: (1) a much simpler geometry with integral cassette body structure, combining vertical and horizontal target plates, which are more suitable for actively water-cooled W/Cu plasma facing components, facilitating installation precision control for minimizing surface misalignment, achieving high engineering reliability and lowering the capital cost as well; (2) it has much greater flexibility in magnetic configurations, allowing for the position of the outer strike point on either vertical or horizontal target plates to accommodate a relatively wide triangularity range, δ l = 0.4–0.6, thus enabling to explore various advanced scenarios. A water-cooled copper in-vessel coil has been installed under the dome. Five supersonic molecular beam injection systems have been mounted in the divertor to achieve faster and more precise feedback control of the gas injection rate. Furthermore, this new divertor allows for double null divertor operation and slowly sweeping the outer strike point across the horizontal and vertical target plates to spread the heat flux for long-pulse operations. Preliminary experimental results demonstrate the ‘corner effect’ and are in good agreement with simulations using SOLPS-ITER code including drifts. The EAST new divertor provides a test-bed for the closed divertor concept to achieve steady-state detachment operation at high power. Next step, a more closed divertor, ‘sharp-cornered slot’ divertor, building upon the current CS divertor concept, has been proposed as a candidate for the EAST upper divertor upgrade.

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Manufacturing and high heat flux testing of flat-type W/Cu/CuCrZr mock-up by HIP assisted brazing process

Cited by 35 publications

References 18 publications

Multi-scale simulations of the mechanical behaviors of the W-Cu joint interface with a diffusion layer

Multi-scale simulations of the mechanical behaviors of the W-Cu joint interface with a diffusion layer

A new method for characterizing the heat transfer capacity of the divertor and high heat flux components

Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST

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