High heat flux testing for W/Cu monoblock PFUs with varying defects

Zhuang, Qiya; Mou, Nanyu; Han, Lijun; Li, Qiang; Li, Lei; Zi, Pengfei; Wang, Zhaoliang; Chen, Zhe; Peng, Wuqinliang; Cao, Lei; Yao, Damao

doi:10.1016/j.fusengdes.2022.113137

Cited by 9 publications

(2 citation statements)

References 12 publications

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“…The PFUs that meet the acceptance criteria are defined no-defects PFUs. The PFUs with a small number of 2 × 3 mm defects are defined as minor defects PFUs (total area less than 10% of the inspection area), and the PFUs with large number of 2 × 3 mm defects are major defects PFUs [7]. It is worth noting that the main objective of this study was to investigate the feasibility of thermal decay time constants in evaluating the heat transfer performance of defective PFCs.…”

Section: Research Subjectsmentioning

confidence: 99%

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

et al. 2023

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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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Section: Research Subjectsmentioning

confidence: 99%

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

et al. 2023

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“…As a long pulse device similar to ITER pulse duration, EAST has been installed numerous W/Cu monoblocks for divertor targets and limiters to enhance its high heat load exhaust capacity [8]. Before the winter plasma campaign of 2022, a new limiter mainly composed of W/Cu monoblocks was successfully developed and installed in EAST.…”

Section: Introductionmentioning

confidence: 99%

Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments

Guo,

Zhu,

Yan

et al. 2024

Nucl. Fusion

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In the ITER and future fusion devices, W/Cu monoblocks will be used as divertor target which are exposed to both steady state heat load and transient heat flux. Especially, the transient heat flux up to 10 GW/m2 during plasma disruption, is expected to induce the shallow surface damages, such as melting, and even boiling of W/Cu monoblocks. Thus, the performance of damaged W/Cu monoblocks under subsequent long-term plasma discharges is a key concern that needs to be verified and tested on existing tokamaks. Since 2022, a new type of main limiter composed of ITER-like W/Cu monoblocks has been installed and tested in EAST. The surface of W/Cu monoblocks of the limiter was damaged by the transient heat flux during the early stages of plasma construction. Subsequently, they were subjected to long-term plasma discharges over 2600 shots in normal plasma discharge conditions. This circumstance conveniently facilitates the discussion of the performance of W/Cu monoblocks with damaged surfaces especially a melting edge with hill structure under prolonged exposure to plasma. In general, the shallow damage resulting from transient heat flux on W/Cu monoblocks appears to have minimal impact on the heat exhaust capacity under steady-state heat loads, as indicated by both experimental monitoring and numerical simulation results. However, shallow melting, leading to a change in surface structure and the formation of hills, could theoretically increase local temperatures, creating potential hot spots. This phenomenon requires further validation through dedicated experiments. Moreover, the brittleness of the near-surface layer may give rise to brittle destructions, such as cracks and even dust particles, posing an additional concern. These findings yield unique qualitative conclusions that can be referenced for ITER and other fusion devices.

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

2023

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High heat flux testing for W/Cu monoblock PFUs with varying defects

Cited by 9 publications

References 12 publications

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

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

Long-term plasma exposure of ITER-like W/Cu monoblocks with pre-damaged surfaces in EAST experiments

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

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