| アイテムタイプ |
学術雑誌論文 / Journal Article(1) |
| 公開日 |
2026-06-29 |
| タイトル |
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タイトル |
Thermal-hydraulic performance of water-cooled ceramic breeder test blanket module |
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言語 |
en |
| 言語 |
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言語 |
eng |
| 資源タイプ |
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資源タイプ識別子 |
http://purl.org/coar/resource_type/c_6501 |
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資源タイプ |
journal article |
| 著者 |
Wenhai Guan
Ide Hideyuki
Hirose Takanori
Osaka Tsutomu
Kouno Takehiro
Sawahata Osamu
Kawamura Yoshinori
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| 抄録 |
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内容記述タイプ |
Abstract |
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内容記述 |
A comprehensive thermal–hydraulic evaluation of the Water‑Cooled Ceramic Breeder (WCCB) Test Blanket Module (TBM) to be tested in ITER was conducted using a combined approach of Computational Fluid Dynamics (CFD) analyses, finite‑element thermal analyses, and full‑scale experiments. The CFD results showed that most regions of the First Wall (FW) attain coolant velocities above 1 m/s, supporting the validity of previously assumed heat‑transfer coefficients. Localized low‑velocity regions were identified near the partition plate and the outlets of the 3‑mm channels; however, conservative thermal analyses assuming zero heat‑transfer coefficient in these areas confirmed that FW temperatures remain below the F82H limit of 550 °C under both design (0.30 MW/m²) and maximum (0.84 MW/m²) ITER heat loads. Pressure‑drop analyses revealed a total submodule pressure drop of 57.2 kPa, with U‑shaped pipes contributing more than half of the total loss. Full‑scale pressure‑drop measurements, combined with a dedicated bypass loop to isolate inlet and outlet losses, showed good agreement with the CFD predictions for mass flow rates up to 0.1 kg/s. These results validate the numerical models and confirm that the current WCCB TBM submodule satisfies thermal–hydraulic requirements. The established methodology provides a foundation for future optimization and higher‑flow experimental campaigns. |
| 書誌情報 |
Fusion engineering and design
発行日 2026-09
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| DOI |
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識別子タイプ |
DOI |
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関連識別子 |
10.1016/j.fusengdes.2026.115912 |
