ログイン
Language:

WEKO3

  • トップ
  • ランキング
To
lat lon distance
To

Field does not validate



インデックスリンク

インデックスツリー

メールアドレスを入力してください。

WEKO

One fine body…

WEKO

One fine body…

アイテム

  1. 学会発表・講演等
  2. ポスター発表

Thermal-hydraulic Performance of Water-Cooled Ceramic Breeder Test Blanket Module

https://repo.qst.go.jp/records/2002525
https://repo.qst.go.jp/records/2002525
06f02364-ac3a-4a88-bd69-4de515aafc83
アイテムタイプ 会議発表用資料 / Presentation(1)
公開日 2025-11-17
タイトル
タイトル Thermal-hydraulic Performance of Water-Cooled Ceramic Breeder Test Blanket Module
言語 en
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6670
資源タイプ conference poster
著者 Wenhai Guan

× Wenhai Guan

Wenhai Guan

Search repository
Hirose Takanori

× Hirose Takanori

Hirose Takanori

Search repository
Kawamura Yoshinori

× Kawamura Yoshinori

Kawamura Yoshinori

Search repository
抄録
内容記述 The water-cooled ceramic breeder (WCCB) test blanket module (TBM), developed by Japan, is planned for installation in the ITER #18 equatorial port. This initiative aims to validate tritium breeding and extraction, guiding the exploration of breeding blankets for DEMO. The TBM consists of 56 submodules, a header, and supporting structures, all designed for tritium breeding, fluid management (including cooling water and helium purge gas), and mechanical connections to the TBM shield. The primary structural material for the TBM will be a Japanese reduced activation ferritic martensitic steel known as F82H. The WCCB requires coolant conditions similar to those of a Pressurized Water Reactor (PWR), with normal operation at 15.5 MPa and 280°C, to withstand the thermal load from ITER. Thus, the thermal-hydraulic performance of the WCCB TBM needs to be quantitatively analyzed to ensure adequate heat removal capability in the current structural design. In this study, a physical mock-up of the WCCB TBM, constructed from F82H, will be tested under PWR-like coolant conditions. The testing aims to measure surface temperatures and pressure loss between the inlet and outlet of the mock-up. A computational fluid dynamics (CFD) analysis will also be performed to assess the pressure loss of the physical mock-up and flow velocity, supporting further design work. The physical mock-up is designed based on the current structural design of the WCCB TBM and will be evaluated in a vacuum environment of 10^-4 Pa. The coolant conditions will simulate PWR conditions. Pressure gauges and thermocouples will be installed at the inlet and outlet of the mock-up. A three-dimensional CFD analysis will be conducted using the commercial software ANSYS Fluent, employing a steady flow analysis with a k-ω viscosity model for the coolant channels. The experimental results indicate a homogeneous temperature distribution on the physical mock-up, with no hot spots observed. The monitored surface temperatures corroborate the CFD results regarding flow velocity. The measured pressure loss between the inlet and outlet matches the values predicted by the CFD analysis. A detailed description of the investigation procedures and a discussion of the experimental and CFD analysis results will be presented.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述 16th International Symposium on Fusion Nuclear Technology
発表年月日
日付 2025-11-11
戻る
0
views
See details
Views

Versions

Ver.1 2026-01-19 03:58:05.477137
Show All versions

Share

Share
tweet

Cite as

Other

print

エクスポート

OAI-PMH
  • OAI-PMH JPCOAR 2.0
  • OAI-PMH JPCOAR 1.0
  • OAI-PMH DublinCore
  • OAI-PMH DDI
Other Formats
  • JSON
  • BIBTEX
  • ZIP

コミュニティ

確認

確認

確認


Powered by WEKO3


Powered by WEKO3