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Progress in developing ITER and DEMO first wall technologies at SWIP

J.M. Chen, X. Liu, P.H. Wang, P. Huang, J.B. Wang, L.Z. Cai, F.Y. Jin, X.B. Zhu, Q. Li, Y.Y. Chen2020年被引用 10Nuclear FusionIF 3出版社

The first wall (FW) is key component for ITER and the Chinese DEMO—the China Fusion Engineering Test Reactor (CFETR). It faces burning plasma and has a high heat flux (HHF) surface load. Critical issues and key technologies for manufacturing the ITER and CFETR FW are discussed with regards to thermal fatigue performance, Be/CuCrZr and W/reduced activation ferritic/martensitic (RAFM) steel bonding, material properties and failure mechanisms. Design improvement of the hypervapotron cooling channel and the joint interface structure was done, which increases the thermal fatigue lifetime of the enhanced heat flux (EHF) ITER FW by more than one order of magnitude as indicated by thermo-mechanical analysis. Small mock-ups and full-size EHF FW fingers were manufactured by qualified technologies in sequence. An HHF test of the small mock-ups showed that Be tile size and defects at the Be/CuCrZr interface have a great effect on the fatigue lifetime. Manufacturing tests showed a thick oxygen-free Cu interlayer could provide a good solution for the interface cracking issue. An ITER EHF FW semi-prototype was manufactured with additional two full-size finger pairs that successfully survived the demanding HHF test at 4.7 and 5.9 MW m−2. Various manufacturing technologies for joining W/RAFM steel for the CFETR FW have been studied, including a TiN coating at the interface as a tritium permeation barrier. Hot iso-static pressed W/RAFM steel joints showed a higher bonding strength than brazing joints but varied a lot with the interlayer metals. Further studies are required to optimize the technologies.

日本語訳

第一壁(FW)は、ITERおよび中国のDEMO炉——中国核融合工学試験炉(CFETR)にとって重要な構成要素である。これは燃焼プラズマに面し、高熱流束(HHF)表面負荷を受ける。ITERおよびCFETRのFW製造に関する重要課題と主要技術について、熱疲労特性、Be/CuCrZrおよびW/低放射化フェライト/マルテンサイト(RAFM)鋼の接合、材料特性、破壊機構の観点から議論する。ハイパーバトロン冷却流路および接合界面構造の設計改良が行われ、熱機械解析により、高熱流束(EHF)ITER FWの熱疲労寿命が1桁以上向上することが示された。小型モックアップおよび実寸大EHF FWフィンガーは、認定された技術を用いて順次製造された。小型モックアップのHHF試験により、Beタイルの寸法およびBe/CuCrZr界面の欠陥が疲労寿命に大きな影響を及ぼすことが示された。製造試験により、厚肉無酸素銅中間層が界面はく離問題に対する有効な解決策となり得ることが示された。ITER EHF FWセミプロトタイプが、追加の2対の実寸大フィンガーとともに製造され、4.7 MW m⁻²および5.9 MW m⁻²の過酷なHHF試験に成功した。CFETR FW用のW/RAFM鋼接合に関する各種製造技術が研究されており、トリチウム透過障壁としてのTiNコーティングを界面に適用する手法も含まれる。熱間静水圧加圧(HIP)によるW/RAFM鋼接合継手は、ろう付け継手よりも高い接合強度を示したが、中間層金属によって強度は大きく変動した。技術の最適化にはさらなる研究が必要である。

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