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The new ITER baseline, research plan and open R&D issues

https://repo.qst.go.jp/records/2003244
https://repo.qst.go.jp/records/2003244
3b1c3238-9c08-483e-b341-1bb0ca6d3f05
アイテムタイプ 学術雑誌論文 / Journal Article(1)
公開日 2026-04-10
タイトル
タイトル The new ITER baseline, research plan and open R&D issues
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_6501
資源タイプ journal article
著者 Urano Hajime

× Urano Hajime

Urano Hajime

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Matsunaga Go

× Matsunaga Go

Matsunaga Go

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Hirose Takanori

× Hirose Takanori

Hirose Takanori

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Kunihiro Ogawa

× Kunihiro Ogawa

Kunihiro Ogawa

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Motojima Gen

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Motojima Gen

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抄録
内容記述タイプ Abstract
内容記述 A new baseline (NB) has been proposed by the ITER Project to ensure a robust achievement of the Projects’ goals, in view of past challenges including delays incurred due to the Covid-19 pandemic, technical challenges in completing first-of-a-kind components and in nuclear licensing. The NB includes modifications to the configuration of the ITER device and its ancillaries (e.g. change from beryllium to tungsten as first wall material, modification of the heating and current drive mix, etc.) as well as additional testing of components (e.g. toroidal field coils) or phased installation (start with inertially cooled first wall before later installation of the final actively water-cooled components) to minimise operational risks. In the NB, the ITER research plan (IRP) will be divided into three main phases: (a) start of research operation, with 40 MW of ECH and 10 MW of ICH, which will focus on the demonstration of 15 MA operation in L-mode, commissioning of all required systems, including disruption mitigation, and the demonstration of H-mode plasma operation in deuterium; (b) DT-1, with 60–67 MW of ECH, 33 MW of neutral beam injection (NBI) and 10–20 MW of ICH, which will demonstrate robust operation in high confinement H-mode plasmas in DT up to Q ⩾ 10 and for burn durations of 300–500 s within an accumulated neutron fluence of ∼1% of the ITER machine’s lifetime total, and; (c) DT-2, with up to 67 MW of ECH, up to 49.5 MW of NBI and up to 20 MW of ICH, with the ITER tokamak and ancillaries in their final configuration to demonstrate routine operation in DT plasmas at high Q and the Q ⩾ 5 long-pulse and steady-state scenarios to the final neutron fluence and to perform R&D on nuclear fusion reactor issues. The logic, physics basis, modelling and experimental evaluations carried out to support the NB and the associated IRP are described. These include the impact of the tungsten wall on plasma scenarios and associated risk mitigation measures, as well as the optimisation of the tokamak components and ancillaries to minimise Project risks. Open R&D issues related to these evaluations and mitigation measures are also described together with experimental, modelling and validation activities required to address them.
書誌情報 Plasma Physics and Controlled Fusion

巻 67, p. 065023, 発行日 2025-06
DOI
識別子タイプ DOI
関連識別子 10.1088/1361-6587/add9c9
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