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

A Loarte, R A Pitts, T Wauters, I Nunes, P de Vries, S H Kim, F Köchl, A Polevoi, M Lehnen, J Artola2025年6月Plasma Physics and Controlled FusionIF 2.2出版社

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.

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AIによる論文要約

ITER の新しい基準、研究計画、および未解決の R&D 課題
JAこの論文は、ITER プロジェクトに携わる研究者や技術者、核融合分野に興味のある学生に向けて書かれています。ITER の最新の動向と課題を知りたい人にお勧めです。#ITER #核融合 #プラズマ #実験計画 #技術課題
LLM向け: {'Title': 'ITER の新しい基準、研究計画、および未解決の R&D 課題', 'Author(s)': 'ITER プロジェクトチーム', 'Res…

この論文は、ITER プロジェクトの新しい基準と研究計画について説明しています。新しい基準には、装置の設計変更や追加テストなどが含まれており、段階的な運転計画によってリスクを最小限に抑えることを目指しています。この論文は、ITER プロジェクトの現状と今後の課題を理解するのに役立ちます。

The new ITER baseline, research plan and open R&D issues
ENThis paper is essential reading for fusion researchers, engineers, and policymakers involved in the ITER project or interested in the development of fusion energy.#ITER #FusionEnergy #PlasmaPhysics #ReactorDesign
LLM向け: {'Title': 'The new ITER baseline, research plan and open R&D issues', 'Author(s)…

This paper outlines ITER's new baseline plan, which includes changes to the device configuration and a phased research approach to mitigate risks and ensure robust achievement of project goals. The plan focuses on demonstrating high-performance plasma operation, DT fusion, and addressing key fusion reactor issues.

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