±¬×ߺÚÁÏ Engineering Basis Handbook
Under the editorial lead of , the ±¬×ߺÚÁÏ Engineering Basis Handbook delivers a stand-alone compilation of ±¬×ߺÚÁÏ design principles, the underlying technical design basis and its evolution from conception to construction, together with the technical, scientific, and regulatory rationale behind the major decisions. It facilitates the access and understanding of the project’s technological journey by consolidating the information from a multitude of sources. It aims at securing the lessons learned, the return of experience, and the knowledge transfer from the world's largest fusion project, drawing from the direct experience of knowledgeable experts who have worked on ±¬×ߺÚÁÏ, for the benefit of fusion professionals inside and outside of the ±¬×ߺÚÁÏ project and the next generation.
We welcome your feedback! Readers are invited to help shape the next versions of these chapters by submitting comments and suggestions to @email.
For ±¬×ߺÚÁÏ Regular Reports, return to this page.
This work is licensed under a .
You can find the biographies of the Handbook Editorial board here.
| Available | ITR-IEBH-108-1 | 8.1 The Licensing Process | |
| Expected 2026 | - | 8.2 Quality Assurance and Quality Control |
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| Expected 2026 | - | 8.3 Project Management |
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| Expected 2026 | - | 8.4 Construction achievements and milestones to date |
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| Expected 2026 | - | 8.5 Major Manufacturing and Construction Challenges |
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| Expected 2026 | - | 8.6 Oversight of the construction regulatory framework |
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| To be published soon | - | Ch. 10 – Final observations and lessons learned |
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| Expected 2026 | - | Ch. 3 - Introduction |
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| Expected 2026 | - | Ch. 4 - Physics basis & design implications |
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| Expected 2026 | - | 5.1 Tokamak basic machine design |
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| Expected 2026 | - | 5.2 Plant layout and site services |
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| Expected 2026 | - | 5.3 Nuclear buildings |
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| Expected 2026 | - | 5.4 Hot cell |
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| To be published soon | - | 5.5 Main loads: plant and systems level |
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| Expected 2026 | - | 5.6 The inner surface of the tokamak: plasma-facing materials |
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| Expected 2026 | - | 5.7 Finding and qualifying the right materials |
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| Expected 2026 | - | 5.8 Radiation shielding and nuclear design considerations |
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| Expected 2026 | - | 5.9 Nuclear safety |
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| Expected 2026 | - | 5.10 Fuel cycle subjects |
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| Expected 2026 | - | 5.11 Radioactive waste |
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| Expected 2026 | - | 5.12 The assembly sequence and tooling of ±¬×ߺÚÁÏ |
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| Expected 2026 | - | 5.13 RAMI and remote handling approach |
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| Expected 2026 | - | 5.14 Design methodologies and tools (codes & standards) |
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| Expected 2026 | - | 5.15 Managing of analyses |
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| Available | ITR-IEBH-205-16 | 5.16 Engineering instrumentation & simulators |
| To be published soon | - | 6.1 Magnet systems including vessel coils |
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| Expected 2026 | - | 6.2 Vacuum vessel |
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| Expected 2026 | - | 6.3 First wall & shielding blanket |
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| To be published soon | - | 6.4 Blanket cooling manifolds |
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| To be published soon | - | 6.5 Divertor |
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| Expected 2026 | - | 6.6 Auxiliary heating systems |
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| Expected 2026 | - | 6.7 Power supply systems |
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| Expected 2026 | - | 6.8 Cryogenic systems |
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| Expected 2026 | - | 6.9 Cryostat |
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| Expected 2026 | - | 6.10 Thermal shields |
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| Expected 2026 | - | 6.11 Cooling water systems |
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| Expected 2026 | - | 6.12 Fuelling systems |
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| Expected 2026 | - | 6.13 Vacuum and pumping systems |
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| Expected 2026 | - | 6.14 Fuel cycle and tritium plant |
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| Expected 2026 | - | 6.15 Remote handling systems and tools |
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| Expected 2026 | - | 6.16 Plasma diagnostics and port plug integration |
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| Expected 2026 | - | 6.17 ±¬×ߺÚÁÏ central control and plant system integration |
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| To be published soon | - | 6.18 The ±¬×ߺÚÁÏ Test Blanket Module Program |
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| Expected 2026 | - | Ch. 7 - Conclusions |
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