Progress and challenges of the ITER TBM Program from the IO perspective

被引：28

作者：

Giancarli, L. M. ^{[1
]}

Barabash, V. ^{[1
]}

Campbell, D. J. ^{[1
]}

Chiocchio, S. ^{[1
]}

Cordiera, J. J. ^{[1
]}

Dammann, A. ^{[1
]}

Dell'Orco, G. ^{[1
]}

Elbez-Uzan, J. ^{[1
]}

Fourneron, J. M. ^{[1
]}

Friconneau, J. P. ^{[1
]}

Gasparotto, M. ^{[2
]}

Iseli, M. ^{[1
]}

Jung, C. -Y. ^{[1
]}

Kim, B. -Y. ^{[1
]}

Lazarov, D. ^{[1
]}

Levesy, B. ^{[1
]}

Loughlin, M. ^{[1
]}

Merola, M. ^{[1
]}

Neviere, J. -C. ^{[3
]}

Pascal, R. ^{[1
]}

Ring, W. ^{[1
]}

Schneiderova, I. ^{[4
]}

Willms, S. ^{[1
]}

Siarras, A. ^{[1
]}

Shu, W. ^{[1
]}

Snipes, J. A. ^{[1
]}

van der Laan, J. G. ^{[1
]}

机构：

[1] ITER Org, Route Vinon Sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France

[2] Max Planck Inst Plasma Phys, Wendelsteinstr 1, D-17491 Greifswald, Germany

[3] Comex Nucl, F-13115 St Paul Les Durance, France

[4] Sogeti High Tech, F-13857 Aix En Provence, France

来源：

FUSION ENGINEERING AND DESIGN | 2016年 / 109卷

关键词：

Breeding blanket; TBM; ITER; DEMO; RESEARCH-AND-DEVELOPMENT; TEST BLANKET SYSTEMS; DESIGN; MODULE;

D O I：

10.1016/j.fusengdes.2015.11.046

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The paper describes the organization of the Test Blanket Module (TBM) program, its overall objective and schedule and the status of the technical activities within the ITER Organization-Central Team (IO-CT). The latter include the design integration of the Test Blanket Systems (TBSs) into the nuclear buildings, ensuring all interfaces with other ITER systems, the design of the common TBS components such as the TBM Frames, the Dummy TBMs, and the TBS maintenance tools and equipment in the TBM Port Cell as well as in the Hot Cell building, the design of the TBS connection pipes and the definition of the required maintenance operations and associated R&D. The paper also discusses the major challenges that the TBM Program will be facing in ITER such as the potential impact of the TBMs ferriticimartensitic structures on plasma operations, the approaches to tritium and contamination confinement, the required mitigation and recovery actions in case of accidents, and the assessment of the reliability aspects that could have an impact on ITER availability. (C) 2016 ITER Organization. Published by Elsevier B.V. All rights reserved.

引用

页码：1491 / 1497

页数：7

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