کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
272198 505016 2012 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Overview of the ITER TBM Program
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Overview of the ITER TBM Program
چکیده انگلیسی

The objective of the ITER TBM Program is to provide the first experimental data on the performance of the breeding blankets in the integrated fusion nuclear environment. Such information is essential to design and predict the performance of DEMO and future fusion reactors. It foresees to test six mock-ups of breeding blankets, called Test Blanket Module (TBM), in three dedicated ITER equatorial ports from the beginning of the ITER operation. The TBM and its associated ancillary systems, including cooling system and tritium extraction system, forms the Test Blanket System (TBS) that will be fully integrated in the ITER machine and buildings. This paper describes the main features of the six TBSs that are presently planned for installation and operation in ITER, the main interfaces with other ITER systems and the main aspects of the TBM Program management.


► The ITER TBM Program is the answer to the ITER mission of “testing tritium breeding module concepts that would lead in a future reactor to tritium self-sufficiency, the extraction of high grade heat and electricity production”.
► This paper describes the main features of the six TBSs that are presently planned for installation and operation in ITER, the main interfaces with other ITER systems and the main aspects of the TBM Program management.
► The pre-conceptual design of the six Test Blanket Systems to be tested in ITER is available and their integration in the ITER facility is currently on-going.
► For each Test Blanket System, the most important next step is the signature of the corresponding TBM Arrangement that will allow performing the TBS conceptual design review shortly after.
► Delivery and installation of the six Test Blanket Systems is planned for the initial ITER H-phase.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 87, Issues 5–6, August 2012, Pages 395–402
نویسندگان
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