دانلود مقاله ISI انگلیسی شماره 10559
ترجمه فارسی عنوان مقاله

بررسی اجمالی فعالیت های تحقیق و توسعه TBM در هند

عنوان انگلیسی
Overview of TBM R&D activities in India
کد مقاله سال انتشار تعداد صفحات مقاله انگلیسی
10559 2012 5 صفحه PDF
منبع

Publisher : Elsevier - Science Direct (الزویر - ساینس دایرکت)

Journal : Fusion Engineering and Design, Volume 87, Issues 5–6, August 2012, Pages 461–465

ترجمه کلمات کلیدی
روکش تولید شونده -
کلمات کلیدی انگلیسی
Breeding Blanket, TBM, LLCB, ITER, DEMO,
پیش نمایش مقاله
پیش نمایش مقاله  بررسی اجمالی فعالیت های تحقیق و توسعه  TBM در هند

چکیده انگلیسی

In India, development of Lead–Lithium Ceramic Breeder (LLCB) blanket is being performed as the primary candidate of Test Blanket Module (TBM) towards DEMO reactor. The LLCB TBM will be tested from the first phase of ITER operation (H-H phase) in one-half of an ITER port no. 2. The Indian TBM R&D program is focused on the development of blanket materials and critical technologies: structural material (IN-RAFMS), breeding materials (Pb–Li, Li2TiO3), development of technologies for Lead–Lithium cooling system (LLCS), helium cooling system (HCS), tritium extraction system (TES) and TBM related fabrication technologies. This paper will provide an overview of LLCB TBM R&D activities under progress in India

مقدمه انگلیسی

India is developing LLCB blanket as a primary option for its DEMO reactor [1]. In the Indian fusion roadmap towards DEMO reactor, ITER-Test Blanket Module program [2] is one of the major milestones through which the performance of the LLCB blanket, candidate blanket materials and auxiliary system technologies can be tested and qualified in real fusion environment. The LLCB TBM will be tested from the first phase of ITER operation (H-H phase) in one-half of an ITER port no. 2. The Indian TBM R&D program is focused on the development of blanket materials and critical technologies: structural material (IN-RAFMS), breeding materials (Pb–Li, Li2TiO3), development of technologies for Lead–Lithium Cooling System (LLCS), helium cooling system (HCS), tritium extraction system (TES) and TBM related fabrication technologies. Lead–Lithium technologies development activities are focused on Lead–Lithium loop developments for MHD experiments, corrosion experiments and operational experience with critical loop components. IN-RAFM steel is a structural material under development for fusion reactor applications. Several fabrication procedures for manufacturing TBM sub-components and their assembly sequence need to be investigated in the developmental program. For the fabrication of TBM sub-components mock-up, IN-RAFMS is being considered to investigate its fabrication feasibilities by Hot Isostatic Press (HIP), Electron Beam Welding (EBW), laser and narrow gap TIG welding processes. The R&D activities focusing on ITER-TBM system development are in full swing in Institute for Plasma Research (IPR) Gandhinagar, in collaboration with Bhabha Atomic Research Centre (BARC), Mumbai, Indira Gandhi Centre for Atomic Research (IGCAR), Kalpakkam, and other research institutions and universities within India. This paper provides an overview of the LLCB TBM activities and related R&D progress in India.