کد مقاله کد نشریه سال انتشار مقاله انگلیسی ترجمه فارسی نسخه تمام متن
4921157 1429339 2017 5 صفحه PDF سفارش دهید دانلود کنید
عنوان انگلیسی مقاله ISI
Impact analysis of the time trend of TBR and irradiation damage assessment of HCSB blanket for CFETR
دانلود مقاله + سفارش ترجمه
دانلود مقاله ISI
فقط 1 هزار تومان
سفارش ترجمه تخصصی
با تضمین قیمت و کیفیت
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Impact analysis of the time trend of TBR and irradiation damage assessment of HCSB blanket for CFETR
چکیده انگلیسی

Chinese Fusion Engineering Testing Reactor (CFETR) is a test tokamak reactor to bridge the gap between ITER and future fusion power plants and to demonstrate generation of fusion power in China. In fusion power plants, tritium is generated from the reaction of neutron and Lithium. One of the missions of CFETR is the full cycle of tritium self-sufficiency. For the mission, a Helium Cooled Solid Breeder blanket (HCSB) was proposed for CFETR and its conceptual design has been carried out. In order to assess the capacity of the tritium breeding and irradiation damage of first wall of the HCSB blanket during the 8 years' engineering test stage, this paper presents the time trend of TBR analysis and irradiation damage assessment of HCSB blanket based on the three-dimensional (3D) neutronics model which is created by McCad. In the 3D neutronics model, the outboard blanket on equatorial plane is described based on the detailed 3D engineering model. The calculations were performed by MCNP and FISPACT with FENDL/2.1 data library. The impact analysis of the thickness of coolant plates (CP) and the structural material content in CPs to the TBR is assessment.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 114, January 2017, Pages 52-56
نویسندگان
, , , , , ,
دانلود مقاله + سفارش ترجمه
دانلود مقاله ISI
فقط 1 هزار تومان
سفارش ترجمه تخصصی
با تضمین قیمت و کیفیت