کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
4921215 | 1429340 | 2016 | 6 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Nuclear-thermal-coupled optimization code for the fusion breeding blanket conceptual design
ترجمه فارسی عنوان
کد بهینه سازی هسته ای-حرارتی برای طراحی مفهومی پدری درهم آمیخته
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کلمات کلیدی
پتو، جوش حرارتی هسته ای، بهینه سازی ساخت شعاعی،
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
چکیده انگلیسی
Fusion breeding blanket as one of the key in-vessel components performs the functions of breeding the tritium, removing the nuclear heat and heat flux from plasma chamber as well as acting as part of shielding system. The radial build design which determines the arrangement of function zones and material properties on the radial direction is the basis of the detailed design of fusion breeding blanket. For facilitating the radial build design, this study aims for developing a pre-design code to optimize the radial build of blanket with considering the performance of nuclear and thermal-hydraulic simultaneously. Two main features of this code are: (1) Coupling of the neutronics analysis with the thermal-hydraulic analysis to speed up the analysis progress; (2) preliminary optimization algorithm using one or multiple specified objectives subject to the design criteria in the form of constrains imposed on design variables and performance parameters within the possible engineering ranges. This pre-design code has been applied to the conceptual design of water-cooled ceramic breeding blanket in project of China fusion engineering testing reactor (CFETR).
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 113, December 2016, Pages 37-42
Journal: Fusion Engineering and Design - Volume 113, December 2016, Pages 37-42
نویسندگان
Jia Li, Kecheng Jiang, Xiaokang Zhang, Xingchen Nie, Qinjun Zhu, Songlin Liu,