کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
4921407 1429343 2016 4 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Concept of DT fuel cycle for a fusion neutron source DEMO-FNS
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Concept of DT fuel cycle for a fusion neutron source DEMO-FNS
چکیده انگلیسی
Optimization of fuel cycle characteristics was aimed at reducing flows and inventory of hydrogen isotopes and tritium in fuel cycle subsystems. The calculations were carried out using computer code TC-FNS to estimate tritium distribution in fusion reactor systems and components of “tritium plant”. The code enables calculations of tritium flows and inventory in the tokamak systems. Calculations of tritium flows and accumulation have been carried out for two different cases of the fuel mixture for neutral beam injection (NBI) system. The amounts of tritium which is required for operation of all fuel cycle systems in two different cases of the fuel mixture for NBI are 0.45 “” kg (D:T = 1:0) and 0.9 kg (D:T = 1:1) respectively.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volumes 109–111, Part A, 1 November 2016, Pages 57-60
نویسندگان
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