کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1730627 1521223 2006 10 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
CANDU reactor core simulations using fully coupled DRAGON and DONJON calculations
چکیده انگلیسی

The operating CANDU-6 reactors are refueled on-power to compensate for the reactivity loss due to fuel burnup. In order to predict the core behavior, fuel bundle burnups and local parameter information need to be tracked. The history-based approach has been developed to follow local parameter as well as history effect in CANDU reactors.The finite reactor diffusion code DONJON and the lattice code DRAGON have been coupled to perform reactor follow-up calculations using a history-based approach. A coupled methodology that manages the transfer of information between standard DONJON and DRAGON data structures has been developed. Push-through refueling can be taken into account directly in cell calculations. Using actual on-site information, an isotopic core content database has been generated with coupled DONJON and DRAGON calculations. Moreover calculations have been performed for different local parameters. Results are compared with those obtained using standard cross section generation approaches.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 33, Issue 8, May 2006, Pages 682–691
نویسندگان
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