کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
1741377 1017387 2009 4 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
A thermal-hydraulic code (THYD) for the miniature neutron source reactor thermal-hydraulic transients
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
A thermal-hydraulic code (THYD) for the miniature neutron source reactor thermal-hydraulic transients
چکیده انگلیسی

The transient thermal-hydraulic problem of MNSR is represented by ten differential equations solved numerically using Runge–Kutta method.Computational results are then compared with experimental measurements. Fuel grids and cooling coil models are incorporated in the model too. Radiating energy from the clad is taken into account in the energy balance in the reactor. The pool is divided into three sections in the model. The effect of the cooling coil of the pool upper section on reactor thermal-hydraulic parameters is discussed. The only input parameter of the reactor is the power temporal distribution. Good agreement between calculated and measured data was obtained.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Progress in Nuclear Energy - Volume 51, Issue 3, April 2009, Pages 470–473
نویسندگان
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