کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
298257 511782 2009 9 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor
چکیده انگلیسی

The SIMMER-III code is a two-dimensional, multi-velocity-field, multi-phase, multi-component, Eulerian, fluid-dynamics code coupled with a fuel-pin model and a space- and energy-dependent neutron transport kinetics model. Since the three-dimensional representation of the core enables realistic distribution of the materials constituting the core, including control rods, SIMMER-IV has been developed as a direct extension of SIMMER-III to three dimensions with retaining exactly the same physical models as SIMMER-III. Recently, the parallelization of SIMMER-IV has been achieved, allowing application to reactor calculations within available computational resources. A three-dimensional simulation using SIMMER-IV has drawn more realistic accident scenario including a late stage during the transition phase. Additional static neutronic calculations identified major factors significantly influencing the reactivity change shown in the SIMMER-IV simulation.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Engineering and Design - Volume 239, Issue 9, September 2009, Pages 1673–1681
نویسندگان
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