کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
5474912 1521086 2017 12 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
CFD/Monte-Carlo neutron transport coupling scheme, application to TRIGA reactor
چکیده انگلیسی
A new computational model of the JSI TRIGA Mark II, coupling Monte Carlo neutron transport code TRIPOLI and fluid dynamics code CFX was built and verified with a set of new experimental data. A set of subroutines was developed to allow the communication between the Monte-Carlo transport code and CFD code. First, test of the coupling scheme is presented: for a given thermal power of the reactor, the coupled model numerically reproduced fuel temperature monitored during reactor operation and axial water temperature profile measured in the coolant channels. Then axial temperature profiles in the coolant channels were measured with a newly developed sensor during steady-state operation. Predictions of the coupled model are in expected agreement with experimental data recorded during reactor operations. Influence of the coupling has been investigated.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 110, December 2017, Pages 36-47
نویسندگان
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