کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
366605 621453 2015 6 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Experimental investigation of sodium boiling heat exchange in fuel subassembly mockup for perspective fast reactor safety substantiation
ترجمه فارسی عنوان
بررسی تجربی سدیم جوش حرارتی در پیکرنما زیرمجمع سوخت برای اثبات دیدگاه ایمنی راکتور سریع
کلمات کلیدی
راکتور واقع؛ سدیم؛ پیکرنما زیرمجمع سوخت؛ مطالعات تجربی؛ غلیان؛ دو مرحله نقشه رژیم جریان؛ انتقال حرارت
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی انرژی هسته ای و مهندسی
چکیده انگلیسی

Numerical modeling of ULOF-type accident development in sodium-cooled fast reactor carried out using the COREMELT code indicate the development and spreading of sodium boiling in the core accompanied with fluctuations of reactor technological parameters lasting over a period of several tens of a seconds. Significant influence on the calculation results is produced by two-phase coolant flow regime so the code boiling models requiring experimental confirmation. Design solution that includes the “sodium cavity” above the reactor core was suggested in order to exclude reactor accidents resulting in the destruction of reactor core elements. As the result of experimental studies on heat exchange during sodium boiling in the fast reactor fuel subassembly mockup with “sodium cavity” conducted on the AR-1 test facility under natural circulation conditions it was demonstrated possibility of long-term fuel pins simulators stable cooling. Schematic map of two-phase liquid metal flow regimes in fuel pin bundles is presented, data on the heat transfer during liquid metal coolant boiling in the fuel assembly are presented and analyzed. The obtained experimental data are used for further elaboration of the calculation model of sodium boiling in the fuel assembly and for COREMELT computer code verification.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Nuclear Energy and Technology - Volume 1, Issue 2, October 2015, Pages 147–152
نویسندگان
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