کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
8066948 1521077 2018 13 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
ASTEC-Na code: Thermal-hydraulic model validation and benchmarking with other codes
چکیده انگلیسی
This paper describes the work performed within the WP2.1 of the JASMIN project to validate the thermal-hydraulic models of ASTEC-Na code. The experiments used for validation purposes have been: BI1, E8 and EFM1, carried out in the CABRI reactor; BE + 3, APL1 and APL3, carried out in the SCARABEE reactor and N02, conducted in the KNS facility. ASTEC-Na has been also successfully applied (pretest calculations) to assess the performances of the KASOLA sodium loop and to verify its response under different operating conditions. Finally, a PHENIX natural circulation test has also been performed with ASTEC-Na. Besides, these experimental tests have been used as a code benchmarking exercise where thermal-hydraulic codes (CATHARE, RELAP5-Na and RELAP5-3D) and severe accident codes (SIMMER-III and SAS-SFR) have been compared with ASTEC-Na.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 119, September 2018, Pages 427-439
نویسندگان
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