کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
8067149 1521082 2018 8 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
Validation of STRCS code for calculation of fission-product transport in reactor coolant system during severe accidents
چکیده انگلیسی
Transport and deposition of fission products within the primary coolant circuit during severe accident condition have significant effect on the amount of released radionuclides in the containment. In this study, a new code, STRCS, compatible with RELAP5/SCDAP code, has been developed that calculates the fission products' transport through the piping system. The homogeneous and heterogeneous nucleation, aerosol agglomeration, aerosol and vapor deposition and aerosol resuspension are considered in this code. The developed code was validated through international standard problems STROM SR11 and PHEBUS FPT-1 experiments. The STRCS predictions are in good agreement with the ISPs published results, although the obtained results deviate from the PHEBUS FPT-1 experimental data.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 114, April 2018, Pages 206-213
نویسندگان
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