کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
5474990 | 1521086 | 2017 | 13 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Cross section adjustment for fast reactor design: ATCROSS code and its application
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کلمات کلیدی
موضوعات مرتبط
مهندسی و علوم پایه
مهندسی انرژی
مهندسی انرژی و فناوری های برق
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Cross section adjustment for fast reactor design: ATCROSS code and its application Cross section adjustment for fast reactor design: ATCROSS code and its application](/preview/png/5474990.png)
چکیده انگلیسی
The results of uncertainty analyses performed for the Korean PGSFR reactor are in a good accordance with those already published for the similar designs; thus the calculated target cross section uncertainties could be seen as realistic. The uncertainty of keff induced by cross section data reaches approximately 2%. The uncertainty induced by cross section data for fuel temperature and loss of coolant reactivity feedback effects reach 6% and 13%, respectively. These uncertainties may be reduced by applying the conventional cross section adjustment method in conjunction with sufficient amount of high-quality experimental data. The first application of conventional cross section method to PGSFR core design is introduced in the paper.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Annals of Nuclear Energy - Volume 110, December 2017, Pages 928-940
Journal: Annals of Nuclear Energy - Volume 110, December 2017, Pages 928-940
نویسندگان
Branislav Vrban, Jakub Lüley, Å tefan Äerba, Filip Osuský, Sang Ji Kim,