کد مقاله | کد نشریه | سال انتشار | مقاله انگلیسی | نسخه تمام متن |
---|---|---|---|---|
1875752 | 1532086 | 2016 | 7 صفحه PDF | دانلود رایگان |
عنوان انگلیسی مقاله ISI
Measurement of 23Na(n,2n) cross section in well-defined reactor spectra
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موضوعات مرتبط
مهندسی و علوم پایه
فیزیک و نجوم
تشعشع
پیش نمایش صفحه اول مقاله
![عکس صفحه اول مقاله: Measurement of 23Na(n,2n) cross section in well-defined reactor spectra Measurement of 23Na(n,2n) cross section in well-defined reactor spectra](/preview/png/1875752.png)
چکیده انگلیسی
The present paper aims to compare the calculated and experimental reaction rates of 23Na(n,2n)22Na in a well-defined reactor spectra of a special core assembled in the LR-0 reactor. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination. The resulting value averaged in spectra is 0.91±0.02 µb. This cross-section is important as it is included in International Reactor Dosimetry and Fusion File and is also relevant to the correct estimation of long-term activity of Na coolant in Sodium Fast Reactors. The calculations were performed with the MCNP6 code using ENDF/B-VII.0, JEFF-3.1, JEFF-3.2, JENDL-3.3, JENDL-4, ROSFOND-2010 and CENDL-3.1 nuclear data libraries. Generally the best C/E agreement, within 2%, was found using the ROSFOND-2010 data set, whereas the worst, as high as 40%, was found using the ENDF/B-VII.0.
ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Applied Radiation and Isotopes - Volume 111, May 2016, Pages 1-7
Journal: Applied Radiation and Isotopes - Volume 111, May 2016, Pages 1-7
نویسندگان
Michal KoÅ¡Å¥ál, Marie Å vadlenková, Petr BaroÅ, Ján MilÄák, Martin MareÄek, Jan UhlÃÅ,