Measurement of 23Na(n, 2n) cross section in well-defined reactor spectra. (May 2016)

• Record Type: Journal Article
• Authors: Košťál, Michal; Švadlenková, Marie; Baroň, Petr; Milčák, Ján; Mareček, Martin; Uhlíř, Jan
• Is Part Of: Applied radiation and isotopes. Volume 111(2016:May)
• Page Start: 1
• Page End: 7
• Publication Date: 2016-05
• Subjects: Cross section measurement -- LR-0 -- Sample irradiation -- Sodium induced activity -- 22Na; Radiology -- Periodicals; Radiation -- Industrial applications -- Periodicals; Nuclear chemistry -- Periodicals; Internet resource; Periodical; 660.298
• DOI: 10.1016/j.apradiso.2016.02.003
• Languages: English
• ISSNs: 0969-8043

Abstract

Abstract: The present paper aims to compare the calculated and experimental reaction rates of 23 Na(n, 2n) 22 Na 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. Highlights: Determination of 22 Na reaction rate in irradiated NaF sample. Determination of spectral average cross section of 23 Na(n, 2 n) reaction. Calculation of reaction rate 23 Na(n, 2 n) reaction. Discrepancies between calculation and experiment.