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

被引：12

作者：

Kost'al, Michal ^{[1
]}

Svadlenkova, Marie ^{[1
]}

Baron, Petr ^{[1
]}

Milcak, Jan ^{[1
]}

Marecek, Martin ^{[1
]}

Uhlir, Jan ^{[1
]}

机构：

[1] Res Ctr Rez Ltd, Husinec Rez 25068 130, Czech Republic

来源：

APPLIED RADIATION AND ISOTOPES | 2016年 / 111卷

关键词：

Cross section measurement; LR-0; Sample irradiation; Sodium induced activity; Na-22; NUCLEAR-DATA LIBRARY; GRAPHITE;

D O I：

10.1016/j.apradiso.2016.02.003

中图分类号：

O61 [无机化学];

学科分类号：

070301 ; 081704 ;

摘要：

The present paper aims to compare the calculated and experimental reaction rates of Na-23(n,2n)Na-22 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 mu b. 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 CAE 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. (C) 2016 Elsevier Ltd. All rights reserved.

引用

页码：1 / 7

页数：7

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