Measurement of the 23Na(n,2n) cross section in 235U and 252Cf fission neutron spectra

被引：1

作者：

Kostal, Michal ^{[1
]}

Schulc, Martin ^{[1
]}

Rypar, Vojtech ^{[1
]}

Losa, Evzen ^{[1
]}

Svadlenkova, Marie ^{[1
]}

Baron, Petr ^{[1
]}

Jansky, Bohumil ^{[1
]}

Novak, Evzen ^{[1
]}

Marecek, Martin ^{[1
]}

Uhlir, Jan ^{[1
]}

机构：

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

来源：

ND 2016: INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY | 2017年 / 146卷

关键词：

NUCLEAR-DATA LIBRARY; WELL-DEFINED CORES; GRAPHITE; SCIENCE;

D O I：

10.1051/epjconf/201714604045

中图分类号：

TL [原子能技术]; O571 [原子核物理学];

学科分类号：

0827 ; 082701 ;

摘要：

The presented paper aims to compare the calculated and experimental reaction rates of Na-23(n,2n)Na-22 in a well-defined reactor spectra and in the spontaneous fission spectrum of Cf-252. The experimentally determined reaction rate, derived using gamma spectroscopy of irradiated NaF sample, is used for average cross section determination. Estimation of 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, CENDL-3.1 and IRDFF nuclear data libraries. In the case of reactor spectrum, reasonable agreement was not achieved with any library. However, in the case of Cf-252 spectrum agreement was achieved with IRDFF, JEFF-3.1 and JENDL libraries.

引用

页数：4

共 50 条

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