期刊文献+

能谱变化对^(239)Pu裂变室测量快中子注量的影响 被引量:1

Fast neutron flux measurement uncertainty due to the variation of neutron spectra distribution
下载PDF
导出
摘要 热中子和共振区的中子在快中子临界装置中所占的份额很小,但是由于其相对大的截面,在慢化物存在的情况下,热中子和共振中子份额的微小变化,对239Pu裂变室测量中子注量的结果影响很大。通过测量239Pu裂变电离室在包镉和包硼、周围有无慢化物等情况下的反应率,Au、In活化片的镉比,S活化片在能谱变化下与239Pu的反应率比等,分析了快中子临界装置中热中子和共振区中子的分布,讨论了中子能谱变化对239Pu裂变室测量快中子注量的影响及解决办法。 As the fission cross-section of ^(239)Pu is flat while the neutron energy is larger than 10keV, the ^(239)Pu fission chamber is often used to measure the absolute fast neutron flux in the fast reactors or assemblies. Due to a little fraction in the fast neutron assemblies, having a relative large cross-section, the thermal neutron and resonance region neutron make the measured reaction rate varied abruptly when some moderators are near the detector. The ^(239)Pu fission rate with and without ^(10)B capsule, the Cadmium rate of ^(197)Au and ^(115)In, and the ^(32)S reaction rate are measured to analyze the neutron spectra variation out of the CFBR-II reactor. The fast neutron flux measurement methods are concluded in the end.
出处 《核电子学与探测技术》 CAS CSCD 北大核心 2004年第4期391-394,共4页 Nuclear Electronics & Detection Technology
关键词 中子能谱 中子注量 裂变室 活化片 反应率 neutron flux neutron spectra fission chamber foil detectors
  • 相关文献

参考文献1

二级参考文献1

  • 1ASTM.E265-88, Standard method for determining fast -neutron flux density by radio activation of sulfur[]..1998

共引文献5

同被引文献8

引证文献1

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部