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γ能谱法在快堆新燃料235U富集度核实测量中的应用

Application of γ-NDA Method in Fast Neutron Reactor Fresh Fuel’s Uranium Enrichment Measurement

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【作者】 何丽霞蒙延泰邵婕文郜强

【Author】 HE Li-xia,MENG Yan-tai,SHAO Jie-wen,GAO Qiang (China Institute of Atomic Energy,Beijing 102413,China)

【机构】 中国原子能科学研究院核保障技术重点实验室中国原子能科学研究院核保障技术重点实验室 北京102413北京102413

【摘要】 采用无损分析方法中最常用的γ能谱法及专用分析软件PC/FRAM核实了中国原子能科学研究院实验快堆新燃料中235U富集度的标称值。从实验角度出发,首先对系统进行了标样测量验证,在新燃料库房任取8根新燃料单棒,分段取点测量,计算得8根单棒的235U富集度与标称值偏差绝大部分在3%以内。以上结果提示,γ能谱法用于快堆新燃料235U富集度测量的方法可取,在核燃料设施加工与核电站进行新燃料组件交接方面可以推广应用。

【Abstract】 γ-spectrometry in non-destructive assay field and special PC/FRAM code were used to verify fresh fuel rods’ 235U enrichment declared value,which will be used in Chinese experiment fast neutron reactor.The experiment required system should be validated by uranium standards.Different plots on 8 fresh fuel rods were measured.The results show that most of the 235U enrichment deviation between measured value and declared are less than 3%.So,it can be concluded that γ-spectrometry is efficient in verifying 235U enrichment in fuel rods which will be used in reactors;and this method should be widely used in fuel transfers between nuclear power plant and fresh fuel manufactories.

  • 【分类号】TL81
  • 【被引频次】8
  • 【下载频次】150
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