秦山一期核电厂乏燃料元件扫描测量  

Gamma Scanning of Spent Fuel Elements from Qinshan NPP PhaseⅠ

作　　者：朱欣欣[1] ZHU Xinxin(China Institute of Atomic Energy,Beijing,102413 China)

机构地区：[1]中国原子能科学研究院,北京102413

出　　处：《科技资讯》2021年第9期49-52,共4页Science & Technology Information

摘　　要：乏燃料元件辐照后热室检查中,γ扫描测量作为无损检测手段之一,可以获得燃料辐照行为的相关信息,秦山一期核电厂乏燃料元件检验中,利用高纯锗γ谱仪完成了8根燃料元件棒γ扫描测量,元件燃耗分布在33 956~39 922 MWd/tU之间,获得了燃料元件轴向相对燃耗分布及燃料活性区堆积高度等数据。结果显示,采用0.5 mm精细扫描下,芯块与芯块间隙位置清晰可辩;燃料元件轴向燃耗总体呈现为两端低、中间平坦式分布,这与堆内中子注量分布相关,燃料元件格架处燃耗略低;燃料堆积高度较名义高度均有不同程度的增加,高度增长率在0.31%~0.90%之间;可用134Cs/137Cs原子比表征其相对燃耗分布。As one of non-destructive examination methods in hot cell,gamma scanning is used to provide data relevant to fuel behavior.8 fuel elements from Qinshan NPP phaseⅠwith burnup range of 33956~39922 MWd/tU were measured by gamma scanning,and the axial relative burnup distribution of fuel elements and the stack length of fuel active zone were obtained.The results show that the space position between the pellets can be identified by 0.5 mm fine scanning.The axial burnup of the f uel element is generally low at both ends and flat in the middle,which is related to the neutron flux distribution in the reactor,and the burnup at the fuel element grid is slightly lower.The fuel stack height increases in varying degrees compared with the nominal height,and the height growth rate is between 0.31%~0.90%,and the relative burnup distribution can be characterized by the atom ratio of 134Cs/137Cs.

关 键 词：乏燃料元件 γ扫描 燃耗分布 堆积高度 

分 类 号：TL-34[核科学技术]