压水堆乏燃料后处理厂的废包壳特征研究  

Study on the Characteristics of Cladding in the PWR Spent Fuel Reprocessing Plant

作　　者：马鸿宾 郭鑫宇 武毓勇 刘铁军 姜百华 Ma Hongbin;Guo Xinyu;Wu Yuyong;Liu Tiejun;Jiang Baihua(China Nuclear Power Engineering Co.,Ltd.,Beijing 100840,China)

机构地区：[1]中国核电工程有限公司,北京100840

出　　处：《广东化工》2022年第8期133-135,共3页Guangdong Chemical Industry

摘　　要：为了获取压水堆乏燃料后处理厂固体废物整备系统的工艺设计参数,开展乏燃料废包壳特性参数的研究。通过对压水堆燃料组件和包壳管段参数的调查,确定了包壳模拟件的长度、直径、壁厚、堆积体积、开口率等规格。并以模拟件为对象,开展了漂洗、沥干和称重试验,得到了模拟件的含水量数据,为工程设计提供了输入条件。同时,通过计算确定了废包壳的干燥目标值。In order to obtain the process parameters of radioactive solid waste conditioning system in PWR spent fuel reprocessing plant, the characteristic parameters of spent fuel cladding were studied. Through the investigation of the parameters of PWR fuel assembly and cladding pipe section, the length, diameter,wall thickness, accumulative volume, opening rate and other specifications of cladding simulation parts were determined. Taking the simulation parts as the object,rinsing, draining and weighing tests were carried out, and the water content data of the simulation parts were obtained, which provides input conditions for engineering design. At the same time, the drying target value of waste cladding was determined by calculation.

关 键 词：压水堆 乏燃料 后处理厂 包壳 干燥 

分 类 号：TL24[核科学技术—核燃料循环与材料] X771[环境科学与工程—环境工程]