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研究了无源符合中子法测量不同含Ｐｕ材料的方法和技术。采用高计数率符合中子计数器测量材料中的２４０Ｐｕ等核素自发裂变产生的裂变中子，通过计算等效２４０Ｐｕ量来确定材料中的总含Ｐｕ量。在现场实测了含Ｐｕ炉渣等十多类各种物理形态的材料。讨论了测量数据的修正及误差来源。测量误差一般在８％—１１％，大部分结果与天平称重估算法在１０％内符合。
The methods and techniques for measuring different materials containing Pu with passive neutron method are studied. The neutron counter is used to measure the total amount of Pu in the material by calculating the equivalent amount of 240Pu using a neutron counter that measures fission neutrons generated by spontaneous fission of nuclides such as 240Pu. Measured in the field containing more than 10 kinds of Pu slag and other physical forms of materials. The measurement data correction and error sources are discussed. Measurement error is generally 8% -11%, most of the results with the balance weighing method within 10% of the agreement.