论文部分内容阅读
燃料组件中235U富集度测量方法普遍采用中子活化法和质谱法。由于中子活化法测量设备庞大和质谱法破坏样品的缺点,无法作为快速、便携测量燃料组件235U富集度的有效手段,不适于作为燃料组件管理和运输过程中铀同位素富集度的测量验证手段。为此,研发一种以小型中子发生器(14 MeV中子源)为激发源的快速、便携测量燃料组件235U富集度方法。依据特定裂变核素平均产额之比与235U富集度的近似线性相关性,成功地测量了235U富集度范围为10%~90%铀样品。
235U enrichment measurement methods commonly used in fuel assemblies neutron activation and mass spectrometry. Due to the large measuring equipment of neutron activation and the disadvantage of mass spectrometry destroying the sample, it can not be used as an efficient and rapid measure for the enrichment of 235U fuel assemblies, which is not suitable for the measurement and verification of uranium isotope enrichment during the management and transportation of fuel assemblies means. To this end, a method of enrichment for a fast, portable measurement fuel assembly 235U powered by a small neutron generator (14 MeV neutron source) has been developed. Uranium samples with a 235U enrichment range of 10% to 90% were successfully measured based on the approximate linearity of the ratio of average fission nuclide yields to 235U enrichment.