利用裂变径迹探测器刻度缓发中子监测仪的探测效率

CALIBRATION OF DETECTION EFFICIENCY OF DELAYED NEUTRON DETECTOR BY FISSION TRACK DETECTORS

  • 摘要: <正> 一、前言 本文所指的缓发中子监测仪是探测燃料元件破损的仪器,探头为BF_3计数管,当燃料元件破损后,裂变产物所释放的缓发中子经慢化后成热中子,进入BF_3计数管产生~(10)B(n,α)~7Li反应。记录其脉冲,监督燃料元件的破损。

     

    Abstract: The paper presents a new method to calibrate detection efficiency of delayedneutron detector for monitoring breakage of fuel elements in nuclear reactor. The device consists of three parts: loop of test installed on the nuclearreactor, simulating failed fuel element and fission track detector. Under same condition, at first the counts of delayed neutron are measuredusing delayed neutron detector, then the counts of delayed neutron are measuredusing fission track detector. Results show that the flux rate of delayed neutron equals 4.8 n/cm~2·s, andthe detection efficiency equals 8.1%.

     

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