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Radiation hardness testing of an organic liquid scintillator detector for use in high dose rate accident response scenarios

机译:用于高剂量率事故响应场景的有机液体闪烁体探测器的辐射硬度测试

摘要

Organic liquid scintillation detectors offer the advantage relative to many alternatives that they are sensitive to both fast neutrons and gamma rays, whilst radiation type can be discerned on the basis of pulse-shape discrimination. Mixed radiation fields of this type can arise in the context of reactor accidents via, for example, 137Cs (gamma) and 244Cm (neutrons). However, performance degradation of such scintillators, such as EJ-301, is a significant possibility that might limit the use of this technology in accident response applications. The premise behind the high dose rate testing of such a liquid scintillator described in this paper is for fuel debris characterisation at Fukushima Daiichi, which has expected dose rates of up to 1000 Gy/hr in close proximity to fuel debris. The tests carried out for this investigation involved using the 60Co gamma irradiation facility at the Dalton Cumbria Facility, Cumbria, United Kingdom to expose the detector to a similar dose rate to that which is estimated within the primary containment vessel for survivability tests. Radiation hardness tests have rarely been reported for such devices and it is expected that the performance will be dependent on the survival of the window of the photomultiplier tube rather than the liquid scintillant itself. A major advantage of the use of this detector is its physical size, due to the limitations on access into Fukushima reactors physical space is a premium. The research described in this paper presents the results of the dose rate exposure of the detector before signal was lost with the total dose observed providing information on any degradation affecting the performance of the device post-irradiation
机译:相对于许多替代方案,有机液体闪烁探测器提供的优势是它们对快中子和伽玛射线都敏感,而辐射类型可以根据脉冲形状辨别来辨别。在反应堆事故中,例如通过137Cs(伽马)和244Cm(中子)会产生这种混合辐射场。但是,这种闪烁器(例如EJ-301)的性能下降是一种很大的可能性,可能会限制该技术在事故响应应用中的使用。本文介绍的这种液体闪烁体的高剂量率测试的前提是福岛第一核电站的燃料碎片表征,其在接近燃料碎片的情况下预期的剂量率高达1000 Gy / hr。为进行此调查而进行的测试涉及使用位于英国坎布里亚郡道尔顿坎布里亚工厂的60Coγ射线辐照设备,使探测器暴露于与主要安全壳内估计的剂量率相似的剂量率,以进行生存性测试。很少有关于这种装置的辐射硬度测试的报道,并且预期性能将取决于光电倍增管窗口的寿命而不是液体闪烁体本身的寿命。使用该探测器的主要优势是其物理尺寸,由于进入福岛反应堆的访问受到限制,因此物理空间非常宝贵。本文所述的研究提出了信号丢失之前检测器的剂量率暴露结果,并观察到了总剂量,从而提供了有关影响设备照射后性能的任何劣化的信息。

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