阈探测器是研究中子能谱的一种有效工具,而中子能谱是解决某些辐射剂最学问题(其中包括确定紧急核事故中子剂量)所不可缺少的资料。用核乳胶和活化阈探测器测量事故中子剂量有一定的局限性。1967年,K.Becker 等人提出用“非照相方法”测量事故中子个人剂量的建议,并用天然铀和聚碳酸酯制作一种简单的裂变径迹个人中子剂量计~([1])。近年来,我们也研制了这种固体裂变径迹中子剂量计。在超临界紧急事故中,应用这种剂量计来测量中子剂量具有许多明显的优点:测量速度快,可测量的剂量范围大,环境适应性强和径迹计数能自动化等。其缺点是剂量计本身固有的γ放射性虽然已降低到很弱,但仍高出环境本底 Threshold detectors are an effective tool for studying neutron energy spectra, and neutron energy spectrum is indispensable for solving some of the most problematic radiological problems, including the determination of neutron doses for emergency nuclear accidents. There are some limitations to measuring accidental neutron doses with nuclear latex and activation threshold detectors. In 1967, K. Becker et al proposed the “non-photographic method” to measure the individual dose of incident neutrons and made a simple fission track personal neutron dosimeter with natural uranium and polycarbonate ~ ([1]) . In recent years, we have also developed this solid fission track neutron dosimeter. In supercritical emergencies, the use of such dosimeters to measure neutron dosages has many significant advantages: rapid measurement, measurable dose range, environmental adaptability and track count automation. The disadvantage is that although the inherent gamma radiation of the dosimeter has been reduced to a very low level, it is still above the background of the environment