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Techniques of Measuring Neutron Spectra with Threshold Detectors—Tissue Dose Determination

机译：阈值检测器测量中子光谱的技术—组织剂量测定

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摘要

A method is described for measuring the spectrum of fast neutrons with a series of foil detectors. The detectors consist of Au and Au plus Cd for determining the thermal flux, Pu239 shielded with B10 for determining the total fast flux, Np237 for determining the total flux above 0.75 Mev, U238 for determining the total flux above 1.5 Mev, and S32 for determining the total flux above 2.5 Mev. From these data the spectrum of fast neutrons can be constructed reasonably well for spectra similar to that of fission. The amount of induced activity in the detecting elements is determined with scintillation counters, which are calibrated by irradiation of suitable foils with thermal neutrons. Fast neutron tissue dose can be calculated from the measured spectrum. Since the foil method of measuring spectra works well for high intensity bursts of neutrons, dosimetry may be accomplished under conditions where other methods, e.g., the ionization chamber and proportional counter, would lead to questionable data.
机译：描述了一种利用一系列箔片探测器测量快速中子光谱的方法。检测器由Au和Au加Cd确定热通量，Pu239用B10屏蔽确定总快速通量，Np237确定大于0.75 Mev的总通量，U238确定大于1.5 Mev的总通量和S32确定总通量高于2.5 Mev。根据这些数据，对于类似于裂变的光谱，可以很好地构造快中子的光谱。用闪烁计数器确定检测元件中的诱导活性的量，该闪烁计数器通过用热中子辐照合适的箔片来校准。快速中子组织剂量可以从测得的光谱中计算出来。由于箔的光谱测量方法对于中子的高强度爆发非常有效，因此剂量测定可以在其他方法（例如电离室和比例计数器）导致可疑数据的条件下完成。

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