Raaijmakers C P, Konijnenberg M W, Verhagen H W, Mijnheer B J
The Netherlands Cancer Institute, Antoni van Leeuwenhoek Huis, Amsterdam.
Med Phys. 1995 Mar;22(3):321-9. doi: 10.1118/1.597447.
The application of activation foils, thermoluminescent detectors, and ionization chambers has been investigated for the determination of the different dose components in phantoms irradiated with a mixed gamma-ray and epithermal neutron beam for boron neutron capture therapy. The thermal neutron fluence has been determined using a set of AuAl and MnNi activation foils. TLD-700 and a Mg(Ar) ionization chamber have been used for the determination of the gamma-ray dose. The dose from epithermal neutrons has been determined using a TE(TE) ionization chamber. The detector characteristics and the relative sensitivities of the various detectors to the different dose components in the phantom have been determined. The following accuracies (1 standard deviation) in the determination of the different components have been obtained: thermal neutron fluence rate: 5%; gamma-ray dose rate: 7%; epithermal neutron dose rate: 15%. These values make these detectors suitable for obtaining the complete set of clinical dosimetry data required for patient dose assessment.
为了确定在硼中子俘获疗法中用混合γ射线和超热中子束照射的体模中的不同剂量成分，对活化箔、热释光探测器和电离室的应用进行了研究。使用一组金铝和锰镍活化箔确定热中子注量。TLD - 700和一个镁（氩）电离室用于确定γ射线剂量。使用一个TE（TE）电离室确定超热中子剂量。已经确定了探测器特性以及各种探测器对体模中不同剂量成分的相对灵敏度。在确定不同成分时获得了以下精度（1个标准偏差）：热中子注量率：5%；γ射线剂量率：7%；超热中子剂量率：15%。这些值使得这些探测器适用于获取患者剂量评估所需的完整临床剂量学数据集。
