Auman L E, Miller W H, Graham C C, Stretch C D, Welty T J, West L
Department of Nuclear Engineering, University of Missouri, Columbia 65211.
Health Phys. 1992 Feb;62(2):190-3. doi: 10.1097/00004032-199202000-00011.
To improve the methodology for assessing neutron dose at Union Electric's Callaway Nuclear Power Plant, an intercomparison of neutron detectors and dosimeters was performed. Seven different neutron detectors and dosimeters were tested in four different neutron fields utilizing facilities at the Missouri University Research Reactor and at the Southwest Radiation Calibration Center at the University of Arkansas. In general, all results agree within a factor of 2 in predicting the neutron dose equivalent. It was concluded that measurements of dose in containment should utilize the Tissue-Equivalent Proportional Counter (TEPC), the Bonner-sphere system, and the proton recoil spectrometer to accurately assess the neutron dose. These data can then be used to provide correction factors for more traditionally used dosimeters in containment, such as thermoluminescent dosimeters and survey meters.
为改进联合电力公司卡拉韦核电站中子剂量的评估方法，进行了中子探测器和剂量计的比对。利用密苏里大学研究堆及阿肯色大学西南辐射校准中心的设施，在四个不同中子场中对七种不同的中子探测器和剂量计进行了测试。总体而言，在预测中子剂量当量方面，所有结果的差异在2倍以内。得出的结论是，安全壳内剂量测量应使用组织等效正比计数器（TEPC）、邦纳球系统和质子反冲谱仪来准确评估中子剂量。然后，这些数据可用于为安全壳内更传统使用的剂量计（如热释光剂量计和巡测仪）提供校正因子。
