Kyllönen J, Lindborg L
Swedish Radiation Protection Authority, SE-171 16 Stockholm, Sweden.
Radiat Prot Dosimetry. 2007;125(1-4):314-7. doi: 10.1093/rpd/ncm162. Epub 2007 Feb 18.
A graphite-walled proportional counter with low neutron sensitivity was used in combination with a tissue-equivalent proportional counter (TEPC) to separate the photon and neutron components in mixed radiation fields. Monte Carlo (MCNP4C) simulations of the photon and neutron responses of the two detectors were done to obtain correction factors for the sensitivity differences. In an alternative method the radiation components were determined using constant-yD-values for typical photon and neutron energy distributions. The results show no significant difference between the two methods and the measured neutron dose-equivalent agrees within +/-50% with Bonner sphere determined values. The experimental data were obtained in measurement campaigns organised within the EVIDOS-project.
使用具有低中子灵敏度的石墨壁正比计数器与组织等效正比计数器（TEPC）相结合，以分离混合辐射场中的光子和中子成分。对这两种探测器的光子和中子响应进行了蒙特卡罗（MCNP4C）模拟，以获得灵敏度差异的校正因子。在另一种方法中，利用典型光子和中子能量分布的恒定yD值来确定辐射成分。结果表明，两种方法之间没有显著差异，并且测量得到的中子剂量当量与邦纳球测定值在±50%范围内相符。实验数据是在EVIDOS项目组织的测量活动中获得的。
