Kim Chankyu, Yoo Hyunjun, Kim Yewon, Moon Myungkook, Kim Jong Yul, Kang Dong Uk, Lee Daehee, Kim Myung Soo, Cho Minsik, Lee Eunjoong, Cho Gyuseong
Department of Nuclear and Quantum Engineering, KAIST, 305-701 Daejeon, Republic of Korea.
Neutron Instrumentation Division, KAERI, 305-353 Daejeon, Republic of Korea.
Radiat Prot Dosimetry. 2016 Sep;170(1-4):377-81. doi: 10.1093/rpd/ncw086. Epub 2016 Apr 28.
Plastic scintillation detectors have practical advantages in the field of dosimetry. Energy calibration of measured gamma spectra is important for dose computation, but it is not simple in the plastic scintillators because of their different characteristics and a finite resolution. In this study, the gamma spectra in a polystyrene scintillator were calculated for the energy calibration and dose computation. Based on the relationship between the energy resolution and estimated energy broadening effect in the calculated spectra, the gamma spectra were simply calculated without many iterations. The calculated spectra were in agreement with the calculation by an existing method and measurements.
塑料闪烁探测器在剂量测定领域具有实际优势。测量的伽马能谱的能量校准对于剂量计算很重要,但在塑料闪烁体中进行能量校准并不简单,因为它们具有不同的特性且分辨率有限。在本研究中,为了进行能量校准和剂量计算,计算了聚苯乙烯闪烁体中的伽马能谱。基于计算能谱中能量分辨率与估计的能量展宽效应之间的关系,无需多次迭代即可简单地计算伽马能谱。计算得到的能谱与现有方法的计算结果和测量结果一致。