Ninkovic M M, Raicevic J J, Adrovic F
Vinca Institute of Nuclear Sciences, P.O. Box 522, 11001 Belgrade, Serbia & Montenegro.
Radiat Prot Dosimetry. 2005;115(1-4):247-50. doi: 10.1093/rpd/nci131.
It is often required to estimate the dose rate at a distance from radionuclides that are sources of X rays and gamma rays. Such calculations may be required for planning radiation protection measures in the vicinity of radioactive sources or patients containing radionuclides, calibrations of radiation instruments or for estimating the absorbed dose rate to patients receiving brachytherapy. The factor relating activity and air kerma rate is called air kerma rate constant--gamma(delta). In this paper, the results of recalculation of this quantity for unfiltered point sources of radionuclides in practice used most often are given. The calculations included corrections for internal conversion of X rays and gamma rays and detailed accounting of the generation of the K and L series X rays from internal conversion and electron capture. Particular air kerma rate constants were calculated for each discrete line in the photon spectrum of radionuclide with a yield per decay event >0.01% and the energy >20 keV. Since the energy structure of the photon spectra and accessible discrete numerical values of the mass energy-transfer coefficient for air are not the same, the cubic spline interpolation was used to obtained the coefficient, where the photon spectrum data are available. In the calculation, the latest gamma ray spectral data for all radionuclides and latest data for the mass energy-transfer coefficient for air are used. Air kerma rate constants for the following 35 radionuclides are calculated: 11C, 13N, 15O, 18F, 24Na, 42K, 43K, 51Cr, 52Fe, 59Fe, 57Co, 58Co, 60Co, 67Ga, 68Ga, 75Se, 99Mo, 99mTc, 111In, 113mIn, 123I, 125I, 131I, 127Xe, 133Xe, 137Cs, 152Eu, 154Eu, 170Tm, 182Ta, 192Ir, 197Hg, 198Au, 201Tl and 241Am.
通常需要估算距作为X射线和γ射线源的放射性核素一定距离处的剂量率。在规划放射源或含有放射性核素的患者附近的辐射防护措施、辐射仪器的校准或估算接受近距离治疗的患者的吸收剂量率时,可能需要进行此类计算。将活度与空气比释动能率相关联的因子称为空气比释动能率常数——γ(δ)。本文给出了对实际中最常用的未过滤放射性核素点源的该量重新计算的结果。计算包括对X射线和γ射线内转换的校正以及对由内转换和电子俘获产生的K和L系X射线生成的详细核算。对于放射性核素光子谱中每次衰变事件产额>0.01%且能量>20 keV的每条离散谱线,计算了特定的空气比释动能率常数。由于光子谱的能量结构和空气的质能转移系数可获取的离散数值不同,在有光子谱数据的地方,使用三次样条插值来获得该系数。在计算中,使用了所有放射性核素的最新γ射线谱数据和空气的质能转移系数的最新数据。计算了以下35种放射性核素的空气比释动能率常数:碳-11、氮-13、氧-15、氟-18、钠-24、钾-42、钾-43、铬-51、铁-52、铁-59、钴-57、钴-58、钴-60、镓-67、镓-68、硒-75、钼-99、锝-99m、铟-111、铟-113m、碘-123、碘-125、碘-131、氙-127、氙-133、铯-137、铕-152、铕-154、铥-170、钽-182、铱-192、汞-197、金-198、铊-201和镅-241。