Objective

In this article, IDAC-Dose2.1 and OLINDA computer codes are compared as they are the most widely used software tools for internal dosimetry assessment at the present time. OLINDA/EXM personal computer code was created as a replacement for the widely used MIRDOSE3.1 code. IDAC-Dose2.1 was developed based on the ICRP specific absorbed fractions and computational framework of internal dose assessment given for reference adults in ICRP Publication 133. IDAC uses cumulated activities per administered activity in hours and calculates the absorbed dose and the effective dose. The program calculates the dose in the Eckerman stylized family phantoms. It is useful in standardizing and automating internal dose calculations, assessing doses in clinical trials with radiopharmaceuticals, making theoretic calculations for existing pharmaceuticals, teaching, and other purposes.

Methods

To produce such a comparison, the results of this work were compared with available published data in the literature on radiopharmaceuticals. Radiopharmaceuticals with ⁸⁹Zr, ¹⁵³Sm, ¹⁷⁷Lu radionuclides are used as the basis for the comparison. ⁸⁹Zr, ¹⁵³Sm, ¹⁷⁷Lu radionuclides are regarded as the future of radiopharmaceutical treatment. For ⁸⁹Zr, two different labelled carriers, Zr-89_cMAb U36 and Zr-89 Panitumumab, were used on patients.

Results

The results show a clear difference in terms of absorbed dose of the Zr-89 radiopharmaceuticals for red bone marrow when calculated by IDAC-Dose2.1 (0.76 mGy/MBq), while the estimated absorbed dose in literature results is 0.07 mGy/MBq and 0.14 mGy/MBq when the calculation is done by OLINDA program. In the case of ¹⁷⁷Lu-EDTMP, the absorbed dose in red bone marrow is in reasonable agreement (0.63 mGy/MBq and 0.8 mGy/MBq for IDAC-Dose2.1 and OLINDA, respectively). A significant difference was found for the absorbed dose in the bone surface, which was almost twice as high for OLINDA (2.1 mGy/MBq for IDAC-Dose2.1 and 5.4 mGy/MBq for OLINDA). In some direct cases, the calculated absorbed dose in the urinary bladder wall with OLINDA is ten times higher compared to WinAct (which was utilized to calculate the total activity in the organs and tissues) and IDAC 2.1. These results are considered key to greater accuracy in internal dose calculation.

中文翻译：

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Zr-89、Sm-153 和 Lu-177 医用放射性同位素的吸收剂量评估：IDAC-Dose2.1 和 OLINDA 经验

客观的

在本文中，IDAC-Dose2.1 和 OLINDA 计算机代码进行了比较，因为它们是目前用于内部剂量测定评估的最广泛使用的软件工具。OLINDA/EXM 个人计算机代码是作为广泛使用的 MIRDOSE3.1 代码的替代品而创建的。IDAC-Dose2.1 是根据 ICRP 第 133 号出版物中为参考成人提供的 ICRP 特定吸收分数和内部剂量评估计算框架开发的。IDAC 使用以小时为单位的每次给药活动的累积活动，并计算吸收剂量和有效剂量。该程序计算 Eckerman 程式化的家庭体模中的剂量。它可用于标准化和自动化内部剂量计算，评估放射性药物临床试验中的剂量，对现有药物进行理论计算，教学，

方法

为了进行这种比较，将这项工作的结果与放射性药物文献中可用的已发表数据进行了比较。使用⁸⁹ Zr、¹⁵³ Sm、¹⁷⁷ Lu 放射性核素的放射性药物作为比较的基础。⁸⁹ Zr、¹⁵³ Sm、¹⁷⁷ Lu 放射性核素被认为是放射性药物治疗的未来。对于⁸⁹ Zr，两种不同的标记载体 Zr-89_cMAb U36 和 Zr-89 Panitumumab 用于患者。

结果

结果表明，当通过 IDAC-Dose2.1 (0.76 mGy/MBq) 计算时，Zr-89 放射性药物对红骨髓的吸收剂量存在明显差异，而文献结果中估计的吸收剂量为 0.07 mGy/MBq 和通过 OLINDA 程序计算时为 0.14 mGy/MBq。在^{177的情况下}Lu-EDTMP，红骨髓中的吸收剂量相当一致（IDAC-Dose2.1 和 OLINDA 分别为 0.63 mGy/MBq 和 0.8 mGy/MBq）。发现骨表面吸收剂量存在显着差异，几乎是 OLINDA 的两倍（IDAC-Dose2.1 为 2.1 mGy/MBq，OLINDA 为 5.4 mGy/MBq）。在一些直接案例中，使用 OLINDA 计算的膀胱壁吸收剂量比 WinAct（用于计算器官和组织中的总活性）和 IDAC 2.1 高十倍。这些结果被认为是提高内部剂量计算准确性的关键。