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回旋加速器生产的 (99m)Tc 放射性核素杂质的评估。

Assessment of radionuclidic impurities in cyclotron produced (99m)Tc.

机构信息

Nuclear Physics Institute, Academy of Sciences of the Czech Republic, vvi, Husinec-Řež, Czech Republic.

出版信息

Nucl Med Biol. 2012 Nov;39(8):1286-91. doi: 10.1016/j.nucmedbio.2012.06.009. Epub 2012 Jul 15.

Abstract

INTRODUCTION

The commercial viability of cyclotron-produced (99m)Tc as an alternative to generator-produced (99m)Tc depends on several factors. These include: production yield, ease of target processing and recycling of (100)Mo, radiochemical purity, specific activity as well as the presence of other radionuclides, particularly various Tc radioisotopes that cannot be separated chemically and will remain in the final clinical preparation. These Tc radionuclidic impurities are derived from nuclear interactions of the accelerated protons with other stable Mo isotopes present in the enriched (100)Mo target. The aim of our study was to determine experimentally the yields of Tc radioisotopes produced from these stable Mo isotopes as a function of incident beam energy in order to predict radionuclidic purity of (99m)Tc produced in highly enriched (100)Mo targets of known isotopic composition.

METHODS

Enriched molybdenum targets of (95)Mo, (96)Mo, (97)Mo, (98)Mo and (100)Mo were prepared by pressing powdered metal into an aluminum target support. The thick targets were bombarded with 10 to 24MeV protons using the external beam line of the U-120M cyclotron of the Nuclear Physics Institute, Řež. The thick target yields of (94)Tc, (94m)Tc, (95)Tc, (95m)Tc, (96m+g)Tc and (97m)Tc were derived from their activities measured by γ spectrometry using a high purity Ge detector. These data were then used to assess the effect of isotopic composition of highly enriched (100)Mo targets on the radionuclidic purity of (99m)Tc as a function of proton beam energy. Estimates were validated by comparison to measured activities of Tc radioisotopes in proton irradiated, highly enriched (100)Mo targets of known isotopic composition.

RESULTS

The measured thick target yields of (94)Tc, (94m)Tc, (95)Tc, (95m)Tc, (96m+g)Tc and (97m)Tc correspond well with recently published values calculated via the EMPIRE-3 code. However, the measured yields are more favourable with regard to achievable radionuclidic purity of (99m)Tc. Reliability of the measured thick target yields was demonstrated by comparison of the estimated and measured activities of (94)Tc, (95)Tc, (95m)Tc, and (96m+g)Tc in highly enriched (100)Mo (99%) targets that showed good agreement, with maximum differences within estimated uncertainties. Radioisotopes (94m)Tc and (97m)Tc were not detected in the irradiated (100)Mo targets due to their low activities and measurement conditions; on the other hand we detected small amounts of the short-lived positron emitter (93)Tc (T(½)=2.75h). In addition to (99m)Tc and trace amounts of the various Tc isotopes, significant activities of (96)Nb, (97)Nb and (99)Mo were detected in the irradiated (100)Mo targets.

CONCLUSIONS

Radioisotope formation during the proton irradiation of Mo targets prepared from different, enriched stable Mo isotopes provides a useful data base to predict the presence of Tc radionuclidic impurities in (99m)Tc derived from proton irradiated (100)Mo targets of known isotopic composition. The longer-lived Tc isotopes including (94)Tc (T(½)=4.883h), (95)Tc (T(½)=20.0h), (95m)Tc (T(½)=61 d), (96m+g)Tc (T(½)=4.24 d) and (97m)Tc (T(½)=90 d) are of particular concern since they may affect the dosimetry in clinical applications. Our data demonstrate that cyclotron production of (99m)Tc, using highly enriched (100)Mo targets and 19-24MeV incident proton energy, will result in a product of acceptable radionuclidic purity for applications in nuclear medicine.

摘要

简介

回旋加速器生产的 (99m)Tc 作为发生器生产的 (99m)Tc 的替代物的商业可行性取决于几个因素。这些因素包括:产率、目标处理的难易程度和 (100)Mo 的回收、放射性纯度、比活度以及其他放射性核素的存在,特别是不能通过化学方法分离并将留在最终临床制剂中的各种 Tc 放射性同位素。这些 Tc 放射性核素杂质来源于加速质子与富集 (100)Mo 靶中存在的其他稳定 Mo 同位素的核相互作用。我们研究的目的是实验确定从这些稳定 Mo 同位素中产生的 Tc 放射性同位素的产率作为入射束能量的函数,以便预测在已知同位素组成的高浓缩 (100)Mo 靶中产生的 (99m)Tc 的放射性核素纯度。

方法

使用粉末金属压入铝靶支撑物的方法制备了 (95)Mo、(96)Mo、(97)Mo、(98)Mo 和 (100)Mo 的浓缩钼靶。使用核物理研究所 U-120M 回旋加速器的外部束线用 10 到 24MeV 质子轰击厚靶。通过使用高纯 Ge 探测器的 γ 谱法测量它们的活度,从其活度中推导出 (94)Tc、(94m)Tc、(95)Tc、(95m)Tc、(96m+g)Tc 和 (97m)Tc 的产率。然后,这些数据被用来评估高浓缩 (100)Mo 靶的同位素组成对作为质子束能量函数的 (99m)Tc 的放射性核素纯度的影响。通过将测量到的在已知同位素组成的高浓缩 (100)Mo 靶中辐照的 Tc 放射性同位素的活度与估算值进行比较来验证估计值。

结果

测量的 (94)Tc、(94m)Tc、(95)Tc、(95m)Tc、(96m+g)Tc 和 (97m)Tc 的厚靶产率与最近通过 EMPIRE-3 代码计算得出的值非常吻合。然而,在 (99m)Tc 的放射性核素纯度方面,测量的产率更有利。通过比较在高浓缩 (100)Mo(99%)靶中辐照的 (94)Tc、(95)Tc、(95m)Tc 和 (96m+g)Tc 的估算和测量活度,证明了测量厚靶产率的可靠性,这表明两者吻合良好,最大差异在估算不确定度范围内。由于其低活度和测量条件,在辐照的 (100)Mo 靶中未检测到放射性同位素 (94m)Tc 和 (97m)Tc;另一方面,我们检测到了少量短寿命正电子发射体 (93)Tc(半衰期 T(½)=2.75h)。除了 (99m)Tc 和痕量的各种 Tc 同位素外,在辐照的 (100)Mo 靶中还检测到了显著量的 (96)Nb、(97)Nb 和 (99)Mo。

结论

由不同浓缩稳定 Mo 同位素制备的 Mo 靶在质子辐照过程中形成的放射性同位素为预测从已知同位素组成的质子辐照 (100)Mo 靶中产生的 (99m)Tc 中 Tc 放射性核素杂质的存在提供了有用的基础数据。包括 (94)Tc(半衰期 T(½)=4.883h)、(95)Tc(半衰期 T(½)=20.0h)、(95m)Tc(半衰期 T(½)=61d)、(96m+g)Tc(半衰期 T(½)=4.24d)和 (97m)Tc(半衰期 T(½)=90d)在内的长寿命 Tc 同位素特别令人关注,因为它们可能会影响临床应用中的剂量学。我们的数据表明,使用高浓缩 (100)Mo 靶和 19-24MeV 入射质子能量,回旋加速器生产的 (99m)Tc 将产生放射性核素纯度可接受的产品,适用于核医学应用。

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