Ishfaq M M, Mushtaq A, Jawaid M
Nuclear Chemistry Division, Pakistan Institute of Nuclear Science and Technology, Islamabad, Pakistan.
Biol Trace Elem Res. 1999 Winter;71-72:519-26. doi: 10.1007/BF02784240.
In recent years, much effort has been concentrated on the use of beta-emitting radionuclides for the treatment of various cancers. The reports suggested the application of 186Re and 153Sm as radiotherapeutic radionuclides for the treatment of palliative widespread skeletal metastases, whereas 166Ho was suggested as an agent for radiation synovectomy. Hence, a study on the production of 186Re, 153Sm, and 166Ho radionuclides was carried out by neutron activation of the appropriate target materials using a Pakistan Atomic Research Reactor (PARR-1) at a neutrons flux of 1 x 10(4) n/cm2 s. These radionuclides were then converted to appropriate radiopharmaceuticals for their use on animals and patients. The targets of natural Re (metal), natural Sm2O3, enriched Sm2O3 (99.06%), Sm(NO3)3 (solid), Sm(NO3)3 (liquid), and Ho2O3 were irradiated in the PARR-1. After irradiation, the purity of these radionuclides were checked by a multichannel analyzer, Canberra series 85 (MCA) coupled with HPGe detector and then measured in radioisotope calibrator Capintec ionization chamber model CRC-5RH. The effect of the irradiation time and amount of target material was investigated on the production yields of the radionuclides. The results showed an increase in the specific activity of Re with an increase in the irradiation time from 1 to 72 h, whereas a decrease in the specific activity was observed with increase in the amount of Re from 10 to 100 mg. Similar results were obtained for 153Sm and 166Ho radionuclides. The results further indicated that the specific activity of powder target was much less than the liquid targets for 153Sm. Their conversion to the appropriate radiotherapeutic radiopharmaceuticals were also carried out by investigating the experimental conditions and acceptable quality of 186Re-HEDP and 153Sm-EDTMP complexes were prepared. These complexes were then used on animals and patients which showed good performance.
近年来,人们致力于将发射β射线的放射性核素用于治疗各种癌症。报告建议将186Re和153Sm用作放射性治疗核素,用于治疗广泛的姑息性骨转移,而166Ho被建议用作放射性滑膜切除术的药物。因此,在巴基斯坦原子能研究反应堆(PARR-1)中,以1×10⁴ n/cm² s的中子通量对合适的靶材料进行中子活化,开展了对186Re、153Sm和166Ho放射性核素的生产研究。然后将这些放射性核素转化为合适的放射性药物,用于动物和患者。天然铼(金属)、天然氧化钐、富集氧化钐(99.06%)、硝酸钐(固体)、硝酸钐(液体)和氧化钬的靶材在PARR-1中进行辐照。辐照后,通过与HPGe探测器联用的Canberra系列85多通道分析仪(MCA)检查这些放射性核素的纯度,然后在Capintec电离室型号CRC-5RH的放射性同位素校准仪中进行测量。研究了辐照时间和靶材量对放射性核素产率的影响。结果表明,随着辐照时间从1小时增加到72小时,铼的比活度增加,而随着铼量从10毫克增加到100毫克,比活度降低。153Sm和166Ho放射性核素也得到了类似结果。结果还表明,对于153Sm,粉末靶的比活度远低于液体靶。通过研究实验条件,还将它们转化为合适的放射性治疗放射性药物,并制备了186Re-HEDP和153Sm-EDTMP配合物,其质量合格。然后将这些配合物用于动物和患者,表现良好。