Browsing by Author "Maddalena, DJ"

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    Development of an exchange-labelling procedure and investigation of the radiochemical stability and biodistribution characteristics for (131I) meta-iodobenzylguanidine sulphate (131I) MIBG
    (Australian Nuclear Science and Technology Organisation, 1989-08) Jenkinson, AV; Maddalena, DJ; Snowdon, GM; Sorby, PJ
    A simple exchange-labelling procedure for the radioiodination of meta-lobobenzylguanidine (MIBG) has been developed which facilitates the production of (131I) MIBG both quickly and efficiently. Stability studies indicate that labelled material if stored at reduced temperature undergoes little breakdown. Comparative biodistribution studies with a commercial source has been used to authenticate both the identity and purity of the product.
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    The development of dysprosium-165 hydroxide macroaggregates for radiation synovectomy
    (Australian Nuclear Science and Technology Organisation, 1988-06) McLaren, AB; Hetherington, ELR; Maddalena, DJ; Snowdon, GM
    The development of a dysprosium-165 product Dy-HMA which is suitable for the radiation synovectomy of arthritic joints is described. Dysprosium-165 is a short-lived (t 1 /2 = 139 min) β-emitter produced by the neutron irradiation of natural dysprosium. Dy-HMA is a suspension of macroaggregated hydroxide particles in saline with the majority of particles in the 3-5 um range. Studies in rabbits have demonstrated minimal leakage following the intra-articular injection of a knee joint. At 24 hours the accumulation in the liver is about 0.003% of the injected dose and there is considerably less in other organs and tissue. The use of Dy-HMA has considerable advantages over the presently used yttrium-90 products. The undesired leakage to and subsequent irradiation of other organs is considerably reduced. The period of hospitalisation is reduced from four days to one and the production of 165 Dy in Australia will overcome the difficulties of supply 90Y from overseas.
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    Studies on 99mtc-pertechnetate from the MEK solvent extraction generator
    (Australian Atomic Energy Commission, 1984-12) Mohammad, R; Moore, DE; Maddalena, DJ; Boyd, RE
    Analysis by gas chromatography-mass spectrometry and high performance liquid chromatography has revealed organic residues in (99m)Tc-pertechnetate obtained from 99Mo-molybdate by extraction using the organic solvent methylethylketone (MEK). The organic residues have been identified as either (i) low molecular weight carbonyl compounds such as formaldehyde acetaldehyde and acetone presumably caused by the effects of gamma-radiation on MEK or (ii) condensation products resulting from the action of strong alkali on MEK during the extraction process. The quantities of organic residues varied from batch to batch of extracted pertechnetate; up to 40 μg mL -1 was found. When these compounds were tested in rats by addition to a pyrophosphate bone-seeking radiopharmaceutical the tissue distribution was not significantly different from that in the control which contained no added compound. Assay for 99Tc in MEK-derived pertechnetate indicated up to 10 μg mL -1 of 99Tc carrier. An assessment of the biological effect of 99Tc carrier was obtained by (i) red blood cell labelling where 6 ng mL -1 of 99Tc was sufficient to reduce labelling efficiency; and (ii) pyrophosphate tissue distribution where a significant effect was obtained in the presence of 10 μg mL -1 of 99Tc carrier.
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    TISCON, a basic computer program for the calculation of the biodistribution of radionuclide-labelled drugs in rats and mice
    (Australian Atomic Energy Commission, 1983-09) Maddalena, DJ
    Animal biodistribution studies on radionuclide-labelled drugs are labour-intensive and time-consuming. A method for rapidly carrying out these studies on rats and mice is presented. An interactive computer program written in BASIC is used to calculate parameters of interest such as per cent injected dose (%ID),%ID per gram and target to non-target ratios.