Highest Concentration Of Radioactivity Research Articles

Synthesis, in vitro binding and biodistribution in B16 melanoma-bearing mice of new iodine-125 spermidine benzamide derivatives

In the course of our investigations aimed at improving the biological characteristics of iodobenzamides for melanoma therapeutic applications, four new derivatives containing a spermidine chain have been prepared and radiolabeled with 125I. In vitro studies showed that all compounds displayed high affinity for melanin superior to the reference compound BZA, thus validating our experimental approach. In vivo biodistribution was investigated in B16 melanoma-bearing mice. All four compounds, particularly benzamide 3, showed accumulation in the tumor, but lower, however, than that of BZA. Moreover, high concentrations of radioactivity in other organs, namely, the liver and lung, demonstrated nonspecific tumoral uptake. In view of these results, compounds 1 2 3 4 do not appear to be suitable radiopharmaceuticals for melanoma radionuclide therapy.

Optimisation of occupational exposures during site remediation at WISMU

Abstract Since 1991 the national corporation WISMUT GmbH has been charged with the rehabilitation of the sites of former Uranium mining and milling in East Germany. Since decommissioning and site remediation are carried out at places with enhanced dose rates and high concentrations of airborne radioactivity (Rn-222, long-lived alpha emitters), a large part of the employees is classified as occupational exposed radiation workers. Thus, in 2002, 1,073 workers were engaged with relevant works in radiation protection areas aboveground (radiation exposed workers of category B; mean effective dose: 0.3 mSv; maximum dose: 2.2 mSv), and 514 workers still prepared by underground activities the flooding of the Uranium mines (category A; mean effective dose: 0.9 mSv; maximum effective dose: 4.9 mSv). The paper presents the measures taken by WISMUT to optimise the occupational exposure. The need for implementing appropriate ALARA methods in the field of occupational exposure is last but not least caused by the fact that for a number of employees the integral exposure over the total working life time has exceeded already the 400 mSv figure.

Disposition and Pharmacokinetics of L-N6-(1-Iminoethyl)Lysine-5-Tetrazole-Amide, a Selective iNOS Inhibitor, in Rats

The metabolism, pharmacokinetics, tissue distribution, and excretion of L-N6-(1-iminoethyl)lysine-5-tetrazole-amide (L-NIL-TA), a selective inducible NO synthase (iNOS) inhibitor, were investigated in rats. [14C]L-NIL-TA is extensively metabolized after either oral or IV administration with a minor amount (<1%) excreted as the prodrug. L-NIL-TA is metabolized via a single hydrolysis pathway to form the active drug, L-N6-(1-iminoethyl)lysine (L-NIL). The oxidative deamination of 2-amino group of L-NIL forms a 2-keto metabolite (M5), which further loses carbon dioxide to yield a carboxylic acid metabolite (M6). Acetylation of L-NIL and M5 resulted in the formations of metabolites M7 and M4, respectively. Complete recovery of the radioactive dose was achieved after either oral (91.2% in urine and 4.66% in feces) and IV (99.3% in urine and 5.11% in feces) administration. L-NIL-TA-related material was extensively distributed to the tissues, with the highest concentration of radioactivity being found in muscle. Maximal concentration of radioactivity was reached between 0.5 and 1 h post-dose in the majority of tissues, with the exception of muscle and skin where the maximal concentrations were achieved at 8 h post-dose. © 2004 Wiley-Liss, Inc. and the American Pharmacists Association J Pharm Sci 93:1229–1240, 2004

Targeted alpha therapy in vivo: direct evidence for single cancer cell kill using 149Tb-rituximab.

This study demonstrates high-efficiency sterilisation of single cancer cells in a SCID mouse model of leukaemia using rituximab, a monoclonal antibody that targets CD20, labelled with terbium-149, an alpha-emitting radionuclide. Radio-immunotherapy with 5.5 MBq labelled antibody conjugate (1.11 GBq/mg) 2 days after an intravenous graft of 5.10(6) Daudi cells resulted in tumour-free survival for >120 days in 89% of treated animals. In contrast, all control mice (no treatment or treated with 5 or 300 micro g unlabelled rituximab) developed lymphoma disease. At the end of the study period, 28.4%+/-4% of the long-lived daughter activity remained in the body, of which 91.1% was located in bone tissue and 6.3% in the liver. A relatively high daughter radioactivity concentration was found in the spleen (12%+/-2%/g), suggesting that the killed cancer cells are mainly eliminated through the spleen. This promising preliminary in vivo study suggests that targeted alpha therapy with (149)Tb is worthy of consideration as a new-generation radio-immunotherapeutic approach.

Formation of benzo[a]pyrene and 7,12-dimethylbenz[a]anthracene adducts in vascular endothelia of cytochrome P4501A-induced chicken embryos.

Polycyclic aromatic hydrocarbons (PAHs) are widespread in the environment and birds may be exposed to PAHs via diet, from preening feathers contaminated with oil, or through contamination of the eggshell during embryo development. In the present study, tissue distribution and the cell-specific binding of two labeled PAHs, benzo[a]pyrene ([3H]BaP) and 7,12-dimethylbenz[a]anthracene ([3H]DMBA), were examined in chicken embryos exposed in ovo to CYP1A inducers. Tape-section autoradiograms revealed high concentrations of radioactivity in the bile, liver, kidneys, heart, and leptomeninges. Light microscopy autoradiography of solvent-extracted tissue slices showed a high and selective binding in endothelial cells in certain blood vessels in brain, heart, lung, and chest muscle. Binding was also observed in blood vessel endothelial cells in the chorioallantoic membrane (CAM), an extraembryonal tissue lining the eggshell. Endothelial binding was confirmed in CAM exposed in vitro, implying that tissue-binding metabolites were formed in situ. The CYP1A inhibitor ellipticine abolished bleeding in the target endothelial cells in CAM. It is thus concluded that blood vessel endothelia in various tissues in birds can bioactivate environmental contaminants and be targets for their toxicity. In view of its critical position beneath the shell, the CAM could be an important target for toxicants following external exposure in oviparous species.

The safety of the use of ethyl oleate in food is supported by metabolism data in rats and clinical safety data in humans

The absorption, distribution, and excretion of radiolabeled ethyl oleate (EO) was studied in Sprague–Dawley rats after a single, peroral dose of 1.7 or 3.4 g/kg body weight and was compared with a radiolabeled triacylglycerol (TG) containing only oleic acid as the fatty acid (triolein). Both test materials were well absorbed with approximately 70–90% of the EO dose absorbed and approximately 90–100% of the TG dose absorbed. At sacrifice (72 h post-dose), tissue distribution of EO-derived radioactivity and TG-derived radioactivity was similar. The tissue with the highest concentration of radioactivity in both groups was mesenteric fat. The other organs and tissues had very low concentrations of test material-derived radioactivity. Both test materials were rapidly and extensively excreted as CO 2 with no remarkable differences between their excretion profiles. Approximately 40–70% of the administered dose for both groups was excreted as CO 2 within the first 12 h (consistent with β-oxidation of fatty acids). Fecal elimination of EO appeared to be dose-dependent. At the dose of 1.7 g/kg, 7–8% of the administered dose was eliminated in the feces. At the dose of 3.4 g/kg, approximately 20% of the administered dose was excreted in the feces. Excretion of TG-derived radiolabel in the feces was approximately 2–4% for both doses. Overall, the results demonstrate that the absorption, distribution, and excretion of radiolabeled EO is similar to that of TG providing evidence that the oleic acid moiety of EO is utilized in the body as a normal dietary TG-derived fatty acid. To confirm the expected safety of EO in humans, a total of 235 subjects participated in a 12-week trial where two levels of ethyl oleate in a milk-based beverage were investigated: 8 g/day in a single serving (approximately 0.1 g/kg) and 16 g/day taken in two divided servings (approximately 0.2 g/kg). Adverse events (AEs) were recorded throughout the 12-week trial. In addition, a brief physical exam (including vital signs and body weight), ECGs, fasting serum chemistry profile, serum lipid profile, and urinalysis were performed at baseline and after study completion. Results showed the incidence of reported AEs was similar between the EO groups and the control groups. Analysis of comprehensive laboratory data revealed no EO exposure-related, clinically significant adverse changes in laboratory parameters. These studies demonstrated that EO has a highly favorable safety profile and is well tolerated in the diet.

DISPOSITION OF 3-CHLORO-4-(DICHLOROMETHYL)-5-HYDROXY-2(5 H )-FURANONE (MX) IN B6C3F1 MICE AND F344 RATS

3-Chloro-4-(dichloromethyl)-5-hydroxy-2(5 H )-furanone (MX) is a mutagenic by-product of chlorination of drinking water, particularly where the water contains humic matter. MX has been estimated to account for 50% of the mutagenic activity in some drinking water. A bioassay in rats demonstrated an increased tumor incidence, primarily in liver and thyroid glands. This study was designed to provide disposition/metabolism information in mice to evaluate the necessity of a National Toxicology Program chronic bioassay and to provide data for female rats. Radioactivity was rapidly absorbed and excreted near equally in urine (42-54%) and feces (40-51%) 72 h following oral administration of 14 C-labeled MX at single doses from 0.2 to 20 mg/kg to male and female mice and female rats. A larger percentage (71-73%) of MX-derived radioactivity was excreted in urine after an iv dose (0.2 mg/kg) in both female rats and male mice. Most MX-derived radioactivity was excreted within the first 24 h postdosing. MX was transformed to urinary and biliary metabolites. A major extremely polar urinary metabolite was tentatively identified as 1-hydroxy-1,2,2-ethanetricarboxylic acid. This metabolite is likely transformed from the MX degradation product 2-hydroxy-3-formyl-4-oxo-2-butenoic acid. Oral administration produced highest tissue/blood ratios in the following order: forestomach (>100), glandular stomach, intestine, and kidney. Intravenous administration resulted in high, prolonged levels of radioactivity in blood compared to oral dosing. Therefore, MX disposition appears to be dominated by its chemical reactivity with highest concentrations of radioactivity being found at the site of administration.

125I-Labeled PLA/PEO Block Copolymer: Biodistribution Studies in Rats

Block copolymers have a potential utility as drug carriers. In order to study their in vivo fate, the biodegradable block copolymer poly(D,L- lactide ethylene oxide) (PLA/PEO) (Mw 5000/5000) with a p-methoxyphenyl moiety was radio labeled with 125I. The copolymer was [125I] iodinated in the organic medium by a chloramine T method. The labeling efficiency was about 5%, and the agent was freed from [125I] iodide by dialysis. The tissue distribution of radioactivity was determined at 5 min, 1, 2 and 24 hrs after intravenous injection of male rats with 125I-labeled copolymer in the dose 4.5–5.5 mg/kg. After administration of the labeled copolymer, a high concentration of radioactivity in the liver during the initial time intervals was found. At the subsequent intervals after dosing, an increase in 125I activity in the bowels was determined. The distribution of radioactivity into inflamed areas was evaluated as well. The inflammatory-to-non-inflammatory muscle tissue ratios increased with time from 2.18 (5 min), 3.63 (1 h) to 3.68 (2 hrs); after 24 hrs, this ratio was significantly lower (1.70). The PLA/PEO copolymer exhibits along residence time in the blood stream and, therefore, it could be employed as a drug delivery system for inflammatory and cancer treatment.

In vivo biodistribution and pharmacokinetics of 18F-labeled human C-peptide: evaluation in monkeys using positron emission tomography

The recently observed beneficial effects exerted by C-peptide in insulin-dependent diabetes patients (IDDM) have instigated research into the mechanisms of C-peptide action as well as the location for it. Here we report in vivo biodistribution studies performed in monkeys using positron emission tomography (PET) and C-peptide labeled in the N-terminal with fluorine-18. Following iv injection of the radiotracer, dynamic decay data were collected over the chest and/or abdomens of the monkeys. The radioactivity distributed mainly to the kidneys, less to the heart and to some extent to the liver. Excretion of radioactivity into the urinary bladder was observed. Brain uptake was not detected in a static emission scan of the head performed at late times. Accumulation of radioactivity in the skeleton as a result of in vivo defluorination was not observed. Pharmacokinetic modeling of the regional concentrations of radioactivity over time resulted, for most organs, in two-compartment models. The organs with the highest radioactivity concentrations have been identified, enabling dose estimations for studies in humans with low or no C-peptide.

Radiolabeled 2'-fluorodeoxyuracil-beta-D-arabinofuranoside (FAU) and 2'-fluoro-5-methyldeoxyuracil-beta -D-arabinofuranoside (FMAU) as tumor-imaging agents in mice.

The purpose of the present study was to evaluate, in conjunction with the National Cancer Institute, the feasibility of using two thymidine analogs, 2'-fluorodeoxyuracil-beta-D-arabinofuranoside (FAU, NSC-678515) and 2'-fluoro-5-methyldeoxyuracil-beta-D-arabinofuranoside (FMAU, NSC-678516), as 18-fluorine-labeled positron emission tomography (PET) imaging agents. The in vivo distribution and DNA incorporation of [2-(14)C]FAU, [2-(14)C]FMAU, and [2-(14)C]thymidine (as a control) were studied in SCID mice bearing human xenografts of T-cell leukemia CCRF-CEM. Levels of drug-associated radioactivity in blood, tumor and normal tissues including liver, kidneys, heart, lungs, spleen, brain, and skeletal muscle were determined. At 1 h after dosing, radioactivity from all three compounds was distributed in a generally nonspecific manner, except that spleen and tumor tissue had relatively high concentrations of radioactivity from [(14)C]thymidine. At 4 h after dosing, the concentrations of radioactivity from [(14)C]thymidine and [(14)C]FMAU were relatively high in spleen and tumor tissue, and that from [(14)C]FAU was highest in tumor tissue. The tumor/skeletal muscle concentration ratios were 2.25+/-0.69 and 3.07+/-0.42 for [(14)C]FAU and [(14)C]FMAU, respectively. At 24 h after dosing, only spleen and tumor tissues contained appreciable amounts of radioactivity from either compound. In tumor tissue, the levels of radioactivity from [(14)C]FMAU were two- to threefold greater than those from [(14)C]thymidine or [(14)C]FAU. Examination of purified genomic DNA from tumor, liver, kidneys, brain, and skeletal muscle showed that, at 24 h after dosing, only DNA from tumor tissue contained appreciable concentrations of radioactivity. Radioactivity from [(14)C]FMAU in tumor DNA was 45% greater than that from [(14)C]thymidine and about threefold greater than that from [(14)C]FAU. The extent of accumulation of [(14)C]FMAU in tumor tissue and incorporation into tumor DNA indicate that [(18)F]FMAU could be useful as a functional PET tumor-imaging agent.

Distribution and elimination characteristics of 111In-DTPA-D-phe1-octreotide and 111In-DTPA-L-phe1-octreotide in rats.

The present study compares distribution and elimination characteristics of 111In-DTPA-D-Phe1-octreotide and 111In-DTPA-L-Phe1-octreotide in rats and evaluated the effect of the replacement of the terminal L-phenylalanine by D-phenylalanine on pharmacokinetic profiles of the radiolabelled peptides. Both agents exhibited rapid radioactivity clearance from the blood and most organs and tissues with no systematic and significant differences in activity accumulation. The long-term retention and high radioactivity concentrations for both compounds under study were found in the kidneys and organs with a high density of somatostatin receptors, such as the pancreas and adrenals. The residence times in these organs were longer for 111In-DTPA-D-Phe1-octreotide in comparison with 111In-DTPA-L-Phe1-octreotide. The major elimination pathway for both radiolabelled peptides was relatively rapid excretion into the urine. Analysis of the renal handling by an employment of the perfused rat kidney showed that both peptides were eliminated mainly by the mechanism of glomerular filtration. Rat liver perfusion experiments confirmed a very low value of bile clearance of radioactivity for both agents under study.

In vivo pharmacokinetics of pyribenzoxim in rats.

Pyribenzoxim, benzophenone O-[2,6-bis(4,6-dimethoxypyrimidin-2-yloxy)benzoyl]oxime, is a new post-emergence herbicide providing broad-spectrum weed control in rice fields. [14C]Pyribenzoxim was used to study the pharmacokinetics of the compound after oral administration of a dose of 1000 mg kg-1 to male Sprague-Dawley rats. The material balance ranged from 97.3 to 99.7% of the administered dose and urinary and fecal recovery accounted for 97.1%, with the majority of radioactivity recovered in feces (88.6%) by 168 h after treatment. Elimination as volatile products or as carbon dioxide was negligible. The following values were obtained for the compound in the blood: AUC0-168 h, 28,400 micrograms equiv hg-1; Tmax, 12 h; Cmax, 372 micrograms equiv g-1; half-life, 53 h. Radioactivity in tissue decreased from 96.1% of applied radiocarbon at 6 h to 0.4% at 168 h and the highest concentration of radioactivity among the tissues was observed in liver while the lowest residues were found in brain. The elimination half-lives of radioactivity from tissues was in the range of 7 to 77 h and Tmax values of 12, 24 and 12 h were observed for blood, liver and kidney, respectively. Except for that in the digestive tract, the tissue-to-blood ratio (TBR) was highest in the liver.

Validation of the preparation of individual doses of (131)I-sodium o-iodohippurate ((131)I-hippuran).

The preparation of low activity doses of (131)I-hippuran has a drawback due to its high radioactivity concentration. In this study we diluted the radiopharmaceutical with saline or phosphate buffered saline (PBS) in order to decrease the radioactivity concentration, facilitate the preparation of individual doses and validate these procedures. We prepared doses of approx. 1.85 MBq of (131)I-hippuran from 10 different batches the day before the calibration date: undiluted, and diluted 1:9 with saline or PBS. The radiochemical purity (RCP) was evaluated the day after the expiration date. The percentage of (131)I-hippuran retained on syringes was assessed in vitro, after emptying the syringe and washing it twice with water (n=3 x 27); and in vivo, after the endovenous administration of the dose and washing the syringe twice with the patient's blood (n=3 x 75). Sterility was assessed using fluid thyoglicolate medium (n=3 x 15). All RCP values were greater than those required by the European Pharmacopoeia (>96%) except one of the undiluted (131)I-hippuran (95.8%) doses. No statistical difference was observed among them. The mean undiluted (131)I-hippuran retained in vitro was 5.4% (SD=6.5%), statistically greater (P<0.01) than both saline diluted (mean=1.5%, SD=1.1%) and PBS diluted (mean=2.0%, SD=2.4%). The mean undiluted (131)I-hippuran retained in vivo was 6.4% (SD=5.4%), statistically greater (P<10-5) than both saline diluted (mean=3.1%, SD=2.3%) and PBS diluted (mean=3.1%, SD=3.1%). We concluded that: (1) the dilution of (131)I-hippuran with saline or PBS makes both the preparation of individual doses and its administration to the patient easier without decreasing its radiopharmaceutical quality; and (2) using saline or PBS diluted (131)I-hippuran the percentage of radiopharmaceutical retained on the syringes, after use, is minimized.

Rapid imaging of human melanoma xenografts using an scFv fragment of the human monoclonal antibody H11 labelled with 111In.

H11 is a human IgM monoclonal antibody which recognizes a novel tumour-associated antigen expressed on melanoma, glioma, breast cancer, colon cancer, prostate cancer, lung cancer and B-cell lymphoma. In this study, a recombinant single-chain Fv (scFv) fragment of H11 labelled with 111In was investigated for tumour imaging in athymic mice implanted subcutaneously with A-375 human melanoma xenografts. H11 scFv was derivatized with diethylenetriaminepentaacetic acid (DTPA) for labelling with 111In. The immunoreactivity of DTPA-H11 scFv against A-375 cells in vitro ranged from 23% to 36%. 111In-DTPA-H11 scFv was rapidly eliminated from the blood and most normal tissues (except the kidneys) reaching maximum tumour/blood ratios of 12:1 at 48 h post-injection. Tumours were imaged as early as 40 min after injection. The kidneys accumulated the highest concentration of radioactivity (up to 185% injected dose/g). Tumour uptake was 1-3% injected dose/g. The whole-body radiation absorbed dose predicted for administration of 185 MBq of 111In-DTPA-H11 scFv to humans was 37 mSv. The radiation absorbed dose estimates for the kidneys, spleen and intestines were 405 mSv, 698 mSv and 412 mSv, respectively. The results of this preclinical study and a concurrent phase I trial suggest a promising role for H11 scFv for tumour imaging.

Pharmacokinetics, distribution, metabolism and excretion of.

To evaluate the metabolic fate of UCN-01, a signal transduction inhibitor, blood and plasma concentrations, distribution, metabolism and excretion were investigated in rats and dogs after intravenous administration of [3H]UCN-01. The radioactivity in plasma, blood and tissues was measured after intravenous administration of UCN-01. In addition, the radioactivity excreted in bile, urine and feces was also determined. The radioactivity in rat and dog plasma disappeared triphasically with terminal half-lives of 21.3 and 27.2 h, respectively. The ratios of the blood-to-plasma concentrations ranged from 0.82 to 1.13 in rats and 0.81 to 1.73 in dogs. From 0.5 to 4 h after giving [3H]UCN-01 to rats, the radioactivity in all tissues except the brain and testes was higher than in plasma. The highest concentration was observed in the lungs followed by the liver and kidneys. The radioactivity was mainly excreted in feces, reaching 96.0% of the radioactivity dose in rats and 78.4% in dogs up to 168 h after injection. Since the biliary excreted radioactivity was 67.2% over 48 h in bile duct-cannulated rats, most of the radioactivity excreted in feces was from biliary radioactivity. There were several metabolites in bile samples, but little UCN-01. UCN-01 is mainly eliminated by the liver, and there are high concentrations of radioactivity derived from [3H]UCN-01 in all tissues except the brain and testes.

Technetium-99m-tetrofosmin: retention of nitrogen atmosphere in kit vial as a cause of poor quality material.

Technetium-99m (99Tc(m))-tetrofosmin was prepared using four different reconstitution methods. The radiochemical purity (RCP) of these products was assessed 8 h later using thin layer chromatography (TLC). Material produced using the original method supplied by the manufacturer and using an newer method, which involves the use of a vent needle and the addition of air, had acceptable RCP (mean +/- SD 94.2 +/- 1.1% and 94.7 +/- 1.7%, respectively) and similar chromatograms. In addition, both products showed good clinical efficacy and exhibited normal biodistribution behaviour. Preparing 99Tc(m)-tetrofosmin using the two other methods, one using a high radioactive concentration and the other maintaining the nitrogen content of the kit vial, gave rise to chromatograms with reduced RCP (63.5 +/- 10.9% and 61.9 +/- 7.6%, respectively) and greater levels of impurities. Although neither of these last two preparations was used clinically, we suggest that reports of poor quality images may be the result of administration of materials similar to these. Results for the high radioactive concentration method were as expected and are consistent with the restrictions imposed by the manufacturer. However, results using the last method are surprising and would suggest that the production of good quality 99Tc(m)-tetrofosmin is dependent on the quantity of nitrogen in the kit vial. We believe that the amount of nitrogen removed from the kit vial during the process of reconstitution is critical. If too much nitrogen is present this will result in poor quality material. In practice it is conceivable that there could be occasions when insufficient nitrogen is removed when following the manufacturer's original guidance, thereby leading to low RCP material. To ensure adequate nitrogen is removed during reconstitution, adoption of the manufacturer's revised method, involving the deliberate introduction of air, is therefore appropriate.

Studies on the mechanism of cancer protection by wheat bran: effects on the absorption, metabolism and excretion of the food carcinogen 2-amino-3-methylimidazo[4,5-f]quinoline (IQ).

We examined ways in which dietary supplements of wheat bran may protect against colon cancer. The effects of supplementing the diet of female Wistar rats with 10% wheat bran on the disposition and metabolism of the dietary carcinogen 2-amino-3-methylimidazo[4,5-f]quinoline (IQ) labelled with (14)C was determined. Our data show that the wheat bran had a major effect on both the distribution and metabolism of IQ. At a low dose of IQ (1 mg/kg), we unexpectedly found that up to 2 h after gavage there were higher concentrations of radioactivity in the plasma of rats fed wheat bran compared with the controls, but there were lower concentrations of radioactivity after 2 h. At a high dose of IQ (50 mg/kg), there were always lower concentrations of radioactivity in the plasma of rats fed wheat bran compared with the control rats. One of the most marked effects of wheat bran was apparently to significantly retard the metabolism of IQ in the plasma when this was fed at either dose. There were also differences between the rats fed wheat bran and the control in the concentrations and types of IQ metabolites in the urine.

Radiolabeling, stability, and body distribution in rats, of low molecular weight polylactide homopolymer and polylactide–polyethyleneglycol copolymer

In order to study its fate in vivo, a low molecular-weight polylactide homopolymer was derivatized with a p-methoxyphenyl moiety, so as to make it susceptible to radiolabeling with 125 I . A low molecular weight polylactide–polyethyleneglycol copolymer capped with a p-methoxyphenyl residue was also synthesized. The derivatized polymers were successfully [ 125 I ]iodinated in organic medium. The radiolabeled products were freed from [ 125 I ]iodide by dialysis and shown to be stable for 24 h on incubation at 37°C in buffered saline or in blood. On longer incubation at 37°C in buffered saline the radiolabeled polylactide released [ 125 I ]iodide and [ 125 I ]iodinated 3-( p-methoxyphenyl)propionic acid. The radiolabeled copolymer was more stable on incubation at 37°C in buffered saline, but some [ 125 I ]iodide was released. The tissue distribution of radioactivity was determined 5 min, 1, 5 and 24 h after injecting male rats with 125 I -labeled homopolymer or copolymer. Intravenous, intraperitoneal and subcutaneous injection routes were employed. Further rats were injected with [ 125 I ]iodide, to aid interpretation of the data. After administration of labeled homopolymer, a high concentration of radioactivity was found in the liver tissue. The levels slowly decreased over 24 h, and the polymer was successively found in the small and large intestine and the faeces. This is probably indicative of excretion via the bile. Concurrently radioactivity was excreted in the urine. After administration of labeled copolymer, a high concentration of radioactivity was found in the liver and the residual soft tissue, the latter fraction containing two-thirds of the radioactivity one hour after injection. The precise tissue location that this result indicates was not identified. After 1 h radioactivity was excreted in the faeces, again probably via the bile, and in the urine. Tissue distributions after intraperitoneal or subcutaneous injections were concordant with the above results and interpretations, with the additional factor of slow clearance from the injection site.

Technetium-99m HYNIC-annexin V: a potential radiopharmaceutical for the in-vivo detection of apoptosis.

Either inadequate or excessive apoptosis (programmed cell death) is associated with many diseases. A method to image apoptosis in vivo, rather than requiring histologic evaluation of tissue, could assist with therapeutic decision making in these disorders. Programmed cell death is associated with a well-choreographed series of events resulting in the cessation of normal cell function, and the ultimate disappearance of the cell. One component of apoptosis is signaling adjacent cells that this cell is committing suicide by externalizing phosphatidylserine to the outer leaflet of the cell membrane. Annexin V, a 32-kDa endogenous human protein, has a high affinity for membrane-bound phosphatidylserine. We have coupled annexin V with the bifunctional hydrazinonicotinamide reagent (HYNIC) to prepare technetium-99m HYNIC-annexin V and demonstrated localization of radioactivity in tissues undergoing apoptosis in vivo. In this report we describe the results of a series of experiments in mice and rats to characterize the biologic behavior of (99m)Tc-HYNIC- annexin V. Biodistribution studies were performed in groups of rats at 10-180 min after intravenous injection of (99m)Tc-HYNIC-annexin V. In order to estimate the degree of apoptosis required for localization of (99m)Tc-annexin V in vivo, mice were treated with dexamethasone at doses ranging from 1 to 20 mg/kg, 5 h prior to (99m)Tc-HYNIC-annexin V administration, to induce thymic apoptosis. Thymus was excised 1 h after radiolabeled HYNIC-annexin V injection; thymocytes were isolated, incubated with Hoechst 33342 followed by propidium iodide, and analyzed on a fluorescence-activated cell sorter. Each sorted cell population was counted in a scintillation counter. To test (99m)Tc-HYNIC-annexin V as a tracer for external radionuclide imaging of apoptotic cell death, radionuclide imaging of Fas-defective mice (lpr/lpr mice) and wild-type mice treated with the antibody to Fas (anti-Fas) was carried out 1 h post injection. Rat biodistribution studies demonstrated a blood clearance half-time of less than 10 min for (99m)Tc-HYNIC-annexin V. The kidneys had the highest concentration of radioactivity at all time points. Studies in the mouse thymus demonstrated a 40-fold increase in (99m)Tc-HYNIC-annexin V concentration in apoptotic thymocytes compared with the viable cell population. A correlation of r=0.78 was found between radioactivity and flow cytometric and histologic evidence of apoptosis. Imaging studies in the lpr/lpr and wild-type mice showed a substantial increase of activity in the liver of wild-type mice treated with anti-Fas, while there was no significant change, irrespective of anti-Fas administration, in lpr/lpr mice. Excellent images of hepatic apoptosis were obtained in wild-type mice 30 min after injection of (99m)Tc-HYNIC-annexin V. The imaging results were consistent with histologic analysis in these animals. In conlusion, these studies confirm the value of (99m)Tc-HYNIC-annexin V uptake as a marker for the detection and quantification of apoptotic cells in vivo.

Radiological Implications of Using Phosphogypsum as a Building Material in Brazil

Large quantities (approximately 69 million tons) of phosphogypsum are produced as a by-product of the fertiliser industry in Brazil. Although phosphogypsum is mainly calcium sulphate dihydrate, it contains a high level of impurities, including uranium and thoriu decay products, which originate primarily from the source phosphate rock used in fertiliser production. The material is stockpiled on huge stacks which are a potential threat to the surrounding air and especially groundwater resources. Phosphogypsum can replace some of the natural components of building materials. However, it contains a higher radioactivity concentration than the natural products and its use in houses may lead to increased radiation doses to the inhabitants. Although a considerable amount of compositional data exist in countries where phosphogypsum presents higher levels of radioactivity. comparatively few data are available concerning the Brazilian phosphogypsum. The average specific concentrations of 236 Ra. 232 Th and 40 K in the Brazilian phosphogypsum, from different locations, varied from 22 to 672 Bq.kg -1 , from 9 to 174 Bq.kg -1 and from <4.2 to 25 Bq.kg -1 . A simple model is applied to the results to calculate the external and internal irradiation for people living in a common house constructed with this material. The results are examined in the light of standards for indoor exposure adopted in some countries and the criteria set up in the OECD report.