Stability of a mixture of technetium Tc 99m sulfur colloid and lidocaine hydrochloride.

PURPOSE: The stability of a mixture of technetium Tc 99m sulfur colloid and lidocaine hydrochloride for up to eight hours was studied. METHODS: Three vials of technetium Tc 99m sulfur colloid were compounded according to the manufacturer's instructions. From each of the three vials, five samples were withdrawn into syringes with needles: 0.4, 0.45, 0.5, 0.63, and 1 mCi for testing after storage for zero, one, two, four, and eight hours, respectively. Each syringe contained the customary patient dose of 0.4 mCi at the time of testing. Fresh 0.9% sodium chloride injection was used to bring the volume of each syringe to 0.2 mL, and 0.2 mL of lidocaine hydrochloride 1% was added to bring the final volume to 0.4 mL. Measurements of pH, radiochemical purity, and particle size were conducted after the indicated storage times for each group of samples. RESULTS: The pH of samples showed no substantial change over the eight-hour storage period, with individual values in the range of 4.5-5.5. Radiochemical purity did not change substantially, with values ranging from 98.9% to 99.9%. There was no meaningful change in the amount of radioactivity retained by filtration and no increase in particle size. CONCLUSION: Adding lidocaine hydrochloride 1% to syringes containing technetium Tc 99m sulfur colloid and storing the syringes for up to eight hours had no effect on the pH or radiochemical purity of the mixture or on the radioactivity retained by a filter.     

Absorption, tissue distribution, and excretion of 3H-labeled arbaprostil in the male rat

A single dose of arbaprostil-11 beta-3H (4 micrograms/kg) was administered orally to male rats. A maximum plasma radioactivity concentration equivalent to 2.5 to 2.8 nanograms of the prostaglandin per ml was reached at 30 minutes and was maintained until 120 minutes after drug administration. The plasma drug disappearance half-life was 2.6 hours. These results along with data from tissue distribution studies suggested a rapid uptake of radiolabeled arbaprostil by the glandular stomach tissue followed by an apparent zero-order release of drug-related radioactivity from this tissue "reservoir" into the plasma. Drug-related radioactivity was excreted rapidly, with 96 to 99% of the urinary excretion and 82 to 97% of the fecal excretion being completed within 24 hours. A total of 49.6 +/- 3.5% of the orally administered dose was excreted in the urine and 46.7 +/- 3.9% in the feces. No radioactive residues were detected in the animals at the end of the 120 hour specimen collection period. The metabolic stability of the 11 beta-tritium label and the suitability of arbaprostil-3H for use in human studies was demonstrated.     

(99m)Tc-labeled murine ior C5 monoclonal antibody in colorectal carcinoma patients: pharmacokinetics, biodistribution, absorbed radiation doses to normal organs and tissues and tumor localization

Monoclonal Antibody (mAb) ior C5 is a murine IgG(1) that recognizes the tumor associated antigen (TAA) ior C2, a cell surface O-linked glycoprotein carbohydrate chain not present in most normal tissues and homogeneously expressed in the cytoplasm of normal colon epithelium and heterogeneously expressed in more than 83% of primary colorectal carcinomas. This study was designed to investigate the pharmacokinetics, biodistribution and the absorbed radiation doses of (99m)Tc-labeled mAb ior C5 antibody in colorectal tumor patients. Ten patients were administered 3 mg of anti-O-linked glycoprotein carbohydrate chain TAA ior C2 murine monoclonal antibody ior C5 radiolabeled with (99m)Tc activity of 1435.0 +/- 123 MBq by intravenous (i.v.) bolus infusion. Blood and urine samples were collected from 4 out of 10 patients at timed intervals from 10 min and up to 24 h after injection of the (99m)Tc-labeled mAb ior C5 for pharmacokinetic studies. Whole body images were taken in 5 out of 10 patients for quantitative normal organ biodistribution and dosimetry studies and planar anterior and posterior and SPECT images were taken in 5 out of 10 patients for tumor localization. Mean absorbed doses were estimated using the methods developed by the Medical Internal Radiation Dose (MIRD) committee. The effective dose equivalent (EDE) and effective dose (ED) were calculated as prescribed in International Commission on Radiological Protection (ICRP) publications 30 and 60. Plasma disappearance curves of (99m)Tc-labeled murine antibody ior C5 were best fit by a two-compartment model in all patients with (t(1/2alpha)) of 4.32 +/- 2.18 h and (t(1/2beta) of 32.6 +/- 3.82 h. Among the main target organs, accumulation of the radiolabeled antibody was found in liver (9.38 +/- 0.80%), heart (8.92 +/- 0.94%) and spleen (1.37 +/- 0.30%) at 5 min post-administration. These values were reduced at 24 h to (5.91 +/- 0.73%) and (0.62 +/- 0.22%), respectively, for the heart and spleen and increased to (9.78 +/- 1.99%) for liver. Estimates of radiation absorbed dose to normal organs in rad/mCi administered were: whole body, 0.0181 +/- 0.0017; heart wall, 0.0768 +/- 0.0090; kidneys, 0.0530 +/- 0.0260; liver, 0.0565 +/- 0.0109 and spleen, 0.0540 +/- 0.0128. The effective dose equivalent and effective dose estimates for adults were 0.0314 +/- 0.0031 and 0.0249 +/- 0.0027 rem/mCi administered. This feasibility study indicates that the O-linked glycoprotein carbohydrate chain TAA ior C2 is expressed in primary and metastatic colorectal carcinomas and shows very limited expression in normal adult tissues. The very good pattern of biodistribution of (99m)Tc-labeled mAb ior C5 in patients will allow imaging of colorectal carcinoma lesions.     

The disposition of primaquine in the isolated perfused rat liver. Effect of dose size

The disposition of 14C-radiolabeled primaquine in the isolated perfused rat liver preparation was investigated after the administration of 0.5-, 1.5-, and 5.0-mg doses of the drug. The pharmacokinetics of primaquine in this experimental model were dependent on dose size. Increasing the dose from 0.5 to 5.0 mg produced a significant reduction in clearance from 11.6 +/- 2.5 to 2.9 +/- 1.0 ml X min-1. This decrease was accompanied by a disproportionate increase in the value of AUC from 25.4 +/- 5.9 to 1128.6 +/- 575.7 micrograms X min X ml-1, elimination half-life from 33.2 +/- 10.7 to 413.0 +/- 239.3 min, and volume of distribution from 547.7 +/- 153.1 to 1489.0 +/- 249.0 ml. Furthermore, primaquine exhibited dose dependency in its pattern of metabolism. While the carboxylic acid derivative of primaquine was not detected in perfusate after the 0.5-mg dose, it was the principal perfusate metabolite after the 5.0-mg dose. Primaquine was subject to extensive biliary excretion at all doses; the total amount of 14C radioactivity excreted in the bile decreased from 60 to 30% as the dose of primaquine was increased from 0.5 to 5.0 mg. The metabolite composition of radioactivity excreted in the bile was also examined. Total recovery of the administered radioactivity from bile, perfusate, and liver was essentially complete at all doses. The perfusate concentrations at the conclusion of each experiment (i.e. 5 hr) did not differ among dosage groups. By contrast, increased dose size produced a reduction in the amount of 14C radioactivity recovered in bile which was associated with increased levels of 14C in the liver.     

Studies on metabolism and pharmacokinetics of alpha-acetyldigitoxin in man (author's transl)]

3H-alpha-Acetyl-digitoxin was administered to 5 patients i.v. and 3 patients p.o. The half-life of label in the plasma was 8.5 +/- 1 (i.v.) and 8.8 +/- 1 (p.o.) days. 20.9 +/- 3.6% (i.v.) and 21.3 +/- 2.9% (p.o.) of the radioactive dose were excreted into the urine in 6 days. Two patients excreted within 18 days 14.3 and 16.1% of the given dose with the stool. After oral administration 22.3% of the orally administered 3H-activity were eliminated into the feces by one patient. 63% (i.v.) and 53% (p.o.) of the chlorofrom-extracted 3H-activity in the urine could be attributed to digitoxin by means of thin-layer chromatography. The volatile content of plasma radioactivity was 4.07 +/- 0.1% (i.v.) and 6.78 +/- 0.2% (p.o.). The protein binding of a 4%. Albumin solution was 83 +/- 0.54%, for plasma 80.8 +/- 2%.     

Accounting for radioactivity before and after nebulization of tobramycin to insure accuracy of quantification of lung deposition.

The ability to predict drug deposition of inhaled drugs used in cystic fibrosis (CF) is important if there is a need to target specific doses of drug to the lungs of individual patients. The gold standard of measuring pulmonary deposition is the quantification of an aerosolized radiolabel either mixed with the drug solution or tagged directly to the compound of interest. Accuracy of the quantification could be assured if there is agreement between the amount of radioactivity before and after administration. Before administration, the radiolabel is concentrated in the well of the nebulizer, whereas after administration, it is distributed throughout the nebulizer, the expiratory filter and connectors, and the upper airway, stomach, trachea, and lung. Not only is the geometry of the distribution that is presented to the gamma camera different, but there are different attenuation factors for the various body tissues. The primary aim of this study was to evaluate the accuracy of the quantification of deposition. Secondary goals were to compare in vitro nebulizer performance with that measured in vivo during the deposition study. Eighty milligrams of tobramycin and technetium bound to human serum albumin was administered to 10 normal adults using a Pari LC Jet Plus (Pari Respiratory Equipment, Inc., Richmond, VA) breath-enhanced nebulizer. Techniques were developed that allowed for the accounting of 99 +/- 2% of the initial radioactivity. The fraction of the rate of lung deposition to total body deposition was the in vivo respirable fraction (0.62 +/- 0.07), which closely agreed with in vitro measurements of respirable fraction (0.62 +/- 0.04). Drug output measured from the change in weight and concentration in the nebulizer systematically overestimated drug output measured by the deposition study. The results indicate that 11.8 of the initial 80 mg would be deposited in the lungs. This technique could be adapted to accurately quantify the amount of deposition on any inhaled therapeutic agent, but caution must be used when extrapolating performance of a nebulizer on the bench to expected deposition in patients.     

Studies on the mechanism of haloacetonitriles toxicity: quantitative whole body autoradiographic distribution of [2-14C]chloroacetonitrile in rats

Chloroacetonitrile (CAN), a drinking water disinfectant by-product, possesses mutagenic and carcinogenic properties. The objective of this study was to investigate the biologic fate of CAN, using whole body autoradiographic (WBA) techniques. Male Sprague-Dawley rats were treated with a tracer dose of [2-14C]CAN (i.v., 88 muCi/kg, spec. act 4.07 mCi/mmol). At various time intervals (0.08, 1, 3, 6, 12, 24, and 48 h) after treatment, rats were processed for WBA. Over 12 h after administration, the radioactivity excreted in urine, feces, and exhaled as 14CO2 accounted for 51%, 2.7%, and 12% of the dose, respectively. Only 0.8% of the administered dose was exhaled as unchanged CAN. At an early time interval (5 min) extensive accumulation of radioactivity was observed in liver, kidney, and gastrointestinal (G.I.) walls. In addition, high levels of 14C were detected in the thyroid gland, lung bronchioles, adrenal cortex, salivary gland, and testes. At 1 h following administration, the olfactory bulb, olfactory receptor area of the brain and lumbar cistern showed high accumulations of radioactive CAN or its equivalents. At 3, 6, and 12 h after treatment, the radioactivity diffused homogeneously in all tissues and reconcentrated in several organs at later time periods (24 and 48 h). Our studies indicate extensive metabolic biotransformation of CAN in rats. The retention of radioactivity in the tissues of the thyroid gland, G.I., testes, brain and eye suggest that those organs are potential target sites of CAN toxicity.     

The pharmacokinetics of nitrendipine. I. Absorption, plasma concentrations, and excretion after single administration of [14C]nitrendipine to rats and dogs

[14C]nitrendipine (3-ethyl 5-methyl 1,4-dihydro-2,6-dimethyl-4-(3-nitrophenyl)-3,5-pyridine dicarboxylate, Bay e 5009, Baypress, Bayotensin) was administered to rats and dogs (intravenously, orally, intraduodenally, 0.5-50 mg/kg) in order to investigate absorption, disposition, and excretion of parent compound and metabolites. The absorption of radioactivity following oral administration of [14C]nitrendipine was rapid and almost complete in both species. Maximum concentrations of total radioactivity in plasma were reached after 1.2 (rat) or 0.7 h (dog). The radioactivity was eliminated from plasma with terminal half-lives of 57 (rat) and 188 h (dog) during an observation period up to 10 and 9 days, respectively. Unchanged nitrendipine contributed to the AUC of total radioactivity only 8-9% after intravenous and 1-2% after oral administration. The bioavailability of nitrendipine after oral administration amounted to 12% in rats and 29% in dogs due to a strong first pass elimination process. About two thirds of the radioactivity administered were excreted via faeces, one third via urine. Distinct sex-differences in the excretion pattern could be found in rats but not in mice. They were attributed to well-known sex differences of the metabolic capacities in rat liver. In rats the radioactivity excreted via bile (about 75% of the dose) was subject to a marked entero-hepatic circulation, about 50% of the amount excreted being reabsorbed. The radioactive residues in the body were low (0.5% of the dose after 2 days in rats; less than or equal to 0.6% after 9 days in dogs).     

The challenges of quantitative measurement of lung deposition using 99mTc-DTPA from delivery systems with very different delivery times.

In quantifying aerosol delivery, the drug is often mixed with a radiolabel such as (99m)Tc-DTPA whose deposition is used as a proxy for the drug. (99m)Tc-DTPA deposited in the lung is cleared by a combination of absorption into the pulmonary circulation and mucociliary clearance. If administration is not instantaneous, the image will not include that clearance during administration, a problem raised if comparing devices with different administration times. However, if rates of clearance are measured, it will be possible to "correct" the initial image for the clearance that occurred during administration and before counting. Five adult males inhaled a 5-mL solution containing (99m)Tc-DTPA from a breath enhanced jet nebulizer (LC Plus)over the course of 10 min and a 1.25-mL solution from a vibrating membrane device (eFlow), which was delivered in 2.5 min. Quality assurance was the radioactivity count balance (RCB) defined as the difference in the total radioactivity pre-nebulization less post, divided by pre, and expressed as a percentage. Attenuation calculations used a (57)Co flood source (Macey and Marshall). The "correction" for the clearance of (99m)Tc-DTPA was 0.91 +/- 0.04 (mean +/- SD) for the LC Plus) and 0.96 +/- 0.02 for the eFlow). RCB was -0.6 +/- 3.5% for the LC Plus and -4.7 +/- 6.4% for the eFlow, implying acceptable accuracy. For the LC Plus, lung deposition was 15.9(13.4, 18.4)% (mean and 95% CI) of the charge dose, and for the eFlow it was 32.0(29.0, 35.0)%. This technique gave an acceptable level of accuracy for quantitative planar imaging and allowed the comparison of delivery from devices with very different rates of delivery.     

A pharmacokinetic study of JOMO-tech in rats.

A pharmacokinetic study of 99mTc labelled JOMO-tech in rats (after intravenous administration of a dose of 20 microg/kg body weight) was conducted. JOMO-tech is a heterogeneous extract derived from Nocardia opaca cell walls. An excellent fitting of the three-compartmental disposition model was achieved. The first apparent elimination half-life was very short (t1/2alpha = 0.0572 +/- 0.01383 h) followed by longer second apparent elimination half-life (t1/2beta = 0.817 +/- 0.1922 h), whereas at late post-treatment time the third apparent elimination half-life (t1/2gamma = 21.7 +/- 2.1 h) proved to be long. The peak concentration in the blood extrapolated to t = 0 yielded 32.3 +/- 7.54 ngeq/ml, this being approximately 2-fold the amount of that measured in the 5th post-treatment minute (16.84 +/- 1.447 ngeq/ml). It was determined that the main route of excretion was renal. Up to the 48th post-treatment hour, 30.03 +/- 2.788% of the dose was excreted via the urine, and only 6.71 +/- 0.973% was excreted in the feces by the 7 rats evaluated. The amount of radioactivity detected in selected tissue samples (expressed in ngeq JOMO-tech/g wet tissue) decreased in the sequence liver > kidneys > lungs > blood > plasma. In the time period studied, the highest amount of the dose was found in the liver, whereas up to the 3rd post-treatment day a practically equivalent part of the dose was found in the excreta and in the liver.     

Mass balance study of [14C] rabeprazole following oral administration in healthy subjects

The study was designed to determine the excretion balance of radiolabeled rabeprazole in urine and feces and to examine the metabolite profile in plasma, urine and feces after a single oral dose of [14C] rabeprazole, preceded by once daily dose of rabeprazole for 7 days. Six healthy subjects were enrolled in this study. The study was a single-center, open-label, multiple-dose, mass-balance study. Each subject received a single 20 mg dose of rabeprazole tablet for 7 days followed by the administration of 20 mg of [14C] rabeprazole as an oral solution after an overnight fast on Day 8. After oral dosing of [14C] rabeprazole, the mean Cmax of total radioactivity was 1,080 +/- 215 ng equivalent/ml with 0.33 +/- 0.13 hours of the mean tmax. The apparent elimination half-life of total [14C] radioactivity was 12.6 +/- 3.4 hours. The total [14C] recovery in urine and feces was 99.8 +/-0.7% by 168 hours after oral administration of [14C] rabeprazole, and mean cumulative [14C] radioactivity excreted in urine was 90.0 +/- 1.7% by 168 hours and 79.8 +/- 2.5% of the radioactivity was excreted in urine within 24 hours. Excretion via feces added to the total by 9.8%. The major radioactive component in the early plasma samples was rabeprazole, however the thioether and thioether carboxylic acid metabolites were the main radioactive components in the later plasma sample. These results support the previous finding that the substantial contribution of the non-enzymatic thioether pathway minimizes the effect of CYP2C19 polymorphism on the inter-individual variation ofplasma clearance of rabeprazole compared with other PPIs. Low levels of the sulfone metabolite were detected only in early plasma samples. No rabeprazole was detected in any urine and feces samples. The main radioactive components in urine were thioether carboxylic acid and mercapturic acid conjugate metabolites, and in the feces, the thioether carboxylic acid metabolite. The administration of [14C] rabeprazole was safe as evidenced by the lack of serious adverse events and the fact that all observed events were mild in intensity. [14C] rabeprazole was rapidly absorbed after oral administration and mostly excreted in urine.     

Metabolism and excretion of [(14)C]celecoxib in healthy male volunteers.

We determined the disposition of a single 300-mg dose of [(14)C]celecoxib in eight healthy male subjects. The [(14)C]celecoxib was administered as a fine suspension reconstituted in 80 ml of an apple juice/Tween 80/ethanol mixture. Blood and saliva samples were collected at selected time intervals after dosing. All urine and feces were collected on the 10 consecutive days after dose administration. Radioactivity in each sample was determined by liquid scintillation counting or complete oxidation and liquid scintillation counting. Metabolic profiles in plasma, urine, and feces were obtained by HPLC, and metabolites were identified by mass spectrometry and NMR. [(14)C]Celecoxib was well absorbed, reaching peak plasma concentrations within 2 h of dosing. [(14)C]Celecoxib was extensively metabolized, with only 2.56% of the radioactive dose excreted as celecoxib in either urine or feces. The total percentage of administered radioactive dose recovered was 84.8 +/- 4.9%, with 27.1 +/- 2.2% in the urine and 57.6 +/- 7.3% in the feces. The oxidative metabolism of celecoxib involved hydroxylation of celecoxib at the methyl moiety followed by further oxidation of the hydroxyl group to form a carboxylic acid metabolite. The carboxylic acid metabolite of celecoxib was conjugated with glucuronide to form the 1-O-glucuronide. The percentages of the dose excreted in the feces as celecoxib and the carboxylic acid metabolite were 2.56 +/- 1.09 and 54.4 +/- 6.8%, respectively. The majority of the dose excreted in the urine was the carboxylic acid metabolite (18.8 +/- 2.1%); only a small amount was excreted as the acyl glucuronide (1.48 +/- 0.15%).     

Metabolism and disposition of 4-(methylnitrosamino)-1-(3-pyridyl)-1- butanone (NNK) in rhesus monkeys.

Metabolism and disposition of the tobacco-specific N-nitrosamine, 4-(methylnitrosamino)-1-(3-pyridyl)-1-butanone (NNK), a potent rodent lung carcinogen, were studied in rhesus monkeys. In three males receiving a single i.v. dose of [5-3H]NNK (0.72 mCi; 4.6-9.8 microg/kg), urine was collected for 10 days. Within the first 24 h, 86.0 +/- 0.7% of the dose was excreted. NNK-derived radioactivity was still detectable in urine 10 days after dosing (total excretion, 92.7 +/- 0.7%). Decay of urinary radioactivity was biexponential with half-lives of 1.7 and 42 h. Metabolite patterns in urine from the first 6 h closely resembled those reported previously for patas monkeys; end products of metabolic NNK activation represented more than 50% of total radioactivity. At later time points, the pattern shifted in favor of NNK detoxification products (60-70% of total radioactivity in urine), mainly 4-(methylnitrosamino)-1-(3-pyridyl)-1-butanol (NNAL) and its O-glucuronide conjugates. One female rhesus monkey received a single i.v. dose of [5-3H]NNK (1.72 mCi; 28.4 microg/kg) under isoflurane anesthesia; biliary excretion over 6 h (0.6% of the dose) was 10 times less than predicted by our previously reported rat model. No preferential excretion of NNAL glucuronide was observed in monkey bile. Collectively, these results suggest that the rhesus monkey could be a useful model for NNK metabolism and disposition in humans.     

Effect of mitomycin-C on the bioavailability of the radiopharmaceutical (99m)technetium-phytic acid in mice: a model to evaluate the toxicological effect of a chemical drug.

The many desirable characteristics of technetium-99m ((99m)Tc) have stimulated the development of labelling techniques for different molecular and cellular structures. It is generally accepted that a variety of factors can alter the biodistribution of radiopharmaceuticals and one such factor is drug therapy. Because patients on chemotherapeutic treatment receive a radiopharmaceutical in a nuclear medicine procedure, we have studied in Balb/c mice the effect of mitomycin-C on the biodistribution of the radiopharmaceutical (99m)Tc-phytic acid ((99m)Tc-PHY) used in hepatic scintigraphy. Mitomycin-C is an antineoplastic agent obtained from Streptomyces caesptosus and is used on the treatment of disseminated adenocarcinoma of the stomach or pancreas. Three doses of mitomycin-C were administered via the ocular plexus into Balb/c mice. One hour after the last dose, (99m)Tc-PHY was administered and the animals were sacrificed. The organs were isolated, the radioactivity was determined in a well counter and the percentages of radioactivity in the organs were calculated. The results have shown that the percentage radioactivity has been increased in stomach, spleen, lung, thyroid and bone, decreased in pancreas and thymus and not altered in ovary, uterus, kidney, heart, liver and brain. The changes in the distribution of (99m)Tc-PHY may be the result of metabolic processes and/or therapeutic actions produced by the administration of mitomycin-C.     

Effect of technetium Tc 99m pertechnetate on bacterial survival in solution

Survival of Staphylococcus epidermidis (10(2) organisms/ml) in solutions containing various levels of radioactivity was assessed. Six test preparations contained nonbacteriostatic 0.9% sodium chloride solution; four of these contained technetium Tc 99m pertechnetate (99mTcO-4) in various quantities (80, 250, 500, and 750 mCi). A fifth contained technetium that had decayed to an essentially nonradioactive form, and a sixth contained 0.9% sodium chloride solution only. Each of the six 20-ml solutions was inoculated with 2 ml of single-strength trypticase soy broth (TSB) containing 10(3) organisms/ml. At various times up to 12 hours after inoculation, 1-ml aliquots of each test solution were withdrawn and passed through 0.22-micron filters, thereby preventing further irradiation of the filtered organisms. The filters were incubated in single-strength TSB at 37 degrees C, and samples were examined for turbidity at 24, 48, and 72 hours. After 24 hours, 25 of the 36 sample tubes showed turbidity; after 48 hours, the turbid samples totaled 28. Bacteria in the two nonradioactive solutions remained viable throughout the 12-hour sampling period. Accumulated doses of radiation obtained in the 250-, 500-, and 750-mCi samples inhibited bacterial growth. To be a valid quality-control measure, sterility monitoring of prepared radiopharmaceutical dosage forms may need to be performed concurrently with their preparation.     

Disposition and biotransformation of the acetylenic retinoid tazarotene in humans

Oral tazarotene, an acetylenic retinoid, is in clinical development for the treatment of psoriasis. The disposition and biotransformation of tazarotene were investigated in six healthy male volunteers, following a single oral administration of a 6 mg (100 microCi) dose of [14C]tazarotene, in a gelatin capsule. Blood levels of radioactivity peaked 2 h postdose and then rapidly declined. Total recovery of radioactivity was 89.2+/-8.0% of the administered dose, with 26.1+/-4.2% in urine and 63.0+/-7.0% in feces, within 7 days of dosing. Only tazarotenic acid, the principle active metabolite formed via esterase hydrolysis of tazarotene, was detected in blood. One major urinary oxidative metabolite, tazarotenic acid sulfoxide, accounted for 19.2+/-3.0% of the dose. The majority of radioactivity recovered in the feces was attributed to tazarotenic acid representing 46.9+/-9.9% of the dose and only 5.82+/-3.84% of dose was excreted as unchanged tazarotene. Thus following oral administration, tazarotene was rapidly absorbed and underwent extensive hydrolysis to tazarotenic acid, the major circulating species in the blood that was then excreted unchanged in feces. A smaller fraction of tazarotenic acid was further metabolized to an inactive sulfoxide that was excreted in the urine.     

Pharmacokinetics of digoxin and main metabolites/derivatives in healthy humans

Three healthy, young male volunteers received doses of 0.6 and 1.2 mg of specifically labelled [3H]digoxin each by intravenous (i.v.) bolus injection and oral (p.o.) administration in accordance with a randomized four-way crossover design. Plasma, urine, and feces samples were taken over an interval of 144 h after drug administration. Total radioactivity and individual radioactivity assignable to digoxin and its metabolites were measured. After i.v. administration, the mean +/- SD recovery of total radioactivity, as percent of dose, was complete, urine 81.3 +/- 2.0% and feces 17.1 +/- 2.8%. The mean recovery of digoxin and that of its metabolites in urine was digoxin 75.6 +/- 3.0%, dihydrodigoxin 2.8 +/- 1.6%, digoxigenin bisdigitoxoside 1.6 +/- 0.1%, and additional metabolites 1.5 +/- 0.3%. Judging from the metabolite data in urine and considering the 5% impurity of the administered dose, metabolism of digoxin appeared to be insignificant after i.v. administration. The total and renal clearances of digoxin were, on average, 193 +/- 25 ml min-1 and 152 +/- 24 ml min-1. The mean steady state volume of distribution was 489 +/- 73 L and the mean residence time 41 +/- 5 h. For the metabolites dihydrodigoxin and digoxigenin bisdigitoxoside the mean residence times were on average 35 +/- 9 h and 53 +/- 11 h; the renal clearances were 79 +/- 13 ml min-1 and 100 +/- 26 ml min-1. After p.o. administration, the mean recovery of total radioactivity, as percent of the dose, was also complete, urine 65.7 +/- 1.98% and feces 31.6 +/- 7.6%. The mean recovery of digoxin and that of its metabolites, as percent of dose, in urine was digoxin 51.5 +/- 11.4%, dihydrodigoxin 4.5 +/- 3.9%, digoxigenin bisdigitoxoside 1.9 +/- 0.1%, polar metabolites 5.5 +/- 3.8%, and additional metabolites 1.3 +/- 0.6%. After p.o., as compared to i.v. administration, larger amounts of all the metabolites were formed in accordance with first pass metabolism/degradation. Maximum mean plasma concentrations of 4.3 +/- 2.5 ng ml-1 and 9.5 +/- 1.1 ng ml-1 for digoxin were observed at 40 +/- 10 min after p.o. administration of 0.6 and 1.2 mg of the drug. The mean absolute bioavailability of digoxin from an aqueous solution was 0.67 +/- 0.14. Renal clearance and mean oral residence time for digoxin were on average 176 +/- 28 ml min-1 and 37 +/- 4 h after p.o. administration.(ABSTRACT TRUNCATED AT 400 WORDS)     

Pharmacokinetics, tissue distribution, metabolism, and excretion of celecoxib in rats.

The pharmacokinetics, tissue distribution, metabolism, and excretion of celecoxib, 4-[5-(4-methylphenyl)-3-(trifluoromethyl)-1H-pyrazol-1-yl] benzenesulfonamide, a cyclooxygenase-2 inhibitor, were investigated in rats. Celecoxib was metabolized extensively after i.v. administration of [(14)C]celecoxib, and elimination of unchanged compound was minor (less than 2%) in male and female rats. The only metabolism of celecoxib observed in rats was via a single oxidative pathway. The methyl group of celecoxib is first oxidized to a hydroxymethyl metabolite, followed by additional oxidation of the hydroxymethyl group to a carboxylic acid metabolite. Glucuronide conjugates of both the hydroxymethyl and carboxylic acid metabolites are formed. Total mean percent recovery of the radioactive dose was about 100% for both the male rat (9.6% in urine; 91.7% in feces) and the female rat (10.6% in urine; 91.3% in feces). After oral administration of [(14)C]celecoxib at doses of 20, 80, and 400 mg/kg, the majority of the radioactivity was excreted in the feces (88-94%) with the remainder of the dose excreted in the urine (7-10%). Both unchanged drug and the carboxylic acid metabolite of celecoxib were the major radioactive components excreted with the amount of celecoxib excreted in the feces increasing with dose. When administered orally, celecoxib was well distributed to the tissues examined with the highest concentrations of radioactivity found in the gastrointestinal tract. Maximal concentration of radioactivity was reached in most all tissues between 1 and 3 h postdose with the half-life paralleling that of plasma, with the exception of the gastrointestinal tract tissues.     

Distribution, metabolism and excretion of 14C-MT-141 in rats. II. Distribution and excretion after multiple intravenous administration in male rats and after single intravenous administration in female rats

The distribution and tissue accumulation of the radioactivity were studied in male rats after the multiple intravenous administration of 14C-MT-141. The distribution and the placental transfer were also studied using pregnant rats or lactating rats after the single intravenous administration of 14C-MT-141. The radioactive concentration in the fetus was low and the radioactivity was distributed almost uniformly through the fetus body. The peak time of the milk level was 2 hours after the administration and the radioactivity in milk decreased gradually thereafter. The milk levels decreased more slowly than the blood levels did. The blood level after the last dose administered daily for 7 days tended to decrease more slowly, when compared with the single administration. However the blood concentration at 48 hours after the last administration was less than 3 times as high as that after the single administration.