Kathleen F. Tillery

Disposition of decabromobiphenyl ether in rats dosed intravenously or by feeding

The disposition of 14C-labeled decabromobiphenyl ether (DBBE) in male Fischer rats dosed by feeding (0.025-5.0% of the diet) or intravenously (1 mg/kg) was determined. For rats dosed by feeding, intestinal absorption of DBBE was evident in that the intact compound was present in extracts of liver. For these rats, the size of the liver increased with increasing concentration of DBBE in the diet. Liver contained a maximum of 0.449% of the administered radioactivity at 24 h after feeding rats a diet containing 0.0277% [14C]DBBE; no other organ or tissue contained more than 0.26%. The total amount of radioactivity found in tissues was less than 1% of the dose. Of the radioactivity recovered in the feeding experiments, more than 99% was in the feces and gut contents at 72 h; a maximum of 0.012% of the dose was in the urine. In the feces of rats fed [14C]DBBE, there were three metabolites, which together comprised 1.5-27.9% of the radioactivity. Since absorption was minimal, most of the metabolism of [14C]DBBE apparently took place in the gastrointestinal tract. The metabolites increased in percent of total radioactivity with the content of DBBE in the diet, an indication that enzyme induction in intestinal bacteria may have occurred at the higher doses. More extensive metabolism of [14C]DBBE occurred after intravenous administration; only 37% of the radioactivity in the feces was unchanged DBBE. At 72 h after dosing, fecal excretion accounted for 70% of the dose; only 0.129% appeared in the urine. Muscle retained 12.9% and skin 7.25% of the radioactivity administered. In 4 h, rats with biliary cannulas excreted in the bile 7.17% of the intravenously administered radioactivity; less than 1% was excreted as intact DBBE. Biliary excretion was apparently the major route for elimination of the intravenously administered compound. The rapid excretion and extensive metabolism of DBBE, relative to other polyhalogenated compounds, are advantageous properties that may allow it to be used in place of structurally similar compounds presently employed in industrial applications.

Disposition of 2‐hydroxy‐4‐methoxybenzophenone in rats dosed orally, intravenously, or topically

Administration to rats of oral doses of [14C]-2-hydroxy-4-methoxybenzophenone (HMB) in the range of 3.01-2570 mg/kg revealed that a dose-dependent elimination process was operative at the highest dose. Urinary excretion (63.9-72.9% of the dose in 72 h) was the major route for elimination of radioactivity. An intravenous dose (4.63 mg/kg) distributed rapidly throughout the body of rats and appeared in the urine in an amount (67.4%) similar to those for the oral doses. Rats absorbed large portions of doses of [14C]HMB administered topically, either as an ethanolic solution (50, 200, or 800 micrograms/rat) or formulated in a lotion (50 micrograms/rat). For rats with biliary cannulas, 36.6% of the radioactivity of an intravenous dose (4.46 mg/kg) appeared in the bile in 4 h; the initial half-life for biliary elimination was 40 min. In the bile, at least five radioactive components, none of which was intact HMB, were present. The two major components were glucuronides of HMB and demethylated HMB, and a third was probably a sulfate ester of hydroxylated HMB. In urine, there were nine radioactive components, two of which were unchanged HMB and its glucuronide.

Disposition of 2-mercaptobenzothiazole and 2-mercaptobenzothiazole disulfide in rats dosed intravenously, orally, and topically and in guinea pigs dosed topically

To determine the metabolic disposition of [14C]-2-mercaptobenzothiazole (MBT) and [14C]-2-mercaptobenzothiazole disulfide (MBTS), male and female rats were dosed topically. Topical doses were 36.1 micrograms/animal for [14C]MBT and 33.6 micrograms/animal for [14C]MBTS. Although more MBT passed through the skin than MBTS and although, relative to rats, guinea pigs absorbed a greater percentage of the dose (33.4% compared to 16.1-17.5% of the MBT and 12.2% compared to 5.94-7.87% for MBTS), the disposition of radioactivity derived from the two compounds was similar. Washing of the skin removed more of the radioactivity from guinea pigs than from rats. For both sexes of rats dosed intravenously with [14C]MBT (0.602 mg/kg) or [14C]MBTS (0.571 mg/kg), disposition of the compounds was similar. In 72 h, 90.9-101% of the dose appeared in the urine and 3.79-15.1% in the feces. At this time, a small portion of the administered radioactivity (1.52-1.96% of the dose) remained associated with erythrocytes. Oral dosing of rats for 14 d with unlabeled MBT (0.510 mg/kg.d) prior to a single dose of [14C]MBT (0.503 mg/kg) or with unlabeled MBTS (0.521 mg/kg.d) prior to a single dose of [14C]MBTS (0.730 mg/kg). For both sexes, disposition of the compounds was similar. At 96 h after dosing, a small portion of the administered radioactivity (1.20-1.69% of the dose) remained associated with erythrocytes, most of which was bound to the membranes. For both compounds and sexes, 60.8-101% of the radioactivity administered appeared in the urine and 3.46-9.99% in the feces in 96 h. At the time, only trace amounts of radioactivity remained in tissues other than blood. Of these tissues, thyroid contained the highest concentration. In the urine, there was a detectable MBT or MBTS, but there were two metabolites, one of which was identified as a thioglucuronide derivative of MBT. The other was possibly a sulfonic acid derivative of MBT. In conclusion, there were similarities in absorption, distribution, and metabolism of [14C]MBT and [14C]MBTS in rats and in guinea pigs, indicating that [14C]MBTS was readily converted to [14C]MBT.

Disposition in mice of 7-hydroxystaurosporine, a protein kinase inhibitor with antitumor activity

UCN-01, a hydroxylated derivative of staurosporine, was selected for study because of its promising antitumor activity. For mice dosed intravenously, subcutaneously, or by oral gavage with this compound, the maximum tolerated doses (MTD) were 20, 10, and >100 mg/kg, respectively. UCN-01 was stable in mouse and dog plasma, but in human plasma it was converted to a metabolite in a process not inhibited by standard protease and esterase inhibitors. Following n intravenous dose of 10 mg/kg UCN-01, the half-lives for the initial (t1/2α) and terminal (t1/2β) exponential phases of elimination were 10 and 85 min, respectively; the area under the plasma concentration-time curve (AUC value) was 117 μg min ml−1. In mice dosed by oral gavage with 10 mg/kg, the calculated value for the half-life of the elimination phase was 150 min. The AUC value was 15 μg min ml−1, giving a value for bioavailability of 13%. After subcutaneous dosing with 10 mg/kg, the calculated values for half-lives for the distribution and elimination phases were 23 and 130 min, respectively; the AUC value was 113 μg min ml−1. Since this value is equivalent to that obtained for intravenous dosing, administration of UCN-01 by the subcutaneous route may be an alternative to intravenous dosing in preclinical and clinical trials.

Disposition of 2′, 3′-dideoxyadenosine and 2′, 3′-dideoxyinosine in mice

SummaryMice were dosed with [3H]2′,3′-dideoxyadenosine ([3H]ddA) in three procedures: intravenously, intraperitoneally, and interperitoneally following a dose of 2′ -deoxycoformycin (dCF). For mice dosed intravenously, the content of radioactivity in plasma and tissue samples were essentially constant after 30 min. Of the radioactivity in plasma and brain samples collected between 30 min and 24 hr, more than 94% was present as 3H2O, indicating that most of the tritium from [3H]ddA had exchanged with water. No intact ddA was detected, and the deamination product, 2′,3′ -dideoxyinosine (ddI), was present only transiently. In the urine, the major radioactive material was [3H]ddI. Also detected were 3H2O and small amounts of [3H]hypoxanthine and [3H]ddA. Following intraperitoneal doses to mice, levels of radioactivity in plasma, liver, and kidney increased to a maximum by 15–30 min after dosing but dropped to essentially constant levels thereafter, again indicating that the tritium had exchanged with water. At 5, 15, and 30 min after dosing, ddI was the major radioactive component in plasma. Only small amounts of ddA were present. When dCF was administered 24 hr prior to intraperitoneal [3H]ddA, levels of radioactivity in plasma, liver, and kidney reached a maximum at 30 to 60 min after dosing and decreased to essentially constant levels thereafter. The dCF transiently inhibited the deamination of ddA to ddI, since, in plasma, [3H]ddA was the main radioactive component at 5 and 15 min after dosing. Comparison of HPLC assays based on radioactivity detection and UV absorbance showed that they were equivalent for measuring ddA and ddI in samples derived from dosed mice. Therefore, exchange of tritium must have occurred at a metabolic step beyond ddI.For mice dosed intravenously and orally with unlabeled ddI, there was evidence of a saturated process. Nevertheless, for the high and low intravenous doses of ddI, the percent of dose excreted in the urine as unchanged drug was the same.

Disposition of 2‐mercaptobenzimidazole in rats dosed orally or intravenously

The disposition of [14C]-labeled 2-mercaptobenzimidazole (MBI) in male Fischer-344 rats dosed orally (49 or 0.5 mg/kg) or intravenously (0.5 mg/kg) was determined. Absorption of the oral dose was evident, since, in 72 h, most of the radioactivity administered by either route appeared in the urine. Smaller amounts appeared in the feces. In 4 h, 12% of the radioactivity from an intravenous dose of 0.5 mg/kg was excreted in the bile of rats with biliary cannulas. For rats dosed intravenously, the half-life for disappearance of unchanged MBI from plasma was 125 min. In contrast, the terminal half-life for loss of radioactivity from blood was 83 h. The concentration of total radioactivity was higher in liver and kidney tissue than in blood. One of the major urinary metabolites was identified as benzimidazole, and a minor component was tentatively identified as unchanged MBI. Neither of these could be detected in bile.

Disposition of 2‐(2‐quinolyl)‐1,3‐indandione (d. c. yellow #11) in rats dosed orally or intravenously

The disposition of 2-(2-quinolyl)-1,3-indandione (D. C. yellow #11, DCY) in male Fischer rats dosed intravenously or by feeding was determined. For rats given [14C]DCY in the feed (0.00044-0.41% of the diet), recovery of radioactivity during the 24-h dosing period and the 72-h period thereafter ranged from 89.1 to 93.9% for feces and from 4.98 to 6.25 for urine. Tissues contained only trace amounts. Following intravenous dosing with [14C]DCY (0.93 mg/kg), radioactivity distributed readily into most tissues; maximum amounts were present at 5 min, the earliest time of assay. Maximum amounts of radioactivity in fat, skin, and gut tissue, however, were present at 30 min after dosing. These three tissues also had relatively long alpha phases for the elimination of radioactivity. In 24 h after intravenous dosing, rats excreted 81.1% of the dose in the feces and 16.0% of the dose in the urine. For rats fitted with biliary cannulas, 54.5% of the dose, all of which was metabolites of [14C]DCY, was recovered in the bile in 4 h. Associated with the rapid and extensive biliary excretion of metabolites of intravenously administered [14C]DCY was the appearance of large amounts of radioactivity in the feces and also, at intermediate time points, in the liver, gut contents, and gut tissue. In conclusion, rats rapidly distribute, metabolize, and excrete [14C]DCY.

Disposition of 9-aminoacridine in rats dosed orally or intravenously and in monkeys dosed topically.

Following administration of [14C]-labeled 9-aminoacridine ([14C]9AA) hydrochloride either orally or intravenously to rats, the excretion of radioactivity was similar, with 20-26% of the dose appearing in the urine and 57-68% in the feces. The pattern of tissue distribution was also similar for the two routes. This information suggests that absorption of the oral doses was extensive and that, for both routes of administration, biliary excretion accounted for most of the radioactivity in the feces. Biliary excretion of radioactivity derived from [14C]9AA was confirmed in an experiment involving rats with inserted biliary cannulas. For these rats, 49.5% of the dose administered appeared in the bile in 4 h. The major urinary and biliary metabolite of [14C]9AA of rats was identified as an O-beta-glucuronide of hydroxylated 9AA. Absorption of 9AA through the skin could not be conclusively demonstrated. For monkeys dosed topically with [14C]9AA, only small amounts of radioactivity (a total of less than 0.8% of the dose) appeared in the urine and various tissues in 24 h.

Investigations on the basis for the differential toxicity of hexachlorocyclopentadiene administered to rats by various routes

The differential disposition of hexachlorocyclopentadiene (HCCP) following oral administration, as contrasted to inhalation or intravenous administration, may account for its lower toxicity by this route. Following an intravenous dose of [14C]HCCP to rats at 0.59 mg/kg, 39.0% of the radioactivity remained in the tissues at 72 h; after inhalation of vapors of [14C]HCCP (1.3-1.8 mg/kg), this amount was 11.5%. After oral doses of 4.1 or 61 mg/kg, however, the amount was only 2.4%. No detectable amount of intact HCCP was present in the lungs or kidneys of rats exposed to the chemical by inhalation, and only about 1% was converted to CO2, regardless of the route of administration. The chemical reactivity of HCCP with biological materials was evident in in vitro experiments, in which HCCP became bound to components of whole blood, plasma, liver homogenates, fecal homogenates, and intestinal contents. Thus, the lower toxicity of oral doses of HCCP may be related to its reaction with intestinal contents and its lack of absorption into tissues, in substantial amounts, as the intact, reactive form.