G.N. Stradling

Decorporation of actinides: a review of recent research

This paper reports progress on some of the research priorities identified in the Guidebook for the Treatment of Accidental Contamination of Workers published in 1992. It concludes: that the oral administration of DTPA could be an effective procedure for plutonium (Pu) and americium (Am) inhaled as nitrates; that 3,4,3-LI (1,2-HOPO) is the most effective siderophore analogue yet tested for the decorporation of these actinides, and thorium (Th); and that for thorium the efficacy of treatment will be strongly dependent on the radionuclide, and hence mass, likely to be incorporated under different exposure scenarios. No effective treatment regimens appear to be available for neptunium (Np) and uranium (U).

Factors affecting the mobility of plutonium-238 dioxide in the rat.

A major factor influencing the movement of plutonium-238 from the lungs to blood after the intubation of oxide suspensions is the presense of 0.001 micrometer diameter particles. In a polydisperse suspension of particles this fraction increases with time, due it is thought, to fragmentation of larger particles induced by alpha decay. The rate of this process could account for the greater transportability in vivo of plutonium-238 relative to plutonium-239 when the oxides are inhaled. In blood, 0.001 micrometer diameter plutonium-238 oxide particles undergo a rapid reaction to form a low molecular weight species before plutonium is complexed with transferrin and citrate ions. The filtration of this species through the kidneys may explain the observed enhanced urinary excretion of plutonium relative to administered plutonium citrate. The mechanism of urinary excretion and relationship between cumulative urinary excretion and body content for plutonium-238 is similar to that previously observed for plutonium-239, even though different methods of preparation of the oxides were used.

The Efficacies of 3,4,3-LIHOPO and DTPA for Enhancing the Excretion of Plutonium and Americium from the Rat: Comparison with Other Siderophore Analogues

With DTPA as a comparison, the siderophore analogue code named 3,4,3-LIHOPO has been tested for its ability to remove 238Pu and 241Am from rats after their inhalation or intravenous injection as nitrate. The most effective treatment regimen for inhaled Pu was the repeated administration of 30 mumol kg-1 3,4,3-LIHOPO. By 7 days after exposure, the Pu contents of the lungs and total body were reduced respectively to 2 and 4% of those in untreated animals. These values were six and three times less than when DTPA was administered using the same protocol. For inhaled Am, 3,4,3-LIHOPO and DTPA were considered equally effective, the lung and total body contents being reduced respectively to 13 and 10% of those in controls. Some animals showed slight degenerative changes in the liver and proximal tubules of the kidneys after the repeated administration of 30 mumol kg-1 of 3,4,3-LIHOPO; however these changes were less marked than after DTPA treatment. After the intravenous injection of Pu, the most effective regimen was the single administration of 3 mumol kg-1 3,4,3-LIHOPO. The body content at 7 days was reduced to 7% controls compared with 19% after the repeated administration of 30 mumol kg-1 DTPA. At a dosage of 30 mumol kg-1, 3,4,3-LIHOPO was less effective owing to the higher retention of Pu in the liver. With repeated dosages of 30 mumol kg-1 3,4,3-LIHOPO was more effective than DTPA for the decorporation of Am; the body contents were 16 and 31% of those in controls respectively. Importantly, the body content was still reduced to 28% of control after a single administration of 3 mumol kg-1. The ligand 3,4,3-LIHOPO, which is also superior to other siderophore analogues, could represent a most significant development in the decorporation of Pu and Am.

Use of DTPA for Increasing the Rate of Elimination of Plutonium-238 and Americium-241 from Rodents after their Inhalation as the Nitrates

This study has shown that: 1 both inhaled (2 μmol/kg) and injected (30 μmol/kg) diethylenetriaminepentaacetic acid (DTPA) can reduce the lung deposit of 238Pu and 241 Am inhaled as nitrate to about 1% of that in untreated controls; 2 injection of DTPA is more effective than aerosolized DTPA for reducing deposits of 238 Pu and 241Am in the liver and skelton; 3 combined treatment involving early inhalation of DTPA followed by repeated intravenous injections is likely to be the most effective treatment for workers who have accidentally inhaled plutonium and americium nitrates.

The Efficacy of DFO-HOPO, DTPA-DX and DTPA for Enhancing the Excretion of Plutonium and Americium from the Rat

A hydroxypridinone derivative of desferrioxamine (Na-DFO-HOPO), a dihydroxamic derivative of diethylenetriaminepenta-acetic acid (ZnNa-DTPA-DX), and DTPA (CaNa3- and ZnNa3-DTPA) were tested at dosages of 30 mumol kg-1 for their ability to remove 238Pu or 241Am from rats after their intravenous injection as citrate or inhalation as nitrate. The most effective treatment regimen for injected Pu was the repeated administration of DFO-HOPO; by 7 days the body content was reduced to 8% of that in untreated animals. Repeated dosages of 3 mumol kg-1 DFO-HOPO were as effective as those of 30 mumol kg-1 DTPA. After inhalation of Pu nitrate, repeated treatment with DTPA, DTPA-DX or DFO-HOPO reduced the body content by 7 days to, respectively, 10, 15 and 31% of those in untreated animals. After inhalation of Am, DTPA-DX and DTPA were equally effective, the body contents being reduced to 7% of control values with repeated treatment. Injection of DFO-HOPO was ineffective for enhancing the elimination of inhaled or injected Am. The results confirm the strategy of examining the use of siderophore analogues for the decorporation of Pu or Am. However, at present DTPA should remain the agent of choice, particularly after inhalation.

Efficacy of Tiron for Enhancing the Excretion of Uranium from the Rat

Tiron (sodium 4, 5-dihydroxybenzene-1,3-disulphonate) has been suggested as a possible antidote for acute uranium poisoning. In this study, the compound has been administered intraperitoneally to rats in dosages of 30, 300 or 1000 μmol kg-1 at 20, 60 and 180 min after the intratracheal instillation of uranyl nitrate. The amounts of uranium deposited in the lungs of rats were equivalent to intakes by workers of about 12 times the permitted daily limit of 2.5 mg. The average body content of uranium at 5 d after exposure were, respectively, about 100%, 78% and 65% of those in untreated animals. It is concluded that the administration of Tiron is of limited practical value for treatment of uranium exposures not greatly in excess of the permitted intake.

The Efficacies of Pure LICAM(C) and DTPA on the Retention of Plutonium-238 and Americium-241 in Rats after Their Inhalation as Nitrate and Intravenous Injection as Citrate

The pure carboxylated catechoyl amide LICAM(C) and the calcium and zinc salts of diethylenetriaminepenta-acetic acid (DTPA), were tested for efficacy for removing 238Pu and 241Am from rats after inhalation of the nitrate or intravenous injection of the citrate. The results were compared with the efficacy of methylated LICAM(C) used in previous experiments. It was shown that: (1) after inhalation of 238Pu nitrate, DTPA was far superior to pure LICAM(C); (2) after intravenous injection of 238Pu citrate, the infusion of DTPA plus LICAM(C) was only marginally more effective than DTPA alone; and (3) after inhalation or intravenous injection of 238Pu plus 241Am, the efficacy of pure LICAM(C) was only marginally more effective than the methylated form and neither form was effective for the decorporation of 241Am. It was concluded that DTPA, at present, remains the chelating agent of choice for treating persons accidentally contaminated with transportable forms of Pu and Am.

The reactions of 1.0 nanometre diameter plutonium-238 dioxide particles with rat lung fluid.

The reactions of 1.0 nm particles of plutonium-238 dioxide with rat lung fluid have been studied both in vivo and in vitro. In both cases two products have been identified, (i) plutonium-labelled pulmonary surfactant and (ii) a heterogeneous plutonium-labelled material isolated by column chromatography. The formation of plutonium-labelled pulmonary surfactant results in the rapid translocation of plutonium from lungs to blood and in a high urinary excretion relative to administered plutonium citrate.

Removal of Inhaled Plutonium and Americium from the Rat by Administration Of ZnDTPA in Drinking Water

This study has examined the efficacy of ZnDTPA administered in drinking water for removing 238Pu and 241Am from the rat after their simultaneous inhalation as nitrates; the dosage used was 95 μmol kg-1d-1. The continuous administration of ZnDTPA over a 14 d interval, commencing 1 h after exposure, reduced the lung and total body contents of 238 Pu to, respectively, 11 % and 18% of those in untreated rats; the corresponding values for 241Am were 11 % and 14%. After the continuous administration of 95 μmol kg-1 from 4 d to 28 d post exposure, the lung and total body contents of 238Pu were, respectively, 5% and 16% of those in controls; the corresponding values for 241Am were 7% and 19%. Further reductions in the actinide contents of body tissues were found when treatment was extended to 52 d or 76 d. These regimens were as effective as twice weekly injections of 30 μmol kg-1 ZnDTPA commencing at 4 d. After the continuous administration of 95 μmol kg -1 d-1 for 72 d, some pathological changes to the gastrointestinal tract were observed but these were considered to be reparable. It was concluded that further work is required to evaluate the toxicity of the ligand and to establish the optimal treatment regimen.

The metabolism of ceramic and non-ceramic forms of uranium dioxide after deposition in the rat lung

Ceramic and non-ceramic forms of uranium dixoide, produced industrially, were administered to rats either by inhalation or as an aqueous suspension which was injected directly into the pulmonary region of the lungs. The results showed that: 1 both materials should be assigned to inhalation class Y as defined by the International Commission on Radiological Protection; 2 whilst the translocation of uranium to the blood for the non-ceramic UO2 was about twice that obtained for the ceramic form, the two dioxides were unlikely to be differentiated on the basis of their lung retention kinetics; 3 the distribution of uranium amongst body tissues and the relationship between systemic content and cumulative urinary excretion indicated that it was transported in the hexavalent form; 4 in addition to air sampling procedures, lung radioactivity counting measurements could be used to advantage for assessing occupational exposures; 5 the exposure limits should be based on radiation dose rather than chemical toxicity.