No abstract

Data on the gastrointestinal absorption of 12 elements have been reviewed. In each case, absorption is expressed as the fraction of the ingested element absorbed to blood, referred to as the f1 value, applying to intakes of unspecified chemical form by average population groups. The level of confidence in individual absorption values has been estimated in terms of lower and upper bounds, A and B, such that there is judged to be roughly a 90% probability that the true central value is no less than A and no greater than B. Ranges are proposed for intakes by adults, 10-year-old children and 3-month-old infants. Uncertainty in f1 values (B/A) ranged from 10% to factors of 100-400. The lowest uncertainties were for the well absorbed elements, H, I and Cs, for which there are good data, and the greatest uncertainties were for less well absorbed elements for which few data are available, particularly Zr and Sb. Ranges were generally wider for children and infants than for adults because of the need to allow for the likelihood of increased absorption with only limited data in support of the proposed values. The largest ranges were for 3-month-old infants, reflective lack of knowledge on the time-course and magnitude of possible increased absorption in the first few months of life. For each age group, ICRP values of absorption tend towards the upper bound of the ranges, indicating a degree of conservatism in th calculation of ingestion dose coefficients. Examination of the effect of the proposed confidence intervals for f1 values on uncertainties in dose coefficients for ingested radionuclides showed that there was no direct relationship. For some radionuclides, uncertainties in effective dose were small despite large uncertainties in f1 values while for others the uncertainties in effective doses approached the corresponding values for uncertainty in f1 values. These differences reflect the relative contributions to effective dose from cumulative activity in the contents of the alimentary tract, which in many cases is insensitive to uncertainties in f1, and cumulative activity of the absorbed radionuclide in systemic tissues, which is proportional to f1. In general, uncertainties in effective close for children and infants exceeded those in adults as a result of greater uncertainties in f1 values for the younger age groups. However, this effect was reduced in some cases by shorter retention times of absorbed nuclides in body tissues and organs.

No abstract

Decorporation therapy is the only known effective method of reducing the radiation dose to persons following accidental internal contamination with transportable radionuclides. Deposits of actinides in bone should be minimized because development of osteosarcoma appears to be related to internal exposure. In contrast with other actinides, such as plutonium or americium where chelating agent treatment is efficient, the therapeuric approaches used for cases of uranium contamination are widely ineffective. This is the first report on in vivo efficacy of a chelating agent, a siderophore analogue code named 3,4,3-LIHOPO, after systematic exposure to natural uranium in the rat. Using the classical antidotal therapy (sodium bicarbonate) for comparison, this ligand has been investigated for its ability to remove uranium from rats after intravenous or intramuscular injection as nitrate. Following an immediate single intramuscular or intravenous injection of 3,4,3-LIHOPO (30 mumol.kg-1) urinary excretion of uranium was greatly enhanced with a corresponding reduction 24 h later in kidney and bone uranium content (to about 20 and 50% of the control rat respectively). Under identical experimental conditions, sodium bicarbonate (640 mumol.kg-1) reduced the uranium content in kidney in kidney and bone only to about 90 and 70% of controls respectively, and there was less enhancement of uranium excretion. However, when treatment was delayed by 30 min and administered intraperitoneally, there was no marked difference in retention and excretion of uranium between the two compounds. As this ligand showed no apparent irreversible toxicity at effective dosages, it is concluded that the administration of the 3,4,3-LIHOPO chelating agent represents potentially a most significant advance for prompt treatment of uranium contamination, while a more detailed investigation is necessary on the possible advantage when treatment delayed.

This study was designed to compare the translocation from lung of the Pu contained in the pure and mixed industrial oxides PuO2 and (U,Pu)O2. The latter had a Pu content of 20% w/w. For this purpose, young adult male rats and male and female baboons were exposed to a single inhalation of these oxides. Two baboons were exposed to the reference PuO2, i.e. 239PuO2. Rats were killed under anaesthesia 1, 15, 30, 90 and 180 days after exposure, and baboons, also under anaesthesia, 1 year thereafter. The results indicate that lung retention of Pu was independent of the oxide inhaled, but was smaller in rat (12-15% of the initial pulmonary burden, 6 months after exposure) than in baboon (56-80% of this burden, 1 year after exposure). In rat, Pu translocation kinetics were similar for the two industrial oxides, but as from day 15 after inhalation until 6 months thereafter, measurement of Pu deposits in the liver and skeleton showed that translocation of Pu from the mixed oxide was 2-3 times greater than that from the industrial Pu oxide. In baboon, the largest amounts of Pu were retained in the lung and thoracic lymph nodes for the three oxides inhaled. Pu translocation to the liver, skeleton and kidneys, and also urinary Pu excretion, were greater after inhalation of the mixed oxide than after inhalation of the industrial and reference Pu oxides. Nevertheless, the amount of mixed oxide Pu translocated to these sites and excreted in urine remained under 3% of the initial pulmonary burden.