Natural and man–made radionuclide concentrations in lichens at several locations in Austria

Regions of elevated natural radioactivity (Gastein–valley, Waldviertel) were compared to regions of low natural radioactivity (surroundings of Salzburg City). The natural radionuclides 238U, 40K and 7Be and the man–made nuclides 137Cs, 144Ce, 95Ze95Nb were measured by gamma ray spectrometry. No statistically significant difference was found between samples of the Gastein–valley, Waldviertel, Salzburg, Grossarl and Dachstein concerning the content of natural radionuclides. The amount of the short–lived fission products 144Ce, 95Zr–95Nb as well as of the natural 7Be increased with altitude. The specific nuclide concentration varies with species but was almost independent of growth form and substrate.     

Effect of mixed ligand complex therapy on the retention of 95Nb and 144Ce in mice

We have examined in mice the effects of mixed ligand treatments with desferrioxamine B (DFOA), Na3Ca-diethylenetriamine pentaacetic acid (DTPA), and DL-penicillamine (PA) on the retention of a mixture of 95Nb and 144Ce. The results show that 95Nb + 144Ce could be mobilized effectively by simultaneous application of specific agents (i.e., DFOA, DTPA) with no decrease in their efficiencies.     

Fission-product radionuclides in sediments from the north-east irish sea

Summary 1. Gamma radiation dose-rates over mud-flat areas are shown to be at least ten times those measured over sandy beaches.2. Analysis of the surface sediment layer in an estuarine area 6 miles from the Windscale effluent pipeline shows the major gamma-emitting radionuclides to be⁹⁵Zr,⁹⁵Nb and¹⁰⁶Rh.3. Core sampling has indicated that the radioactivity concentration in silt decreases exponentially with depth from the surface layer.4. It is shown that the gamma dose-rate above silt banks is largely accounted for by the concentration of⁹⁵Zr/⁹⁵Nb in the surface silt layer. The residual gamma dose is probably accounted for by¹⁰⁶Ru/¹⁰⁶Rh distributed beneath the surface layer.5. The accumulation factors of⁹⁵Zr +⁹⁵Nb and¹⁰⁶Ru in the surface silt layer are approximately 1.5×10⁴.6. The relationship of radioactivity concentration in surface silt to distance from the effluent pipeline can be described by a simple power function of distance.

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Spaltprodukt-Radionuklide in Sedimenten der nordöstlichen Irischen See

Kurzfassung Als Teil einer Untersuchung über die Verbreitung von radioaktivem Abwasser, das von der radiochemischen Aufarbeitungsanlage in Windscale stammt, wurden Messungen der Gamma-Dosisleistung auf Schlickböden in Ästuaren vorgenommen. Es zeigte sich, daß die Dosisleistungen hier mindestens um eine Größenordnung höher sind als die, welche auf reinem Sandboden gemessen wurden. Oberflächensedimente, die hinsichtlich ihrer Radioaktivität untersucht wurden, enthalten als wichtigste Radionuklide die Spaltprodukte⁹⁵Zr +⁹⁵Nb,¹⁰⁶Ru,¹⁴⁴Ce und¹³⁷Cs. Die Konzentrationen der einzelnen Radionuklide stehen in Beziehung zur Abwassermenge. Probebohrungen in Sedimenten zeigten, daß sich die Konzentration der Radioaktivität exponentiell mit der Tiefe ändert. Der Anreicherungsfaktor von⁹⁵Zr +⁹⁵Nb,¹⁰⁶Ru in Oberflächensedimenten von Ästuaren beträgt ungefähr 1,5 × 10⁴, für¹³⁷Cs dagegen 1,0 × 10³. Die Konzentrationen von⁹⁵Zr +⁹⁵Nb,¹⁰⁶Ru und¹⁴⁴Ce in Oberflächensedimenten sind abhängig vom Abstand der Abwassereinleitung bei Windscale.

     

Influence of radiation dose patterns on lung tumor incidence in dogs that inhaled beta emitters: a preliminary report

Different radiation dose patterns to the lung from inhaled beta-emitting radionuclides may influence the frequency and kind of biological effects. To determine the magnitude of this influence, groups of Beagle dogs were exposed to aerosols of 90Y, 91Y, 144Ce, or 90Sr in relatively insoluble particles and observed for their life spans. Different dose patterns were achieved by using these radionuclides having similar beta emissions and chemical form but having physical half-lives ranging from 2.6 days to 28 years. The range of initial lung burdens of radionuclides studied resulted in a range of biological effects from early deaths at the highest radiation doses to no discernible effects at the lowest doses. The effective half-lives of the four radionuclides in the lung ranged from 2.5 to 600 days. Within 1.5 years after exposure, some dogs died with radiation pneumonitis and pulmonary fibrosis. Between 1.5 and 10 years after exposure, 42 pulmonary carcinomas and 28 pulmonary sarcomas were observed in 163 dogs that died. Protracted irradiation of the lung from 90Sr or 144Ce resulted in a relatively high radiation dose and produced more total lung tumors but fewer lung tumors per rad than less protracted irradiation from 90Y or 91Y. At 10 years after inhalation exposure, the difference in risk per rad among the different dose patterns was a factor of 4 to 8, indicating that the different radiation dose patterns from inhaled beta emitters do influence lung tumor risk factors, at least at high (greater than 20,000 rad) doses to lung.     

Radioactive contamination of bottom sediments in the upper reaches of the Techa river: analysis of the data obtained in 1950 and 1951

A stationary sorption model has been developed for re-evaluating and analysing archive data from 1950-1951 on the radioactive contamination of Techa river bottom sediments close to the site of liquid radioactive waste discharge. In general, good agreement was obtained between calculations and measurements, which substantiates further the assumptions and conclusions in two preceding articles, on the radionuclide composition of discharged liquid radioactive waste. Estimates on the effective liquid radioactive waste discharges given here are significantly different from those deduced in the 1950s, i.e. in summer 1950 and October 1951. The results are discussed in relation to the Techa River Dosimetry System 2000 (TRDS-2000) that has recently been presented to serve as a means for estimating doses to the Techa river residents. Parameter values describing the exponential decrease of bottom sediment contamination along the river due to short-lived radionuclides, such as (106)Ru, and (144)Ce, agree reasonably with those used in TRDS-2000. However, for other radionuclides, such as (95)Zr, (95)Nb, (91)Y, (90)Sr and (137)Cs, substantial differences are found. It is demonstrated that water flow rate, width of the river, and surface area of bottom sediments are important parameters which were not adequately taken into account in TRDS-2000. Also, the stirring-up of contaminated bottom sediments and their subsequent transport by the water flow are seen to be an important mechanism that governs the radionuclide transport downstream. This mechanism was not included in the TRDS-2000 model. It is concluded that the sorption model used in TRDS-2000 for the reconstruction of radioactive contamination of water and bottom sediments of the Techa river in 1949-1951, is subject to considerable errors. While the present paper is focussed on details of the dosimetric modelling, the implications for the Techa river dosimetry are major. They will be further elucidated in a forthcoming paper.     

Repeated inhalation exposure of rats to aerosols of 144CeO2. I. Lung, liver, and skeletal dosimetry.

To develop a better understanding of the influence of cumulative radiation dose and dose rate to the lungs on the biological responses to inhaled radionuclides, several studies are in progress at this institute in which laboratory animals have been exposed once or repeatedly to aerosols of insoluble particles containing 144Ce or 239Pu. In the study reported here, F344 rats were exposed repeatedly to aerosols of 144CeO2 beginning at 94 days of age to reestablish desired lung burdens of 1.9, 9.2, 46, or 230 kBq of 144Ce every 60 days for 1 year (seven exposures). Other 94-day-old rats were exposed once to achieve similar desired initial lung burdens of 144Ce. Older rats were exposed once to achieve desired initial lung burdens of 46 or 230 kBq when 500 days of age, the age of the repeatedly exposed rats when exposed for the last time. Control rats were either unexposed, sham-exposed once or repeatedly, or exposed once or repeatedly to stable CeO2. Approximately equal numbers of male and female rats were used. The cumulative beta-radiation doses to the lungs, liver, and skeleton of rats exposed repeatedly were similar to those of rats with similar total lung burdens of 144Ce from a single inhalation exposure. The average beta-radiation dose rate to the lungs of the rats exposed repeatedly was about one-fifth of that in rats with similar total lung burdens after a single exposure.     

Lung lavage therapy to lessen the biological effects of inhaled 144Ce in dogs

To evaluate the therapeutic effects of removal of an internally deposited radionuclide on long-term biological effects, lung lavage was used to treat dogs that had inhaled 144Ce in a relatively insoluble form, in fused aluminosilicate particles. Either 10 lung lavages were performed between Days 2 and 56 after exposure or 20 lung lavages were performed between Days 2 and 84 after exposure. Approximately one-half of the 144Ce was removed by the lavages, resulting in a corresponding reduction in the total absorbed beta dose to lung. The mean survival time of the treated dogs was 1270 days compared to 370 days for untreated dogs whose initial pulmonary burdens of 144Ce were similar. Treated dogs died late from cancers of the lung or liver, whereas the untreated dogs died at much earlier times from radiation pneumonitis. Dogs treated with lung lavage but not exposed to 144Ce had a mean survival of 4770 days. We concluded that removal of 144Ce from the lung by lavage resulted in increased survival time and in a change in the biological effects from inhaled 144Ce from early-occurring inflammatory disease to late-occurring effects, principally cancer. In addition, the biological effects occurring in the treated dogs could be better predicted from the total absorbed beta dose in the lung and the dose rate after treatment rather than from the original dose rate to the lung. Therefore, we concluded that prompt treatment to remove radioactive materials could be of significant benefit to persons accidentally exposed to high levels of airborne, relatively insoluble, radioactive particles.     

Radionuclides in siberian Thymallus from radiation-contaminated area in the middle stream of the Yenisei River

Concentration of artificial radionuclides in bodies of arctic grayling from the radioactively contaminated zone of the Yenisei River in the vicinity of the Mining-and-Chemical Combine of Rosatom was investigated in 2007-2010. Gamma-spectrometric analysis revealed artificial radionuclides in all the organs and tissues of fish. The isotope composition was the most diverse (60Co, 65Zn, 85Sr, 99Mo, 106Ru, 137Cs, 144Ce) in internal organs of grayling. The activity of radionuclides increased in internal organs including liver and kidney and in the content of digestive tract of grayling during winter and spring, which coincided with the change in the feeding spectrum of grayling. The trophic transfer factor of radionuclides from zoobenthos (Philolimnogammarus spp.) to whole bodies and muscles of grayling was over 1 (1.8-2.4) only for natural radionuclide 40K. The trophic transfer of artificial radionuclides (60Co, 65Zn, 137Cs) to muscles and bodies of grayling was one-two orders of magnitude less effective.     

Dose assessment for the Metlino and Muslyumovo populations who lived along the Techa river from 1949 to 1954

In the period from 1949 to 1956, liquid radioactive waste was routinely and accidentally discharged by the Mayak Production Association, Southern Urals, Russia, into the Techa river. Based on a novel approach, the contamination of the Techa river water, the bottom sediments and the adjacent flood plains was modelled, and internal and external doses were estimated for two villages located downstream of the site of liquid radioactive waste release. Altogether, 11 radionuclides that occurred in the liquid radioactive waste were included in the calculations. The results suggest significantly higher doses than previously assumed, with the major contribution in the year 1951. Radionuclides with half-lives of less than 1 year, such as ⁸⁹Sr, ¹³¹I, ⁹⁵Zr+⁹⁵Nb, ¹⁰³Ru+^103mRh, ¹⁴⁰Ba+¹⁴⁰La, and ¹⁴⁴Ce+¹⁴⁴Pr, represent the major sources and, in contrast, long-lived radionuclides, such as ⁹⁰Sr and ¹³⁷Cs that have so far been assumed to be most important, did not dominate the doses. For adults from the village Metlino, located 7 km downstream of the site of liquid radioactive waste discharge, the committed effective doses due to intake of radionuclides were calculated to be about 2.3 Sv, while the external doses were between about 1.2 Sv and 6.9 Sv. On the other hand, for adults from Muslyumovo, located 75 km downstream, the commited effective doses due to intake of radionuclides were calculated to be about 0.5 Sv, while the external doses were between 0.5 Sv and 2.0 Sv. The values for the skin doses to the Metlino and Muslyumovo populations were about 7.1 Sv and 1.3 Sv, respectively. It is concluded that the current dose estimates for the residents of the Techa river need, therefore, reevaluation.     

Gut retention of metals in rats

In sucklings, a high fraction of orally administered metals and radionuclides is retained in the gut. The location of elements in the gut is of interest because of their potential local health effect. The purpose of this work was to evaluate the influence of chelation therapy on gut retention and location of cadmium, mercury, and cerium in-suckling rats. Radionuclides^115mCd,²⁰³Hg, and¹⁴¹Ce were administered orally to 6-d-old rats. Chelating agent Zn-DTPA (3.64 mmol/kg) was administered to animals that received^115m Cd or¹⁴¹Ce and Na-DMPS (375 μmol/kg) to those that received²⁰³Hg, immediately and 24 h or 24 and 48 h after radionuclide administration. Radio-activity was determined in the whole body and gastrointestinal tract 6 d later. Both early and delayed chelation treatment very effectively reduced whole body retention, and this was mainly owing to reduced gut retention. Although chelation therapy reduced gut retention of administered radionuclides 3–30 times, the site of metal accumulation and retention in the intestine remained unchanged. For all 3 radionuclides, both after early and delayed therapy, the site of metal accumulation was always the lower part of small intestine—ileum.     

The distribution in mice of intravenously administered labelled Candida albicans.

The time dependence of the distribution of intravenously injected radiolabelled Candida albicans in the body of mice was studied. The Candida cells were labelled by cultivating them 7 days at 28 degrees C in a medium containing one of the following radionuclides: 46Sc, 95Nb, 59Fe, 144ce, 89Sr, 60Co, 65Zn, 54Mn, 45Ca, 51Cr and 91Y, which are listed in decreasing order in respect to amount bound. The labelled cells were killed by heating them 120 min at 60 degrees C, without loss of immunologic properties. Owing to the amount and strength of binding, 144Ce labelled Candida, together with 14C labelled cells was used in animal kinetic study. A rapid disappearance of the labelled cells from blood, interrupted by a small peak, was paralleled by a transient uptake in lungs and followed by a long lasting accumulation in the liver. The kidneys and spleen revealed only small uptakes of the labelled material.     

Radionuclide transfer to marine biota species: review of Russian language studies

An extensive programme of experiments on transfer of radionuclides to aquatic species was conducted in the former USSR starting from the early 1950s. Only a few of these studies were made available in the English language literature or taken into account in international reviews of radionuclide behaviour in marine ecosystems. Therefore, an overview of original information on radionuclide transfer to marine biota species available from Russian language literature sources is presented here. The concentration ratio (CR) values for many radionuclides and for marine species such as: ²³⁹Pu, ¹⁰⁶Ru and ⁹⁵Zr (crustacean), ⁵⁴Mn, ⁹⁰Sr, ⁹⁵Nb, ¹⁰⁶Ru, ¹³⁷Cs ²³⁹Pu, ²⁴¹Am and natural U (molluscs), and ⁵⁴Mn, ⁹⁰Sr, ¹³⁷Cs and ¹⁴⁴Ce (fish) are in good agreement with those previously published, whilst for some of them, in particular, for ³²P and ¹¹⁰Ag (crustaceans), ³⁵S (molluscs), ³²P, ³⁵S, ⁹⁵Nb, and ¹⁰⁶Ru (macroalgae) and ⁶⁰Co and ^239,240Pu (fish) the data presented here suggest that changes in the default CR reference values presented in recent marine reviews may be required. The data presented here are intended to supplement substantially the CR values being collated within the handbook on Wildlife Transfer Coefficients, coordinated under the IAEA EMRAS II programme.     

Effect of Pseudomonas contamination or antibiotic decontamination of the GI tract on acute radiation lethality after neutron or gamma irradiation

The influence of antibiotic decontamination of Pseudomonas contamination of the GI tract prior to whole-body neutron or gamma irradiation was studied. It was observed that for fission neutron doses greater than 5.5 Gy, cyclotron-produced neutron doses greater than 6.7 Gy, and 137Cs gamma-ray doses greater than 14.4 Gy, the median survival time of untreated rats was relatively constant at 4.2 to 4.5 days, indicating death was due to intestinal injury. Within the dose range of 3.5 to 5.5 Gy of fission neutrons, 4.9 to 6.7 Gy of cyclotron-produced neutrons, and 9.6 to 14.4 Gy of gamma rays, median survival time of these animals was inversely related to dose and varied from 12 to 4.6 days. This change in survival time with dose reflects a transition in the mechanisms of acute radiation death from pure hematopoietic, to a combination of intestinal and hematopoietic, to pure intestinal death. Decontamination of the GI tract with antibiotics prior to irradiation increased median survival time 1 to 5 days in this transitional dose range. Contamination of the intestinal flora with Pseudomonas aeruginosa prior to irradiation reduced median survival time 1 to 5 days in the same radiation dose range. Pseudomonas-contaminated animals irradiated within this transitional dose range had maximum concentrations of total bacteria and Pseudomonas in their livers at the time of death. However, liver bacteria concentration was usually higher in gamma-irradiated animals, due to a smaller contribution of hematopoietic injury in neutron-irradiated animals. The effects of both decontamination of the GI tract and Pseudomonas contamination of the GI tract were negligible in the range of doses in which median survival time was dose independent, i.e., in the pure "intestinal death" dose range. Finally, despite the marked changes in survival time produced by decontamination or Pseudomonas contamination in the "transitional dose range," these treatments had little effect on ultimate survival after irradiation as measured by the LD50/5 day and the LD50/30 day end points. The implications of these results with respect to treatment of acute radiation injury after whole-body irradiation are discussed.     

Gastrointestinal stability and absorption of insulin in suckling pigs

Stability and absorption of orally administered fluorescein-isothiocyanate labeled insulin (FITC-insulin) in the gastrointestinal (GI) tract were investigated in newborn and 3-day-old pigs. The uptake of FITC-insulin by the intestinal epithelial cells was visualized using confocal laser scanning microscopy. Following oral administration, 3 h later 56 and 88% of orally administered fluorescence was found in the GI tract in newborn and 3-day-old piglets, respectively. Chromatographic analysis revealed that 15-37% of fluorescence recovered from the gastric and proximal intestinal contents was eluted in the void volume of a Sephadex G-25 column. It was also observed that oral administration of FITC-insulin at a dose of 100 nmol/kg body weight led to a significant decrease in blood glucose in newborn pigs (P<0. 05) but not in 3-day-old pigs. Microscopic examination showed that FITC-insulin was taken up via the vesicular transport mechanism throughout the whole small intestine but the ileum appeared to be a preferred site for FITC-insulin transport in newborn pigs. In 3-day-old pigs, the uptake of FITC-insulin occurred only in the distal part of the small intestine. These findings suggest that milk-borne insulin may partially survive in the GI lumen and subsequently act on the gastrointestinal tract in suckling piglets, while GI absorption of milk-borne insulin is limited to newborn pigs.     

Measurement of resuspended aerosol in the Chernobyl area

Size distribution measurements of particulate radionuclides were performed at two sites in the Chernobyl 30-km exclusion zone using several cascade impactors. The results obtained in the period September 1986 till June 1993 were discussed with regard to the general assumption of a log-normal activity size distribution in inhalation dose assessment. At Zapolie (a site 14 km from the Chernobyl reactor) a bimodal distribution was observed in 91% of all measured distributions. In most cases the medians were about 4 µm and in the range 20–30 µm. According to soil granulometric data this finding was explained by superimposing two processes: local resuspension and advective transport of radioactive aerosol from highly contaminated territories. The mean air concentration showed an increasing proportion of inhalable particles over the years since the accident. In 1993 the inhalable fraction was about 48% of the total concentration. At Pripyat, a site situated within a highly contaminated area, unimodal types of size distributions were predominant with the median diameters in the range 5–10 µm for ¹³⁷Cs. For the three nuclides ¹³⁷Cs, ¹⁴⁴Ce and ¹⁰⁶Ru, very similar types of distribution were observed. Apparently, the radioactive aerosol was of fuel origin. During a forest fire at a distance of 17 km, the majority of the radioactivity was associated with submicrometer particles with median diameters in the range 0.28–0.50 µm.     

Biosorption of radionuclides by Rhizopus arrhizus

The sorption of various radionuclides viz. 233U, 239Pu, 241Am, 144Ce, 147Pm, 152+154Eu and 95Zr from aqueous nitrate medium has been studied using biomass Rhizopus arrhizus. The biosorption of 233U and 239Pu was found to be maximum at pH 6-7 whereas for other trivalent actinides and fission products viz. 241Am, 144Ce, 147Pm, 152+154Eu and tetravalent 95Zr, it was more effective at pH 2. This biomass is a promising sorbant for the treatment of radioactive effluents from nuclear industry. © Rapid Science Ltd. 1998     

Modification of 144Ce tissue deposition by mixed ligand complex treatment in mice

The individual effect of desferrioxamine-B (DFOA), Na3Ca-diethylene-triaminepentaacetic acid (DTPA), DL-penicillamine (PA) and Na-salicylate (SA) has been examined as well as the effect of mixed-ligand treatment on the retention and elimination of 144Ce in mice. It was found that 144Ce could easily be mobilized by a single dose of DTPA. Mixed-ligand (MLCs) treatment did not change the deposition characteristics and translocation kinetics of 144Ce.     

Internal radiotherapy of painful bone metastases

Internal radiotherapy is effective in the treatment of metastatic bone pain and can improve quality of life. A number of controlled studies using various agents have shown a mean response rate in pain relief of 70–80% of treated patients. Some investigators prefer radionuclides which emit low beta particles for the treatment of bone pain, because the assumption of lower bone marrow toxicity of this agents. However, neither dosimetric data for radiation absorbed dose to the bone marrow nor clinical blood count depression have shown any significant differences between these agents. Other researchers suggest enhanced antitumoral effects using high-energy beta emitters and propose aggressive first-line treatment in the early disease stage instead of using these radiopharmaceuticals only in end-stage patients suffering intractable bone pain. Another approach consists of including other treatment modalities such as autologous stem cell rescue or in combination with chemo or bisphosphonate therapy to a radionuclide treatment scheme. Future research should focus more on the curative effects of combination with radiosensitizer, for example, chemotherapy, or repeated treatments with bone seeking agents.     

Estimation of rate constant for dissolution of radioactive fuel particles

Some theoretical of the experimental investigation of solubility of radioactive aerosols were examined. Filters, which were exposed during October-November 1987 in Pripyat town, were studied. Measurements on 22 November 1987 showed that an activity in the air was 12.1-20.8 mBq/m3 for 137Cs, 34.9-89.3 mBq/m-3 for 144Ce, 24.3-30.5 mBq/m-3 for 106Ru. Disperse structure of aerosol hot particles and the number of hot particles on each filter fragment was estimated by radiography. To determine a dissolution rate constant a static system with two 0.14 micron pore size membrane MFE filters (Dubna, Russia) enclosing fragments of Petryanov filters was selected. The composition was held in Gamble's solution lung fluid anf then in 0.1 mol/l HCl as dastic juice simulation. The activity of 90Sr, 238Pu, 239 + 240Pu, 241Am and 244Cm in aerosol filters and solutions was measured by radiochemical methods. It was shown that leaching of radionuclides from aerosol hot particles in lung fluid simulation decreases in line 137Cs > 90Sr > 239 + 240Pu > or = 241Am, depending om particle diameter and time. Dissolution constants were presented. Dissolution of aerosol particles in 0.1 mol/l HCl is also shown (dissolution time was 3 days). A radionuclide transition to HCl solution decreases in line 90Am 241Am > 137Cs > 239 + 240Pu. A transition degree reached 21% for 90Sr and extraction of 241Am was 3-17%.