WorldWideScience

Sample records for removing inhaled radionuclides

  1. Improvements in lung lavage to increase its effectiveness in removing inhaled radionuclides

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Guilmette, R.A.; Romero, L.M.; Mewhinney, J.A.

    1991-01-01

    Lung lavage has been shown to be an effective method to remove insoluble radionuclides deposited and retained in the lung, but the treatment has been limited to the effective removal of only about 50% of the retained material. Reported here is change in lavage technique that slightly increases the effectiveness and the addition of high-frequency chest wall oscillation. The latter increased the effectiveness of the lavage procedure but also caused significant physiological complications. These studies were conducted in adult male and female beagles. The aerosol in the first study was 239 PuO 2 heat-treated at 850 degrees C, obtained as powder from a commercial V-blending process. The dogs briefly inhaled the aerosol per nasi. The tissue content at death and the amount of 239 Pu excreted and in the recovered lung lavage fluid was determined by radiochemical methods 5 . These values were used to reconstruct the initial pulmonary burden of 239 and the amount of 239 Pu removed by lavage. In the second study, with the HFCWO, the aerosol was 85 Sr fused in aluminosilicate particles. The IPB of 85 Sr was determined by whole-body counting. The excreta and recovered lung lavage fluids were also assayed for 85 Sr activity

  2. Is the human nasal cavity at risk from inhaled radionuclides?

    International Nuclear Information System (INIS)

    Boecker, B.B.; Hahn, F.F.; Cuddihy, R.G.; Snipes, M.B.; McClellan, R.O.

    1986-01-01

    In a series of three life-span studies in which beagle dogs inhaled relatively soluble forms of beta-emitting radionuclides, a number of cancers of the nasal cavity have arisen at long times after the inhalation exposure. No such cancers were observed in the control dogs. Data obtained in other studies involving serial sacrifice of dogs that received these radionuclides in similar forms have shown that high local concentrations of the radionuclides can persist in nasal turbinates for long periods of time, depending on the physical half-life of the radionuclide inhaled. Several nasal carcinomas have also been observed in dogs injected with 137 CsCl in which the relative concentrations of beta activity in the turbinate region were not as pronounced as in the above studies. Similar risks of sinonasal cancer were calculated for dogs in each of these studies regardless of differences in radionuclide, dosimetry, and route of administration. Since sinonasal cancers have occurred in people exposed to alpha-emitting radionuclides, it is reasonable to assume this could occur with beta emitters as well. Radiation protection guidelines should account for the sinonasal region being at risk. 23 refs., 1 fig., 6 tabs

  3. Toxicity of inhaled alpha-emitting radionuclides - Status report

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Guilmette, R.A.; Gillett, N.A.; Diel, J.H.; Lundgren, D.L.; Hahn, F.F.; Boecker, B.B.; McClellan, R.O.

    1988-01-01

    The toxicity of inhaled alpha-emitting radionuclides is being investigated in a series of interrelated dose-response studies. Dogs, rodents, and nonhuman primates have been exposed to monodisperse or polydisperse aerosols of the oxides of 239 Pu, 238 Pu, 241 Am, or 244 Cm to measure the relative importance of average organ dose, local dose around particles, specific activity, chemical form, particle size, and number of particles inhaled to the development of biological effects. The influence of animal species, age at exposure, and pre-existing lung disease, as well as the effects of repeated exposure, are also being studied, because they may influence the toxicity of these radionuclides. (author)

  4. Toxicity of inhaled alpha-emitting radionuclides - Status report

    Energy Technology Data Exchange (ETDEWEB)

    Muggenburg, B A; Mewhinney, J A; Guilmette, R A; Gillett, N A; Diel, J H; Lundgren, D L; Hahn, F F; Boecker, B B; McClellan, R O

    1988-12-01

    The toxicity of inhaled alpha-emitting radionuclides is being investigated in a series of interrelated dose-response studies. Dogs, rodents, and nonhuman primates have been exposed to monodisperse or polydisperse aerosols of the oxides of {sup 239}Pu, {sup 238}Pu, {sup 241}Am, or {sup 244}Cm to measure the relative importance of average organ dose, local dose around particles, specific activity, chemical form, particle size, and number of particles inhaled to the development of biological effects. The influence of animal species, age at exposure, and pre-existing lung disease, as well as the effects of repeated exposure, are also being studied, because they may influence the toxicity of these radionuclides. (author)

  5. Toxicity studies of inhaled beta-emitting radionuclides - Status report

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, F F; Boeker, B B; Gillett, N A; Griffith, W C; Lundgren, D L; McClellan, R O; Muggenburg, B A; Snipes, M B

    1988-12-01

    The effects of beta-emitting radionuclides inhaled in either a relatively soluble form ({sup 90}SrCl{sub 2}, {sup 144}CeCl{sub 3}, {sup 91}yl{sub 3}, or {sup 137}CsCl) or in a relatively insoluble form ({sup 90}Y, {sup 91}Y, {sup 144}Ce or {sup 90}Sr in fused aluminosilicate particles [FAP]) have been studied in laboratory animals. The results showed that the total beta dose and the dose-rate pattern can modify both the neoplastic and non-neoplastic effects of inhaled beta-emitting radionuclides. In addition, the solubility and chemical characteristics of the radionuclides influence which organs are affected. Effects are seen primarily in organs where the radionuclide is ultimately accumulated, e.g., lung, bone, liver, or tracheobronchial lymph nodes. In addition, effects may be seen in organs where there is little accumulation, but where the radiation dose may still be high, e.g., nasal epithelium and heart. Studies of inhaled {sup 144}Ce-FAP in four different species showed that, compared to mice and dogs, lung tumor risk factors are very low for Syrian hamsters and high for rats. Studies of mice, Syrian hamsters, rats, and dogs repeatedly exposed to aerosols of {sup 144}Ce-FAP showed that lung tumor incidence correlates better with cumulative dose to the lung than with dose rate. Most of the studies in this program are nearing completion and full analyses are in progress. (author)

  6. Individual monitoring program for occupational exposures to radionuclides by inhalation

    International Nuclear Information System (INIS)

    Piechowski, J.; Menoux, B.

    1985-01-01

    Individual monitoring of exposure to radioactive products is carried out when there is a risk of significant internal contamination. In its publications 26 and 35 the International Commission on Radiological Protection has given recommendations on the monitoring programs. Besides, the metabolic models developed in publication 30 have allowed to establish retention and excretion functions for some radionuclides after intake by inhalation in the adult man. These have been published in the report CEA-R--5266. Considering these data and taking into account the practical problems that occur in the course of surveillance of workers, programs of individual monitoring for contamination by inhalation are proposed. These programs for routine and special monitoring have been developed for the most common radionuclides involved in the nuclear industry [fr

  7. Organ dose from inhaled radionuclides taking lull period into account

    International Nuclear Information System (INIS)

    Datta, S.

    1982-01-01

    The dosimetry of inhaled radionuclides is generally carried out in accordance with the lung model recommended by the ICRP Task Group on Lung Dynamics. The relevant expressions are integrated over a given period, assuming continuous inhalation in an atmosphere of constant aerosol concentration. Though for the same amount of intake the dose commitment is found to be independent of variations in the rate of intake, the dose determined over specific intervals of time, is influenced by it or by lull intervals therein. Formulae are developed to arrive at doses to different organs when the subject's intake is constant and continuous for 8 hours, followed by a lull period of 16 hours each day. Results are given for a number of radionuclides and are compared with values characteristic of continuous inhalation. It is observed that when exposure is assumed to be continuous the dose for the same intake of activity is underestimated as compared to the dose when lull period is taken into account. For working periods of 6 days and 30 days the underestimate ranges from 5%-20% and 0.6% to 4.5% respectively. (author)

  8. Influence of radiation-dose pattern from inhaled beta--gamma-emitting radionuclides on canine peripheral lymphocytes

    International Nuclear Information System (INIS)

    Jones, R.K.; Boecker, B.B.; Pickrell, J.A.; Hobbs, C.H.; McClellan, R.O.

    1976-01-01

    As part of studies assess the biological hazards associated with inhaled radionuclides, periodic hematologic evaluations were performed on beagle dogs given a single nose-only exposure to aerosols of beta--gamma-emitting isotopes. The physical form and specific radionuclides selected produced radiation-dose patterns representative of those which might be encountered in the event of human accidental exposures. Dogs received graded lung burdens of either 90 Y, 91 Y, 144 Ce, or 90 Sr, each in fused clay. Differences in the effective half-lives of these radionuclides resulted in a spectrum of cumulative radiation doses to lung delivered at a variety of dose rates. Since the form in which the radionuclides were inhaled was relatively insoluble, the lung and intrathoracic tissues represented the primary recipient of the dose. Regardless of the effective half-life of radionuclide retention, a dose-related depression of peripheral lymphocytes was observed at various times after inhalation exposure. The time at which maximum depression and subsequent recovery occurred, however, was most directly related to the effective half-life of the radionuclide. Of special interest was the persistence of lymphopenia through 2 1 / 2 years after exposure to 144 Ce and 90 Sr in fused clay where, other than tracheobronchial lymph nodes, the lymphoid tissue received very little radiation dose. The possible mechanisms responsible for lymphocyte depression from these various radiation-dose patterns are discussed

  9. Age-specific inhalation radiation dose commitment factors for selected radionuclides

    International Nuclear Information System (INIS)

    Strenge, D.L.; Peloquin, R.A.; Baker, D.A.

    1982-08-01

    Inhalation dose commitment factors are presented for selected radionuclides for exposure of individuals in four age groups: infant, child, teen and adult. Radionuclides considered are 35 S, 36 Cl, 45 Ca, 67 Ga, 75 Se, 85 Sr, 109 Cd, 113 Sn, 125 I, 133 Ba, 170 Tm, 169 Yb, 182 Ta, 192 Ir, 198 Au, 201 Tl, 204 Tl, and 236 Pu. The calculational method is based on the human metabolic model of ICRP as defined in Publication 2 (ICRP 1959) and as used in previous age-specific dose factor calculations by Hoenes and Soldat (1977). Dose commitment factors are presented for the following organs of reference: total body, bone, liver, kidney, thyroid, lung and lower large intestine

  10. Removal of some radionuclides from water by bioaccumulation

    International Nuclear Information System (INIS)

    Miskovic, D.; Conkic, L.; Dalmacija, B.; Gantar, M.

    1992-01-01

    First objective of this study was to investigate the application of biologically activated carbon (BAC) as well as its comparison to adsorption, with the aim of removing some radionuclides from water. The isotopes Cs 134 and Cs 137 were bioaccumulated by BAC up to 50%, while the I 131 isotope was only physicochemically adsorbed (about 40%). Also, the process of radionuclides (Cs 137 , Ce 139 , Co 57 , Co 60 ) fixation on blue-green algae (Nostoc sp.) was investigated. The kinetics of the removal of these radionuclides from water was recorded. It was found that after a contact period of about half an hour 40-70% of the activity was removed. (Author)

  11. The effect of morphometric scaling on deposition and clearance of inhaled radionuclides

    International Nuclear Information System (INIS)

    Bergmann, R.; Hofmann, W.; Koblinger, L.

    1996-01-01

    The linear dimensions of present lung models are based on morphometric measurements on fully inflated lungs. To simulate deposition and clearance of inhaled radionuclides in human lungs under normal breathing conditions, airway diameters and lengths have to be scaled down to the smaller dimensions at functional residual capacity of about 3000 ml

  12. Removal of some radionuclides from water by bioaccumulation

    Energy Technology Data Exchange (ETDEWEB)

    Miskovic, D.; Conkic, L.; Dalmacija, B.; Gantar, M. (Trg D. Obradvica 3, Novi Sad (Yugoslavia). Faculty of Sciences)

    1992-01-01

    First objective of this study was to investigate the application of biologically activated carbon (BAC) as well as its comparison to adsorption, with the aim of removing some radionuclides from water. The isotopes Cs[sup 134] and Cs[sup 137] were bioaccumulated by BAC up to 50%, while the I[sup 131] isotope was only physicochemically adsorbed (about 40%). Also, the process of radionuclides (Cs[sup 137], Ce[sup 139], Co[sup 57], Co[sup 60]) fixation on blue-green algae (Nostoc sp.) was investigated. The kinetics of the removal of these radionuclides from water was recorded. It was found that after a contact period of about half an hour 40-70% of the activity was removed. (Author).

  13. The relative effectiveness of inhaled alpha- and beta-emitting radionuclides in producing lung cancer

    International Nuclear Information System (INIS)

    Boecker, B.B.; Hahn, F.F.; Muggenburg, B.A.; Guilmetter, R.A.; Griffith, W.C.; McClellan, R.O.

    1988-01-01

    Proper assessment of a long-term human health risks associated with inhaled radionuclides requires knowledge of dose to critical cells and tissues and relationships between dose and effect for different biological end points. Results from epidemiological studies of exposed human populations provided important information for such assessments. However, because the types of exposures are limited, these results need to be supplemented with more detailed information on dosimetry and biological effects available through studies in laboratory animals and in vitro systems. To provide health risk information for inhaled fission product and actinide aerosols, life-span studies are being conducted using beagle dogs and other species at the Lovelace Inhalation Toxicology Research Institute (ITRI). Results of two life-span studies in dogs involving inhalation of the beta emitter 91 Y in fused aluminosilicate particles or the alpha emitter 239 PuO 2 are reported here

  14. ACRO - a computer program for calculating organ doses from acute or chronic inhalation and ingestion of radionuclides

    International Nuclear Information System (INIS)

    Hirayama, Akio; Kishimoto, Yoichiro; Shinohara, Kunihiko.

    1978-01-01

    The computer program ACRO has been developed to calculate organ doses from acute or chronic inhalation and ingestion of radionuclides. The ICRP Task Group Lung Model (TGLM) was used for inhalation model, and a simple one-compartment model for ingestion. This program is written in FORTRAN IV, and can be executed with storage requirements of about 260 K bytes. (auth.)

  15. Induction of cancers in the rat after inhalation of alpha-emitting radionuclides

    International Nuclear Information System (INIS)

    Morin, M.; Nenot, J.C.; Masse, R.; Nolibe, D.; Metivier, H.; Lafuma, J.

    1976-01-01

    Experiments have been conducted for several years on the toxic action of inhaled alpha-emitters on laboratory rats. The inhaled radionuclides were 239 Pu, 238 Pu and 241 Am in oxide and nitrate form. The initial alveolar activities varied to give total activities ranging from 1 to 200 thousand million alpha-particles per gram of lung. Variations, depending on the physico-chemical form of the nuclides, in the space and time distributions of the dose are observed. The influence of the two parameters on life span reduction, latency time and frequency of cancer occurrence, initial location of tumours and their histological types were studied. A theoretical model relating the cancerogenous effect to the dose is compared with experimental data. (author)

  16. Lifestyle and age as determinates of intake and dose from inhaled radionuclides

    International Nuclear Information System (INIS)

    Fields, D.E.; Yalcintas, M.G.

    1989-01-01

    The whole-body dose from inhaled radionuclides is a complex function of factors describing exposure and physiology. Exposure-related factors may be estimated by considering likely emission rates combined with measured time-varying meteorological (transport) parameters and estimated exercise patterns. Physiological factors, strongly influencing radionuclide intake and consequent radiation dose, have been catalogued as functions of age and activity level. Both exercise patterns and physiological factors are related to age of the exposed individual. Combining these factors permits estimates to be made of the span of exposures that may be expected in a typical population. The ratio of highest to lowest radionuclide intake is predicted to be of the order of 40, suggesting that specification of an 'average' value may be misleading if this value approaches regulatory limits. Individuals exposed to maximal risk may be identified, and are likely to be active children. Activity pattern (lifestyle) is a primary determinant of risk. (author)

  17. Radiation dose estimates and hazard evaluations for inhaled airborne radionuclides: Final report

    International Nuclear Information System (INIS)

    Mewhinney, J.A.

    1987-09-01

    The project objective was to conduct confirmatory research on physical chemical characteristics of aerosols produced during manufacture of mixed plutonium and uranium oxide nuclear fuel, to determine the radiation dose distribution in tissues of animals after inhalation exposure to representative aerosols of these materials, and to provide estimates of the relationship of radiation dose and biological response in animals after such inhalation exposure. The first chapter summarizes the physical chemical characterization of samples of aerosols collected from gloveboxes at industrial facilities during normal operations. This chapter provides insights into key aerosol characteristics which are of potential importance in determining the biological fate of specific radionuclides contained in the particulates that would be inhaled by humans following accidental release. The second chapter describes the spatial and temporal distribution of radiation dose in tissues of three species of animals exposed to representative aerosols collected from the industrial facilities. These inhalation studies provide a basis for comparison of the influence of physical chemical form of the inhaled particulates and the variability among species of animal in the radiation dose to tissue. The third chapter details to relationship between radiation dose and biological response in rats exposed to two aerosol forms each at three levels of initial pulmonary burden. This study, conducted over the lifespan of the rats and assuming results to be applicable to humans, indicates that the hazard to health due to inhalation of these industrial aerosols is not different than previously determined for laboratory produced aerosol of PuO 2 . Each chapter is processed separately for the data base

  18. A mathematical model for predicting the probability of acute mortality in a human population exposed to accidentally released airborne radionuclides. Final report for Phase I of the project: early effects of inhaled radionuclides

    International Nuclear Information System (INIS)

    Filipy, R.E.; Borst, F.J.; Cross, F.T.; Park, J.F.; Moss, O.R.

    1980-06-01

    The report presents a mathematical model for the purpose of predicting the fraction of human population which would die within 1 year of an accidental exposure to airborne radionuclides. The model is based on data from laboratory experiments with rats, dogs and baboons, and from human epidemiological data. Doses from external, whole-body irradiation and from inhaled, alpha- and beta-emitting radionuclides are calculated for several organs. The probabilities of death from radiation pneumonitis and from bone marrow irradiation are predicted from doses accumulated within 30 days of exposure to the radioactive aerosol. The model is compared with existing similar models under hypothetical exposure conditions. Suggestions for further experiments with inhaled radionuclides are included

  19. Removal of natural radionuclides from drinking water from private wells in Finland

    International Nuclear Information System (INIS)

    Huikuri, Pia; Salonen, Laina; Turtiainen, Tuukka

    1999-01-01

    Removal of natural radionuclides is often necessary in Finland when household water is taken from a drilled well. Removal of radionuclides by various methods from Finnish groundwaters were studied in a EU-research project, TENAWA. The results indicated that radon can be removed very efficiently (up to 99%) by applying aeration or granular activated carbon (GAC) filtration. Uranium and radium were also removed (over 94%) by using strong base anion (SBA) and strong acid cation (SAC) resins. The capability of reverse osmosis (RO) equipment to remove radionuclides was over 90% for uranium, radium and polonium. The water quality analyses indicated that water quality remained mostly good during the water treatment. (au)

  20. The RADionuclide Transport, Removal, and Dose (RADTRAD) code

    International Nuclear Information System (INIS)

    Miller, L.A.; Chanin, D.I.; Lee, J.

    1993-01-01

    The RADionuclide Transport, Removal, And Dose (RADTRAD) code is designed for US Nuclear Regulatory Commission (USNRC) use to calculate the radiological consequences to the offsite population and to control room operators following a design-basis accident at Light Water Reactor (LWR) power plants. This code utilizes updated reactor accident source terms published in draft NUREG-1465, ''Accident Source Terms for Light-Water Nuclear Power Plants.'' The code will track the transport of radionuclides as they are released from the reactor pressure vessel, travel through the primary containment and other buildings, and are released to the environment. As the radioactive material is transported through the primary containment and other buildings, credit for several removal mechanisms may be taken including sprays, suppression pools, overlying pools, filters, and natural deposition. Simple models are available for these different removal mechanisms that use, as input, information about the conditions in the plant and predict either a removal coefficient (λ) or decontamination factor. The user may elect to use these models or input a single value for a removal coefficient or decontamination factor

  1. Removal of radionuclides at a waterworks

    DEFF Research Database (Denmark)

    Gäfvert, T.; Ellmark, C.; Holm, E.

    2002-01-01

    A waterworks with an average production rate of 1.3 m3 s−1, providing several large cities in the province of Scania with drinking water has been studied regarding its capacity to remove several natural and anthropogenic radionuclides. The raw water is surface water from lake Bolmen which...

  2. An experimental study on the toxicity of several radionuclides inhaled at different doses

    International Nuclear Information System (INIS)

    Lafuma, J.; Nenot, J.C.; Morin, M.; Masse, R.; Metivier, H.; Nolibe, D.; Skupinski, W.

    1975-01-01

    For over 5 years investigations have been carried out on large lots of rats on the toxicological action of several inhaled radionuclides. Various physico chemical forms of α-emitting actinides and β-emitting lanthanides were used, respectively 239 Pu, 238 Pu, 241 Am, as oxide or nitrate solution at pH1, 244 Cm nitrate, and 144 Ce chloride and 141 Ce chloride and oxide. The activities deposited per gram of lung varied between 10nCi and 10μCi. The first effect observed was life-shortening. A comparison of the survival curves shows a heterogeneity factor whose values for the various radionuclides is given. Lung cancers were also observed. Rarely lung carcinomas were the cause of death, which was unknown and seemed to vary with the different compounds [fr

  3. HADOC: a computer code for calculation of external and inhalation doses from acute radionuclide releases

    International Nuclear Information System (INIS)

    Strenge, D.L.; Peloquin, R.A.

    1981-04-01

    The computer code HADOC (Hanford Acute Dose Calculations) is described and instructions for its use are presented. The code calculates external dose from air submersion and inhalation doses following acute radionuclide releases. Atmospheric dispersion is calculated using the Hanford model with options to determine maximum conditions. Building wake effects and terrain variation may also be considered. Doses are calculated using dose conversion factor supplied in a data library. Doses are reported for one and fifty year dose commitment periods for the maximum individual and the regional population (within 50 miles). The fractional contribution to dose by radionuclide and exposure mode are also printed if requested

  4. Chemical removal of radionuclides in contaminated spinach derived from the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Shiba, Kazuhiro; Kitamura, Yoji; Kozaka, Takashi; Uno, Izumi; Miyoshi, Hirokazu; Yanaga, Makoto

    2012-01-01

    We examined a simple and effective removal method for contaminated farm products to ensure the relief of farmers and the security of consumers. Removal of radionuclides from spinach by chemical methods was investigated. The result of chemical removal showed that antioxidant agents removed radionuclides from spinach by 70–80% for 131 I and more than 80% for radiocesium. In particular, ascorbic acid is promising as a safe and versatile option. (author)

  5. Possibility of removing radionuclides in landfill leachate using advanced wastewater treatment processes

    International Nuclear Information System (INIS)

    Ishikawa, Nao K.; Umita, Teruyuki; Ito, Ayumi

    2013-01-01

    Radionuclides released by the nuclear accident at the Fukushima Daiichi Nuclear Power Plant are being partly concentrated to sewage sludge ash and waste ash. These ashes, in which radiocesium concentration is lower than 8000 Bq/kg, are being disposed of in a controlled landfill site. The leachate from the landfill site is treated in a leachate treatment system combined with some treatment steps before it is discharged into receiving water. In this study, in place of radionuclides, stable element concentrations in the leachate and treated water at each treatment step were measured to estimate the possible extent of radionuclide removal from the leachate step-by-step. It was found that Cs was not removed in any treatment steps, while more than 85% of the Sr, Co, Ni, and Mn present was removed in the alkaline earth element removal step. (author)

  6. Transfer of radionuclides into and their removal from agricultural products

    Energy Technology Data Exchange (ETDEWEB)

    Hisamatsu, Shun-ichi [Akita Univ. (Japan). School of Medicine; Takizawa, Yukio

    1996-12-31

    Transfer of radionuclides to agricultural products and their removal before ingestion are reviewed briefly. Ingestion of {sup 137}Cs through various food groups were intensively has been studied from 1960s. The results of these studies indicated that cereals were relatively important food groups in Japan, while dairy products were a critical food group in Western countries. However, Westernization of Japanese diet and other factors recently make dairy products more important. In the case of {sup 137}Cs ingestion from the Chernobyl accident, 43% of total {sup 137}Cs intake was ingested through dairy products. The removal of radionuclides from food by washing, preparing and cooking is also discussed. (author)

  7. Removal of dissolved heavy metals and radionuclides by microbial spores

    International Nuclear Information System (INIS)

    Revis, N.W.; Hadden, C.T.; Edenborn, H.

    1997-01-01

    Microbial systems have been shown to remove specific heavy metals from contaminated aqueous waste to levels acceptable to EPA for environmental release. However, systems capable of removing a variety of heavy metals from aqueous waste to environmentally acceptable levels remain to be reported. The present studies were performed to determine the specificity of spores of the bacterium Bacillus megaterium for the adsorption of dissolved metals and radionuclides from aqueous waste. The spores effectively adsorbed eight heavy metals from a prepared metal mix and from a plating rinse waste to EPA acceptable levels for waste water. These results suggest that spores have multiple binding sites for the adsorption of heavy metals. Spores were also effective in adsorbing the radionuclides 85 strontium and 197 cesium. The presence of multiple sites in spores for the adsorption of heavy metals and radionuclides makes this biosorbent a good candidate for the treatment of aqueous wastes associated with the plating and nuclear industries. 17 refs., 4 tabs

  8. Removal of radionuclides from liquid streams by reverse osmosis

    International Nuclear Information System (INIS)

    Deshmukh, U.A.; Ramachandhran, V.; Misra, B.M.

    1987-01-01

    Separation of radionuclides in trace concentrations by cellulose acetate membranes has been under investigation in this laboratory, and the behaviour of some important radionuclides such as 137 Cs and 90 Sr under reverse osmosis has been reported earlier. The present work deals with a few other typical radionuclides such as 60 Co, 103 Ru and 131 I which are not fully amenable to conventional methods for their removal. Separation of these radionuclides from liquid streams by the reverse osmosis process was studied using a small reverse osmosis test cell. Various parameters like membrane porosity, applied pressure and feed activity levels were investigated. Cellulose acetate membranes offer reasonable separation of 60 Co, 103 Ru and 131 I radionuclides, indicating the potential of reverse osmosis for treatment of effluents containing these radioisotopes. The percent separation is found to be in the order of Co > Ru > I. The percent radioactive separation improves with increases in feed activity. The performance data are explained in terms of solution-diffusion mechanism. It appears that the separation of radionuclides is not governed by diffusion alone, but by the interaction of solutes with the membranes. (author)

  9. Metabolism of radionuclides in domestic animals

    International Nuclear Information System (INIS)

    Wirth, E.; Leising, C.

    1986-01-01

    The reactor accident at Chernobyl has shown that shortly after the contamination of the environment radionuclides can be found in animal products. The main contamination pathways of domestic animas are: uptake of radionuclides by foodstuffs; uptake of radionuclides by contaminated drinking water; uptake of radionuclides by inhalation; uptake of radionuclides through skin; uptake of radionuclides by ingestion of soil particles. Generally the uptake of radionuclides by food is the dominant exposure pathway. In rare cases the inhalation of radionuclides or the uptake by drinking water may be of importance. The metabolism of incorporated radionuclides is comparable to the respective metabolism of essential mass or trace elements or heavy metals. Radioisotopes of essential elements are for instance iron 55, manganese 54, cobalt 58 and cobalt 60. Other elements are typical antagonists to essential elements, e.g. strontium 90 is an antagonist to calcium or cesium 137 to potassium. Lead 210 and plutonium 239 behave similarly as heavy metals. Generally the knowledge of the metabolism of trace and mass elements, of antagonistic and synergistic elements and heavy metals can be applied to these radionuclides

  10. Exposure to radionuclides in smoke from vegetation fires

    International Nuclear Information System (INIS)

    Carvalho, Fernando P.; Oliveira, João M.; Malta, Margarida

    2014-01-01

    Naturally occurring radionuclides of uranium, thorium, radium, lead and polonium were determined in bushes and trees and in the smoke from summer forest fires. Activity concentrations of radionuclides in smoke particles were much enriched when compared to original vegetation. Polonium-210 ( 210 Po) in smoke was measured in concentrations much higher than all other radionuclides, reaching 7255 ± 285 Bq kg −1 , mostly associated with the smaller size smoke particles ( 210 Po in surface air near forest fires displayed volume concentrations up to 70 mBq m −3 , while in smoke-free air 210 Po concentration was about 30 μBq m −3 . The estimated absorbed radiation dose to an adult member of the public or a firefighter exposed for 24 h to inhalation of smoke near forest fires could exceed 5 μSv per day, i.e, more than 2000 times above the radiation dose from background radioactivity in surface air, and also higher than the radiation dose from 210 Po inhalation in a chronic cigarette smoker. It is concluded that prolonged exposure to smoke allows for enhanced inhalation of radionuclides associated with smoke particles. Due to high radiotoxicity of alpha emitting radionuclides, and in particular of 210 Po, the protection of respiratory tract of fire fighters is strongly recommended. - Highlights: • Natural radionuclides in vegetation are in low concentrations. • Forest fires release natural radionuclides from vegetation and concentrate them in inhalable ash particles. • Prolonged inhalation of smoke from forest fires gives rise enhanced radiation exposure of lungs especially due to polonium. • Respiratory protection of fire fighters and members of public is highly recommended for radioprotection reasons

  11. Removal of radionuclides from household water

    International Nuclear Information System (INIS)

    Vesterbacka, P.; Turtiainen, T.; Haemaelaeinen, K.; Salonen, L.; Arvela, H.

    2007-02-01

    Research upon methods for removing radionuclides from household water was initiated in Finland in 1995. Three research projects, of which two were carried out with National Technology Agency of Finland and one with CEC, have been completed by the end of 2002. One of the main objectives of the research was to compose a guidebook for consumers and water treatment companies. Radon can be removed from household water by aeration and by activated carbon filtration. Aerators that are well designed and set up can remove over 90% of waterborne radon. The best aerators have achieved removal efficiencies that are nearly 100%. However, setting up an aeration system requires thorough planning. Also, activated carbon filtration removes radon efficiently. The removal efficiencies have been over 90%, often nearly 100%. Depending on the water quality and usage, the carbon batch inside the filter needs to be changed every 2 - 3 years. Since activated carbon filters emit gamma radiation while in use, they should not be installed inside the dwelling but in a separate building or by the well. It is recommended that uranium be removed from drinking water by anion exchange, which is the most efficient removal method for this purpose. Typically, the removal efficiencies are nearly 100%. The one exception is the so called tap filter, the removal efficiency of which depends on uranium concentration in raw water and the rate of water flow. High saline concentration in water may extricate uranium from ion exchange resin. Changes in plumbing pressure or pH-value do not have any significant influence in uranium retention. Removal efficiencies of lead and polonium vary a lot depending on the chemical form in which they occur in water. They can be reliably removed from water by reverse osmosis only. Other treatment methods, such as ion exchange and activated carbon filtration, remove lead and polonium partly. Lead and polonium are removed more efficiently when they are bound onto smaller

  12. Exposure to radionuclides in smoke from vegetation fires

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Fernando P., E-mail: carvalho@itn.pt; Oliveira, João M.; Malta, Margarida

    2014-02-01

    Naturally occurring radionuclides of uranium, thorium, radium, lead and polonium were determined in bushes and trees and in the smoke from summer forest fires. Activity concentrations of radionuclides in smoke particles were much enriched when compared to original vegetation. Polonium-210 ({sup 210}Po) in smoke was measured in concentrations much higher than all other radionuclides, reaching 7255 ± 285 Bq kg{sup −1}, mostly associated with the smaller size smoke particles (< 1.0 μm). Depending on smoke particle concentration, {sup 210}Po in surface air near forest fires displayed volume concentrations up to 70 mBq m{sup −3}, while in smoke-free air {sup 210}Po concentration was about 30 μBq m{sup −3}. The estimated absorbed radiation dose to an adult member of the public or a firefighter exposed for 24 h to inhalation of smoke near forest fires could exceed 5 μSv per day, i.e, more than 2000 times above the radiation dose from background radioactivity in surface air, and also higher than the radiation dose from {sup 210}Po inhalation in a chronic cigarette smoker. It is concluded that prolonged exposure to smoke allows for enhanced inhalation of radionuclides associated with smoke particles. Due to high radiotoxicity of alpha emitting radionuclides, and in particular of {sup 210}Po, the protection of respiratory tract of fire fighters is strongly recommended. - Highlights: • Natural radionuclides in vegetation are in low concentrations. • Forest fires release natural radionuclides from vegetation and concentrate them in inhalable ash particles. • Prolonged inhalation of smoke from forest fires gives rise enhanced radiation exposure of lungs especially due to polonium. • Respiratory protection of fire fighters and members of public is highly recommended for radioprotection reasons.

  13. INREM II: a computer implementation of recent models for estimating the dose equivalent to organs of man from an inhaled or ingested radionuclide

    International Nuclear Information System (INIS)

    Killough, G.G.; Dunning, D.E. Jr.; Pleasant, J.C.

    1978-01-01

    This report describes a computer code, INREM II, which calculates the internal radiation dose equivalent to organs of man which results from the intake of a radionuclide by inhalation or ingestion. Deposition and removal of radioactivity from the respiratory tract is represented by the ICRP Task Group Lung Model. A four-segment catenary model of the GI tract is used to estimate movement of radioactive material that is ingested or swallowed after being cleared from the respiratory tract. Retention of radioactivity in other organs is specified by linear combinations of decaying exponential functions. The formation and decay of radioactive daughters is treated explicitly, with each radionuclide species in the chain having its own uptake and retention parameters, as supplied by the user. The dose equivalent to a target organ is computed as the sum of contributions from each source organ in which radioactivity is assumed to be situated. This calculation utilizes a matrix of S-factors (rem/μCi-day) supplied by the user for the particular choice of source and target organs. Output permits the evaluation of crossfire components of dose when penetrating radiations are present. INREM II is coded in FORTRAN IV and has been compiled and executed on an IBM-360 computer

  14. Removal of radionuclides from process streams - a review

    International Nuclear Information System (INIS)

    Itzkovitch, I.J.; Ritcey, G.M.

    1979-04-01

    This report details the origin and control of radium 226, thorium 230 and lead 210 contamination of mill effluent streams from conventional and non-conventional milling of uranium ores, reviews the basic chemistry of the radionuclides as it relates to potential alternatives for control and presents these alternatives along with a summary of published cost data. The conclusions from the study indicate that the current technology, using sulphuric acid processing, solubilizes only a comparatively small quantity of the radionuclides, with the solid containing approximately the same concentration as the original ore. Present technolgy does not provide for complete removal and isolation of the radionuclides. Current practice for control of thorium 230 in liquid effluents by neutralization is adequate to meet present Governmental guidelines. Radium in solution is presently being controlled by precipitation with barium chloride but levels of less than 3 pCi/L of soluble radium could be difficult if not impossible to achieve consistently by this treatment. Indications are that the concentration of lead 210 in liquid effluent may exceed present guidelines. No specific control procedures are employed for lead 210. Methods of isolating radium 226 are required for treating effluents from conventional milling as well as from alternative processes under development. Ion exchange is suggested as a means of isolating these radionuclides. (OT)

  15. Influence of variations in dose and dose rates on biological effects of inhaled beta-emitting radionuclides

    International Nuclear Information System (INIS)

    McClellan, R.O.; Benjamin, S.A.; Boecker, B.B.; Hahn, F.F.; Hobbs, C.H.; Jones, R.K.; Lundgren, D.L.

    1976-01-01

    The biological effects of inhaled β-emitting radionuclides, 90 Y, 91 Y, 144 Ce and 90 Sr, are being investigated in beagle dogs that received single acute exposures at 12 to 14 months of age. The aerosols studied have included 91 YC1 3 , 144 CeC1 3 , 90 SrC1 2 , and 90 Y, 91 Y, 144 Ce or 90 Sr in aluminosilicate particles. Thus, 91 YCl 3 , 144 CeCl 3 and the aluminosilicate containing radionuclide particles all resulted in significant exposures to lung; 91 YC1 3 , 144 CeC1 3 an 90 SrC1 2 resulted in significant exposures to bone; 91 YC1 3 and 144 CeC1 3 resulted in significant exposures to liver. The higher initial doserate exposures have been more effective than low dose-rate exposures on a per-rad basis in producing early effects. To date ( 144 CeO 2 , it was observed that, on a μCi initial lung burden per kilogram body weight basis, mice did not develop pulmonary tumours whereas beagle dogs did. To fid out the reason for this observation mice have been repeatedly exposed by inhalation to 144 CeO 2 to maintain lung burdens of 144 Ce that resulted in radiation dose rates similar to that observed in beagle dogs. Several of the repeatedly exposed mice developed malignant pulmonary tumours. Thus, with similar dose rates and cumulative doses to the lung, mice and dogs responded in a similar manner to chronic β radiation

  16. Removal of radionuclides from household water

    International Nuclear Information System (INIS)

    Vesterbacka, P.; Turtiainen, T.; Haemaelaeinen, K.; Salonen, L.; Arvela, H.

    2003-10-01

    Research upon methods for removing radionuclides from household water was initiated in Finland in 1995. Three research projects, of which two were carried out with National Technology Agency of Finland and one with CEC, have been completed by the end of 2002. One of the main objectives of the research was to compose a guidebook for consumers and water treatment companies. Radon can be removed from household water by aeration and by activated carbon filtration. Aerators that are well designed and set up can remove over 90% of waterborne radon. The best aerators have achieved removal efficiencies that are nearly 100%. However, setting up an aeration system requires thorough planning. Also, activated carbon filtration removes radon efficiently. The removal efficiencies have been over 90%, often nearly 100%. Depending on the water quality and usage, the carbon batch inside the filter needs to be changed every 2-3 years. Since activated carbon filters emit gamma radiation while in use, they should not be installed inside the dwelling but in a separate building or by the well. It is recommended that uranium be removed from drinking water by anion exchange, which is the most efficient removal method for this purpose. Typically, the removal efficiencies are nearly 100%. The one exception is the so called tap filter, the removal efficiency of which depends on uranium concentration in raw water and the rate of water flow. High saline concentration in water may extricate uranium from ion exchange resin. Changes in plumbing pressure or pH-value do not have any significant influence in uranium retention. Removal efficiencies of lead and polonium vary a lot depending on the chemical form in which they occur in water. They can be reliably removed from water by reverse osmosis only. Other treatment methods, such as ion exchange and activated carbon filtration, remove lead and polonium partly. Lead and polonium are removed more efficiently when they are bound onto smaller particles

  17. Environmental behaviour of radionuclides and transfer to man

    International Nuclear Information System (INIS)

    Smith, H.

    1982-01-01

    The environmental behaviour of the radionuclides making the major contribution to man's irradiation through diet is described. The following stages are emphasized: transfer of radionuclides to plants; transfer of radionuclides to animals; metabolism of inhaled or ingested radionuclides in animals providing food for man; transfer of radionuclides through the aquatic environment; application of food chain models. (43 references)

  18. Long-term dose-response studies of inhaled or injected radionuclides

    International Nuclear Information System (INIS)

    Boecker, B.B.; Muggenburg, B.A.; Miller, S.C.; Bradley, P.L.

    1994-01-01

    This report describes the scientific progress in, and current status of, life-span studies of the long-term health risks in Beagle dogs of chronic irradiation from internally deposited radionuclides or from an external source. The reporting period for this document is the 2-year period from October 1, 1991 through September 30, 1993. Studies that were initiated at three different laboratories (Inhalation Toxicology Research Institute, ITRI, University of Utah, and Argonne National Laboratory, ANL) are presented here because they are being completed at ITRI. All living dogs in the Utah-initiated studies were transferred to the ITRI facility for the remainder of their life-span observations and measurements in September 1987. This report is the fourth in a series of reports dealing with the current status and progress of both the Utah and ITRI studies. Other life-span studies involving dogs exposed to gamma radiation from an external source were initiated and conducted for many years at ANL. In 1991, the decision was made to discontinue the chronic irradiation of the remaining living dogs and to transfer all remaining dogs to ITRI for care, clinical observations, and pathological observations at death or euthanasia. This report provides the current status of these dogs. Status reports on the Utah and ITRI studies comprise most of this report. The ITRI-related section presents brief statements of project objectives, the general procedures used in these studies, and some study-specific features for each of the 19 studies being conducted with either beta- or alpha-emitting radionuclides. Dose- and effect-modifying factors being addressed in these studies include total dose, dose rate, LET, solubility, nonuniformity of dose, species, age, sex, health status, and mode of exposure. Recent additions to experimental protocols for studies in which dogs are still alive involve the collection and analysis of tumor tissues using currently available molecular biology techniques

  19. Human dose pathways of radionuclides in forests

    International Nuclear Information System (INIS)

    Rantavaara, A.

    2009-01-01

    Forest soil, understorey vegetation and trees are all sources of radionuclides and human radiation doses after contaminating atmospheric deposition. People are exposed to radiation externally from sources outside the body and internally via ingestion and inhalation of radionuclides. Understorey vegetation contributes to ingestion doses through berries, herbs, wild honey, mushrooms and game meat; also trees provide feed to terrestrial birds and big game. During stay in forests people are subject to external radiation from forest floor and overstorey, and they may inhale airborne radioactive aerosol or gaseous radionuclides in ground level air. In the early phase of contamination also resuspended radionuclides may add to the internal dose of people via inhalation. People in Nordic countries are most exposed to radiation via ingestion of radionuclides in wild foods. The distribution of radionuclides in forests is changed by environmental processes, and thereby also the significance of various dose pathways to humans will change with time. External exposure is received in living environment from contaminated stemwood used as building timber and for manufacturing of furniture and other wood products. The aim of this paper is to outline the significance of various human dose pathways of radionuclides in forests considering the public and workers in forestry and production of bioenergy. Examples on effective doses are given based on two historical events, atmospheric nuclear weapon tests (mostly in 1950's and in 1960's) and the Chernobyl nuclear power plant accident in 1986. (au)

  20. Intake of radioactivity by inhalation, in buildings after nuclear incidents

    International Nuclear Information System (INIS)

    Brenk, H.D.

    1987-01-01

    Risk studies so far assumed that in case of a nuclear incident, the exposure of persons through inhalation proceeds in free air by direct intake of contaminated ambient air. In reality, however, about 80 p.c. of the population is indoors, and there is a considerable delay of room air contamination in comparison with free air contamination. The radionuclides are deposited on indoor surfaces (such as walls, windows, furniture, etc.), and in air-conditioning systems on the filters. This contamination is somewhat regularly removed through cleaning or filter exchange, which reduces the contamination of room air, and then also the radiation exposure by inhalation. The reducing effect can be enhanced by such simple measures as closing doors and windows in time, and switching the air-conditioning system to recirculating regime, followed by enhanced fresh air supply at a later time. (orig./HP) [de

  1. Factors influencing the transfer of radionuclides in agricultural food chains

    International Nuclear Information System (INIS)

    Vandecasteele, C.M.; Zeevaert, Th.; Kirchmann, R.

    1991-01-01

    The applications of nuclear energy have led and will continue to lead to routine or accidental discharges of radioactive elements into the atmospheric and/or aquatic environment resulting in the exposure of populations to ionising radiations. The radionuclides released into the atmosphere are transported downwind, dispersed by the atmospheric mixing phenomena and progressively settled by deposition processes. During the passage of the radioactive cloud, people are irradiated externally as well as internally by inhalation. After the passage of the cloud, exposure of the population continues via three main pathways: external irradiation from the radionuclides deposited on the ground, inhalation of resuspended contaminated particles and ingestion of contaminated food products. When discharged into aquatic systems, the radionuclides can be partly removed from the aqueous phase by adsorption on suspended solids and bottom sediments. As the radioactivity disperses, there is a continuing exchange between water and solid phases. The contaminated sediments deposited on the banks of rivers, lakes and coastal area lead to external irradiation of people spending time at these sites. The residual activity in water exposes man internally through the ingestion of drinking water and food products, contaminated by irrigation of vegetation and ingestion of water by livestock. Among the various exposure pathways, the main route of entry of fission products and most other artificial radionuclides into man has been identified as uptake from the diet. Since agricultural products constitute the basic diet of most populations, the fate and behavior of radionuclides in agricultural ecosystems are of primary importance when assessing the exposure risk of man from environmental releases of radioactivity. 69 refs., 4 figs

  2. Position Paper on Practicable Performance Criteria for the Removal Efficiency of Volatile Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    R. T. Jubin; N. Soelberg; D. M. Strachan

    2012-03-01

    As a result of fuel reprocessing, volatile radionuclides may be released from the facility stack if no processes are put in place to remove them. The radionuclides that are of concern in this document are 3H, 14C, 85Kr, and 129I. The question we attempted to answer is how efficient must this removal process be for each of these radionuclides? To answer this question, we examined the three regulations that may impact the degree to which these radionuclides must be reduced before process gases can be released from the facility. These regulations are 40 CFR 61 (EPA 2010a), 40 CFR 190(EPA 2010b), and 10 CFR 20 (NRC 2012). These regulations apply to the total radionuclide release and to a particular organ - the thyroid. Because these doses can be divided amongst all the radionuclides in different ways and even within the four radionuclides in question, we provided several cases. We first looked at the inventories for these radionuclides for three fuel types (PWR UOX, PWR MOX, and AHTGR), several burn-up values, and time out of reactor extending to 200 y. We calculated doses to the maximum exposed individual (MEI) with the EPA code CAP-88 (Rosnick 1992). Finally, we looked at two dose cases. Allocating all of the allowable dose to be used by the volatile radionuclides is one case, but, perhaps, unrealistic. In lieu of this, we arbitrarily selected a value of 10% of the allowable dose to be assigned to the volatile radionuclides. We calculated the required decontamination factors (DFs) for both of these cases, including the case for the thyroid dose for which 14C and 129I were the main contributors. With respect to 129I doses, we found that the highest dose was calculated with iodine as a fine particulate. The dose scaled as the fraction of the total 129I that was particulate. Therefore, we assumed for all of our calculations that 100% of the 129I was particulate and allow the user of the results given here to scale our calculated doses to their needs.

  3. Treatment techniques for removing natural radionuclides from drinking water. Final report of the TENAWA project

    International Nuclear Information System (INIS)

    Annanmaeki, M.; Turtiainen, T.

    2000-01-01

    TENAWA project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water) was carried out on a cost-shared basic with the European Commission (CEC) under the supervision of Directorate-General XII, Radiation Protection Unit. TENAWA project was started because in several European countries ground water supplies may contain high amounts of natural radionuclides. During the project both laboratory and field research was performed in order to test the applicability of different equipment and techniques for removing natural radionuclides from drinking water. The measurable objectives of the project were: to give recommendations on the most suitable methods for removing radon ( 222 Rn), uranium ( 238,234 U), radium ( 226 , 228 Ra), lead ( 210 Pb) and polonium ( 210 Po) from drinking water of different qualities (i.e. soft, hard, iron-, manganese- and humus-rich, acidic) to test commercially available equipment for its ability to remove radionuclides; to find new materials, absorbents and membranes effective in the removal of radionuclides and to issue guidelines for the treatment and disposal of radioactive wastes produced in water treatment. Radon could be removed efficiently (>95%) from domestic water supplies by both aeration and granular activated carbon (GAC) filtration. Defects in technical reliability or radon removal efficiency were observed in some aerators. The significant drawback of GAC filtration was the elevated gamma dose rates (up to 120 μSv/h) near the filter and the radioactivity of spent GAC. Aeration was found to be a suitable method for removing radon at waterworks, too. The removal efficiencies at waterworks where the aeration process was designed to remove radon or carbon dioxide were 67-99%. If the aeration process was properly designed, removal efficiencies higher than 95% could be attained. Uranium could best be removed (>95%) with strong basic anion exchange resins and radium by applying strong acidic cation exchange resins

  4. Treatment techniques for removing natural radionuclides from drinking water. Final report of the TENAWA project

    Energy Technology Data Exchange (ETDEWEB)

    Annanmaeki, M.; Turtiainen, T. [eds.

    2000-01-01

    TENAWA project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water) was carried out on a cost-shared basic with the European Commission (CEC) under the supervision of Directorate-General XII, Radiation Protection Unit. TENAWA project was started because in several European countries ground water supplies may contain high amounts of natural radionuclides. During the project both laboratory and field research was performed in order to test the applicability of different equipment and techniques for removing natural radionuclides from drinking water. The measurable objectives of the project were: to give recommendations on the most suitable methods for removing radon ({sup 222}Rn), uranium ({sup 238,234}U), radium ({sup 226}, {sup 228}Ra), lead ({sup 210}Pb) and polonium ({sup 210}Po) from drinking water of different qualities (i.e. soft, hard, iron-, manganese- and humus-rich, acidic) to test commercially available equipment for its ability to remove radionuclides; to find new materials, absorbents and membranes effective in the removal of radionuclides and to issue guidelines for the treatment and disposal of radioactive wastes produced in water treatment. Radon could be removed efficiently (>95%) from domestic water supplies by both aeration and granular activated carbon (GAC) filtration. Defects in technical reliability or radon removal efficiency were observed in some aerators. The significant drawback of GAC filtration was the elevated gamma dose rates (up to 120 {mu}Sv/h) near the filter and the radioactivity of spent GAC. Aeration was found to be a suitable method for removing radon at waterworks, too. The removal efficiencies at waterworks where the aeration process was designed to remove radon or carbon dioxide were 67-99%. If the aeration process was properly designed, removal efficiencies higher than 95% could be attained. Uranium could best be removed (>95%) with strong basic anion exchange resins and radium by applying strong

  5. Contribution of inhalation by food animals to man's ingestion dose

    International Nuclear Information System (INIS)

    Zach, R.

    1985-01-01

    Animals' inhalation (AI) pathway was evaluated for 57 radionuclides using infant dose predictions from the food-chain model LIMCAL. With ingestion transfer coefficients fMi to define transfer from the respiratory tract to milk, the AI pathway appeared to be insignificant compared to animals' plant ingestion, as implicitly assumed in most environmental assessment models for nuclear installations. Using ICRP Publication 30 respiratory clearance models for man to adjust ingestion transfer coefficients, animals' inhalation appeared to be important, particularly for some actinide radionuclides. The AI pathway also appeared to be significant relative to man's inhalation, especially for infants. The importance of the AI pathway varied greatly between radionuclides, and results strongly suggest that it cannot be ignored in environmental assessments. Until better data become available to implement this pathway fully, adjusted ingestion transfer coefficient values can be used for transfer from animals' respiratory tract to milk and other food products

  6. Exposure to radionuclides in smoke from vegetation fires.

    Science.gov (United States)

    Carvalho, Fernando P; Oliveira, João M; Malta, Margarida

    2014-02-15

    Naturally occurring radionuclides of uranium, thorium, radium, lead and polonium were determined in bushes and trees and in the smoke from summer forest fires. Activity concentrations of radionuclides in smoke particles were much enriched when compared to original vegetation. Polonium-210 ((210)Po) in smoke was measured in concentrations much higher than all other radionuclides, reaching 7,255 ± 285 Bq kg(-1), mostly associated with the smaller size smoke particles (fires displayed volume concentrations up to 70 m Bq m(-3), while in smoke-free air (210)Po concentration was about 30 μ Bq m(-3). The estimated absorbed radiation dose to an adult member of the public or a firefighter exposed for 24h to inhalation of smoke near forest fires could exceed 5 μSv per day, i.e, more than 2000 times above the radiation dose from background radioactivity in surface air, and also higher than the radiation dose from (210)Po inhalation in a chronic cigarette smoker. It is concluded that prolonged exposure to smoke allows for enhanced inhalation of radionuclides associated with smoke particles. Due to high radiotoxicity of alpha emitting radionuclides, and in particular of (210)Po, the protection of respiratory tract of fire fighters is strongly recommended. Copyright © 2013 Elsevier B.V. All rights reserved.

  7. Removal of radionuclides at a waterworks

    International Nuclear Information System (INIS)

    Gaefvert, T.; Ellmark, C.; Holm, E.

    2002-01-01

    A waterworks, providing several large cities in the province of Scania with drinking-water, with an average production rate of 1.3 m 3. s -1 has been studied regarding its removal capacity for several natural and anthropogenic radionuclides. The raw water is surface water from lake Bolmen which is transported through an 80 km long tunnel in the bedrock before it enters the waterworks. The method used for purification is a combination of precipitation and filtration in sand filters. Two different purification lines are at the moment in use, one using A1 2 (SO 4 ) 3 as a coagulant and one using FeC1 3 . After coagulation and flocculation the precipitation is removed and the water is passed through two different sand filters (rapid-filtration and slow-filtration). Water samples have been collected at the lake, the inlet at the waterworks, after each of the flocculation basins (A1 2 (SO 4 ) 3 and FeC1 3 ), after rapid-filtration and from the municipal distribution net. The samples have been analysed with respect to its content of uranium, thorium, polonium, radium, plutonium and caesium. (au)

  8. Survey on the radiation exposure of the respiratory tract by inhalation of natural radionuclides

    International Nuclear Information System (INIS)

    Poretti, G.

    1987-01-01

    During the last twenty years, work carried out on radiation exposure of the respiratory tract due to the inhaled, naturally occurring nuclides radon, thoron and short-lived daughters has become increasingly important, because the doses received in the respiratory tract, due mainly to the effect of α rays, reach values among the general population which are comparable to or even higher than the average exposures per year of a population undergoing X-ray diagnostic examinations. A brief introduction to the physical characteristics of the natural radiation nuclides reaching the bronchi and lungs with the inhaled air (Rn-220 - thoron and short lived daughters), and the deposition and clearance of the nuclides (often linked to aerosols), is followed by a discussion of the anatomical/physiological characteristics of the ''lung models'', thanks to which it is possible to calculate the energy quantities (i.e. doses) deposited by the α rays in the epithelium of the lungs and bronchi. In addition the retention mechanisms of the radionuclides (as free ions or as aerosols) are briefly described, and finally the calculations to determine the quantity of radioactivity remaining on the walls of the respiratory tract are given. The construction of dosimetric models requires relatively precise knowledge of the thickness of the mucus layers and of the distribution of the nuclides in the mucus, the ciliary movement, the depth in the tissue of the radiation-sensitive cells etc. On the basis of local doses it is then possible to calculate approximately the regional doses for bronchi, lungs and other organs (via blood, accessible by the nuclides before excretion) for the short lived daughters of Rn-222 and Rn-220. Determination of the mean effective dose equivalent requires, amongst other things, knowledge of the concentration of the nuclides in the inhaled air and the mean respiratory frequency of the members of a population. (orig./HSI)

  9. Removal of inhaled industrial mixed oxide aerosols from Beagle dogs by lung lavage and chelation therapy

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Eidson, A.F.; Guilmette, R.A.

    1978-01-01

    An experiment was conducted in 15 adult Beagle dogs to evaluate lung lavage and chelation therapy for the removal of inhaled particles of mixed actinide oxides. The dogs were divided into three groups of five dogs each. Each group was exposed to an aerosol from a different industrial process. Group 1 was exposed to mixed oxide material which had been calcined at 750 0 C collected from a ball milling process. Group 2 was exposed to mixed oxide material from a centerless grinding operation which had been previously heat treated to 1750 0 C. The third group was exposed to 239 PuO 2 not containing uranium from a V-blending procedure which had been heat treated at 850 0 C. After exposure, three dogs in each group were given ten lung lavages and 18 intravenous injections of calcium trisodium diethylenetriaminepentaacetate (DTPA). All dogs were sacrificed 64 days after inhalation exposure. The tissues were radioanalyzed for plutonium and americium. Fluorimetric analyses for uranium in the tissues are in progress. The urine, feces and lavage fluid are also being analyzed for plutonium, americium and uranium. The distribution of plutonium and americium expressed as percentages of the sacrifice body burden was similar in the tissues of the treated and unteated dogs. The lungs contained most of the radionuclides with a small amount in the liver, skeleton and tracheobronchial lymph nodes. The percentage of the sacrifice body burden of americium and plutonium that was present in the lung was less in the treated dogs and was higher in the TBLN's and skeleton than in the untreated dogs. The ratio of Pu/Am was higher in the lungs than in the original material obtained from the industrial sites suggesting a shorter retention time for americium than plutonium to 64 days in the dog

  10. Human dose pathways of radionuclides in forests; Forests ecosystems

    Energy Technology Data Exchange (ETDEWEB)

    Rantavaara, A. (Radiation and Nuclear Safety Authority, Research and Environmental Surveillance, Helsinki (Finland))

    2009-06-15

    Forest soil, understorey vegetation and trees are all sources of radionuclides and human radiation doses after contaminating atmospheric deposition. People are exposed to radiation externally from sources outside the body and internally via ingestion and inhalation of radionuclides. Understorey vegetation contributes to ingestion doses through berries, herbs, wild honey, mushrooms and game meat; also trees provide feed to terrestrial birds and big game. During stay in forests people are subject to external radiation from forest floor and overstorey, and they may inhale airborne radioactive aerosol or gaseous radionuclides in ground level air. In the early phase of contamination also resuspended radionuclides may add to the internal dose of people via inhalation. People in Nordic countries are most exposed to radiation via ingestion of radionuclides in wild foods. The distribution of radionuclides in forests is changed by environmental processes, and thereby also the significance of various dose pathways to humans will change with time. External exposure is received in living environment from contaminated stemwood used as building timber and for manufacturing of furniture and other wood products. The aim of this paper is to outline the significance of various human dose pathways of radionuclides in forests considering the public and workers in forestry and production of bioenergy. Examples on effective doses are given based on two historical events, atmospheric nuclear weapon tests (mostly in 1950's and in 1960's) and the Chernobyl nuclear power plant accident in 1986. (au)

  11. Age-dependent doses to members of the public from intake of radionuclides: Pt. 5. Compilation of ingestion and inhalation dose coefficients

    International Nuclear Information System (INIS)

    1996-01-01

    The present report is a compilation of age-dependent committed effective dose coefficients for ingestion and inhalation of radionuclides of the 31 elements covered in previous CRP Publications. The biokinetic models for adults given in ICRP Publication 30 are applied to calculate these dose coefficients, except that age-specific excretion rates are used and increased gastrointestinal absorption in infants is assurred. Changes in body mass, and tissue geometry in children are also taken into account. (UK)

  12. The removal of inhaled 239Pu from beagle dogs by bronchopulmonary lavage and chelation therapy

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Slauson, D.O.; Miglio, J.J.; Ruoff, L.; Mersch, S.; McClellan, R.O.

    1976-01-01

    The efficacy of bronchopulmonary lavage and chelatan therapy for removing 239 Pu from beagle dogs after inhalation of 239 Pu aerosols having different solubilities has been investigated. The four aerosols used were nebulized from a solution of 239 PuCl 4 and heat treated at temperatures of 325, 600, 900 and 1150 0 C. Groups of six beagle dogs were exposed to each of the aerosols. Subsequently, three dogs in each group were treated by lavage and intravenous injections of DTPA. The remaining three dogs in each group served as untreated controls. It was found that bronchopulmonary lavage treatment was effective in removing nearly half of the 239 Pu activity from the lung regardless of the aerosol production temperature. This early removal of 239 Pu activity resulted in a significant reduction in daily dose rate and therefore cumulative α dose to lung. The effectiveness of DTPA treatment depended on aerosol production temperature, and was effective in reducing accumulation of 239 Pu in liver and skeleton of the dogs that inhaled aerosols produced at 325 0 and 600 0 C by enhancing urinary excretion of 239 Pu. (U.K.)

  13. Long-lived radionuclides in the air of the Dolni Rozinka uranium mine

    International Nuclear Information System (INIS)

    Otahal, Petr; Burian, Ivo; Vosahlik, Josef

    2010-01-01

    Rozna I is the last open uranium mine in Europe, employing about 400 A-category (underground) workers who are exposed to three types of dose commitment: external gamma radiation, inhalation of short-lived radon decay products, and inhalation of long-lived alpha radionuclides of the uranium family. The paper discusses the last-mentioned factor, for which the derived limit for irradiation from the inhalation of a mixture of long-lived alpha emitters of the uranium family is 1850 Bq per calendar year as set by the Czech State Office for Nuclear Safety Decree No. 307/2002 (as amended by Decree No. 499/2005). Four major factors determine the extent of inhalation of long-lived radionuclides in mine air: concentration of uranium and their daughters in the ore, type of mining work being performed, intensity of ventilation, and intensity of spraying. The long-lived component of contamination of the mine atmosphere can be divided into 2 parts: the before-radon radionuclides ( 234 U, 230 Th, 226 Ra), released during the rock separation work, and the after-radon radionuclides ( 210 Po), which are due to radon decay

  14. Removal of radionuclides from the water-soluble fraction of Hanford nuclear defense wastes

    International Nuclear Information System (INIS)

    Strachan, D.M.; Schulz, W.W.

    1980-01-01

    The current Hanford Waste Management Program has operated since 1968 to remove the bulk of the long-lived heat emitters /sup 90/Sr and /sup 137/Cs from stored high-level wastes. The liquid waste remaining after removal of /sup 90/Sr and /sup 137/Cs is returned to underground tanks for eventual evaporation to damp solid salt cake. Approximately 95,000 m/sup 3/ of salt cake and 49,000 m/sup 3/ of ''sludge'' will eventually accumulate in approximately 50 underground single-shell tanks. One alternative for long-term management of high-level Hanford wastes involves retrieval, after a yet-to-be determined interim storage time, conversion to more immobile forms, and terminal storage in a suitable geologic repository. Another alternative for long-term management of salt cake and residual liquid involves removing most of the long-lived radionuclides and many of the shorter-lived ones from these wastes. This paper describes conditions and results of recent hot cell tests of the complete Hanford Radionuclide Removal Process. These advanced tests, made with actual residual liquid containing large concentrations of ethylenediaminetetracetic acid (EDTA) and other organic compounds, provided a rigorous and convincing proof of the process flowsheet. 16 refs

  15. Data file on retention and excretion of inhaled radionuclides calculated using ICRP dosimetric models

    International Nuclear Information System (INIS)

    Ishigure, Nobuhito; Nakano, Takashi; Enomoto, Hiroko; Shimo, Michikuni; Inaba, Jiro

    2000-01-01

    The authors have computed whole-body or a specific organ content and the daily urinary and faecal excretion rate of some selected radionuclides following acute intake by inhalation and ingestion, where the ICRP new respiratory tract model (ICRP Publication 66) and the latest ICRP biokinetic models were applied. The results were compiled in a file of MS Excel. The file was tentatively called MONDAI for reference. MONDAI contains the data for all radionuclides in ICRP Publications 54 and 78 and, in addition, some other radionuclides which are important from the viewpoint of occupational exposure in nuclear industry, research and medicine. They are H-3, P-32, Cr-51, Mn-54, Fe-59, Co-57, Co-58, Co-60, Zn-65, Rb-86, Sr-85, Sr-89, Sr-90, Zr-95, Ru-106, Ag-110m, Sb-124, Sb-125, I-125, I-129, I-131, Cs-134, Cs-137, Ba-140, Ce-141, Ce-144, Hg-203, Ra-226, Ra-228, Th-228, Th-232, U-234, U-235, U-238, Np-237, Pu-238, Pu-239, Pu-240, Am-241, Cm-242, Cm-244 and Cf-252. The day-by-day data up to 1000 days and the data at every 10 days up to 10000 days are presented. The following ICRP default values for the physical characteristics of the radioactive aerosols were used: AMAD=5 micron, geometric SD=2.5, particle density = 3 g/cm 3 , particle shape factor = 1.5. The subject exposed to the aerosols is the ICRP reference worker doing light work: light exercise with the ventilation rate of 1.5 m 3 /h for 5.5 h + sitting with the ventilation rate of 0.54 m 3 /h for 2.5 h. MONDAI was originally made by Version 7.0 of MS Excel for Windows 95, but the file was saved in the form of Ver. 4.0 as well as Ver. 7.0. Therefore, if the user has Ver. 4.0 or an upper version, he can open the file and operate it. With the graph-wizard of MS Excel the user can easily make a diagram for the retention or daily excretion of a radionuclide of interest. The dose coefficient (Sv/Bq intake) of each radionuclide for each absorption type given in ICRP Publication 68 was also written in each sheet. Therefore

  16. Personnel dosimetry in internal radiation exposure by excretory radionuclide measurement

    International Nuclear Information System (INIS)

    Balonov, M.I.; Bruk, G.Ya.; Korelina, N.F.; Likhtarev, I.A.; Repin, V.S.

    1986-01-01

    The collaboration with the SAAS resulted in the development of a mathematical method to calculate radiation doses in human tissues attributed to inhaled radionuclides concerning their retention dynamics in the respiratory system and their uptake into the blood as well as the metabolic pathways in the organs. 'Sanep-stations' and radiation protection service elaborated nomograms for the determination of the commitment doses in the critical organs based on the radionuclide content of a 24-hours urinalysis without intermediate calculations. Recommendations for the use of the method and the nomograms for various radionuclides (solubility classes D and N with MAAD of 1 and 10 μm) are given in the methodological document: 'Indirect dosimetry of inhaled radionuclides in workers'. A calculation method for the annual dose of internal irradiation in tritium workers is also cited

  17. Inhalation Toxicology Research Institute annual report, October 1, 1983-September 30, 1984

    International Nuclear Information System (INIS)

    Guilmette, R.A.; Medinsky, M.A.

    1984-12-01

    The report describes research in the following areas: (1) aerosol generation and characterization; (2) deposition and fate of inhaled materials; (3) dose-response relationships for inhaled radionuclides; (4) dose-response relationships for inhaled chemical toxicants; and (5) biological factors that influence dose-response relationships. Project descriptions have been individually entered into the date base

  18. Lovelace ITRI studies on the toxicity of inhaled radionuclides in beagle dogs

    International Nuclear Information System (INIS)

    McClellan, R.O.; Boecker, B.B.; Hahn, F.F.; Muggenburg, B.A.

    1986-01-01

    This paper reviews 19 studies conducted by the Lovelace ITRI on the toxicity of inhaled radionuclides in beagle dogs. These studies provide information to estimate potential health effects in accidentally exposed people. Specific radionuclides ( 90 Sr, 90 Y, 91 Y, 137 Cs, 144 Ce, 238 Pu, and 239 Pu), chemical forms, and particle sizes were selected for study because they are abundant in nuclear operations and deliver a wide range of radiation dose patterns. Depending upon the aerosol, one or more of the following organs or tissues received the significant irradiation: lung, nasal cavity, lung-associated lymph nodes, whole body, liver, or skeleton, with the radiation dose delivered over durations of time ranging from a few days to several years. In eight studies monodisperse particles of either 238 PuO 2 or 239 PuO 2 were used to evaluate the influence of particle number and total dose on lung cancer induction. Most studies involved single, brief exposures of young adult dogs, but two studies used immature dogs, two used aged dogs, and two studies involved repeated brief exposures. For each aerosol two types of studies were conducted. One was used to evaluate the time course of retention of radioactivity in various tissues of the body for calculating radiation doses. The second was used to determine health effects in animals exposed to achieve different initial lung burdens and observed for the remainder of their life spans. Initial lung burdens were selected to produce early morbidity and mortality at the highest levels and an excess of late-occurring diseases such as cancer at the lowest levels. The latter dogs have had an excess incidence of cancer, especially of the lung, lung-associated lymph nodes, nasal cavity, skeleton, and liver. Relationships between radiation doses to various tissues and effects have been evaluated for individual studies

  19. The deposition, distribution and retention of inhaled 239PuO2 in the lungs of rats with pulmonary emphysema

    International Nuclear Information System (INIS)

    Lundgren, D.L.; Damon, E.G.; Diel, J.H.; Hahn, F.F.

    1981-01-01

    Individuals with chronic obstructive lung disease, such as emphysema, may be more susceptible to injury from other inhaled pollutants. However, dose-response studies of inhaled radionuclides conducted to aid in estimating the biological effects of inhaled radionuclides in man have typically used healthy laboratory animals. Changes in radionuclide deposition, distribution and retention in the lungs as the result of pre-existing lung diseases could alter the radiation dose or the resulting biological effects. An experimental animal model for human emphysema, in which emphysema is induced by the intratracheal instillation of either elastase or papain, has been reviewed. This model was used to study the effects of pulmonary emphysema on the deposition, distribution and retention of inhaled 239 PuO 2 in rats. (author)

  20. Determination of natural occurring radionuclides concentrations

    International Nuclear Information System (INIS)

    Stajic, J.; Markovic, V.; Krstic, D.; Nikezic, D.

    2011-01-01

    Tobacco smoke contains certain concentrations of naturally occurring radionuclides from radioactive chains of uranium and thorium - 214 Pb, 214 Bi, 228 Ac, 208 Tl, 226 Ra, 232 Th and 40 K. Inhaling of tobacco smoke leads to internal exposure of man. In order to estimate absorbed dose of irradiation it is necessary to determine concentrations of radionuclides present in the tobacco leaves. In this paper specific activities of naturally occurring radionuclides were measured in tobacco samples from cigarettes which are used in Serbia. [sr

  1. Global risk from the atmospheric dispersion of radionuclides by nuclear power plant accidents in the coming decades

    Energy Technology Data Exchange (ETDEWEB)

    Christoudias, T.; Proestos, Y. [The Cyprus Institute, Nicosia (Cyprus); Lelieveld, J. [The Cyprus Institute, Nicosia (Cyprus); Max Planck Institute for Chemistry, Mainz (Germany)

    2014-07-01

    We estimate the global risk from the release and atmospheric dispersion of radionuclides from nuclear power plant accidents using the EMAC atmospheric chemistry-general circulation model. We included all nuclear reactors that are currently operational, under construction and planned or proposed. We implemented constant continuous emissions from each location in the model and simulated atmospheric transport and removal via dry and wet deposition processes over 20 years (2010-2030), driven by boundary conditions based on the IPCC A2 future emissions scenario. We present global overall and seasonal risk maps for potential surface layer concentrations and ground deposition of radionuclides, and estimate potential doses to humans from inhalation and ground-deposition exposures to radionuclides. We find that the risk of harmful doses due to inhalation is typically highest in the Northern Hemisphere during boreal winter, due to relatively shallow boundary layer development and limited mixing. Based on the continued operation of the current nuclear power plants, we calculate that the risk of radioactive contamination to the citizens of the USA will remain to be highest worldwide, followed by India and France. By including stations under construction and those that are planned and proposed, our results suggest that the risk will become highest in China, followed by India and the USA.

  2. Deposition, distribution and retention of inhaled /sup 239/PuO/sub 2/ in the lungs of rats with pulmonary emphysema

    Energy Technology Data Exchange (ETDEWEB)

    Lundgren, D L; Damon, E G; Diel, J H; Hahn, F F [Lovelace Foundation for Medical Education and Research, Albuquerque, NM (USA). Inhalation Toxicology Research Inst.

    1981-02-01

    Individuals with chronic obstructive lung disease, such as emphysema, may be more susceptible to injury from other inhaled pollutants. However, dose-response studies of inhaled radionuclides conducted to aid in estimating the biological effects of inhaled radionuclides in man have typically used healthy laboratory animals. Changes in radionuclide deposition, distribution and retention in the lungs as the result of pre-existing lung diseases could alter the radiation dose or the resulting biological effects. An experimental animal model for human emphysema, in which emphysema is induced by the intratracheal instillation of either elastase or papain, has been reviewed. This model was used to study the effects of pulmonary emphysema on the deposition, distribution and retention of inhaled /sup 239/PuO/sub 2/ in rats.

  3. Building shielding effects on radiation doses from routine radionuclide releases

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1977-01-01

    In calculating population doses from the release of radionuclides to the atmosphere, it is usually assumed that man spends all of his time outdoors standing on a smooth infinite plane. Realistically, however, man spends most of the time indoors, so that substantial reductions in radiation doses may result compared with the usual estimates. Calculational models were developed to study the effects of building structures on radiation doses from routine releases of radionuclides to the atmosphere. Both internal dose from inhaled radionuclides and external photon dose from airborne and surface-deposited radionuclides are considered. The effect of building structures is described quantitatively by a dose reduction factor, which is the ratio of the dose inside a structure to the corresponding dose with no structure present. The internal dose from inhaled radionuclides is proportional to the radionuclide concentration in the air. Assuming that the outdoor airborne concentration is constant with time, the time-dependence of the indoor airborne concentration in terms of the structure air ventilation rate, the deposition velocities for radionuclides on the inside floor, walls, and ceiling, and the radioactive decay constant, were calculated

  4. Examinations on the removal of natural radionuclides from drinking water and overview on their distribution in Austria

    International Nuclear Information System (INIS)

    Staubmann, K.

    2002-09-01

    The objective of the thesis was to give an overview about available data regarding natural radioactivity in Austrian ground and spring water and to examine the capability of membrane processes, ion exchange processes and processes for iron and manganese removal to remove natural radionuclides from drinking water. There are already Austrian-wide data existing for the activity concentrations of radon-222 in ground- and spring water, only few values are available for radium-226 (Ra-226), lead-210 (Pb-210), uranium (U) and polonium-210 up til now. From the existing data it is to be expected that in Austria only in exceptions water treatment will be necessary. The tested reverse osmosis and nanofiltration systems removed between 95.6 % and 99.8 % of Ra-226, U and Pb-210 on the average. Laboratory scale experiments for ion exchange showed an essential influence of the concurrent ions in the water on the removal of the radionuclides. With water softeners (cation exchangers) Ra-226 to more than 90 % and Pb to more than 80 % could be removed. By the use of other ones than the standard cartridge fillings for pour-through-filters (ion exchangers) the radionuclides could be removed more selectively and more effectively and the influence on the chemical composition of the water could be minimized. In a laboratory scale experiment simulating the planned treatment process at a waterwork for the removal of iron and manganese Ra-226 was removed to 61%. At the examined processes often disadvantageous side effects onto the water quality which require a subsequent treatment were observed. During the operation of the systems it should be aimed at keeping the activity in the produced waste low so that no radiation protection relevant risk starts from that. (author)

  5. Lifetime tumor risk coefficients for beagle dogs that inhaled cerium-144 chloride

    International Nuclear Information System (INIS)

    Boecker, B.B.; Hahn, F.F.; Griffith, W.C.

    1995-01-01

    Reported here is one of the life-span radionuclide toxicology studies being conducted at ITRI in Beagle dogs. These studies are examining the life-span health risks of inhaled Β-, γ- and α-emitting radionuclides to expand available knowledge on these risks especially for the many cases for which human data are not available. The outcomes of these studies are providing important information on dosimetry and dose-response relationships for these inhaled radionuclides and the relative importance of a broad range of dose- and effect-modifying factors. A number of these studies are currently coming to completion. Much of the ITRI effort is being directed to final reviews of the dosimetric, clinical, and pathologic results and writing summary manuscripts. Radiation doses and effects in tissues adjacent to bone, specifically those of epithelial or marrow origin, should be considered when determining risks from internally deposited, bone-seeking radionuclides such as 144 Ce

  6. Transfer of radionuclides to animal products following ingestion or inhalation

    International Nuclear Information System (INIS)

    Coughtrey, P.J.

    1996-01-01

    Contamination of animal products forms an important pathway in the transfer of radionuclides from source to man. Simulation of radionuclide transfer via animal products requires an understanding of the processes and mechanisms involved in absorption, distribution, turnover and excretion of radionuclides and related elements in animals as well as knowledge of animal grazing habits and husbandry. This paper provides a summary of the metabolism of important radionuclides in typical domestic animals and of the mathematical approaches that have been used to simulate transfer from diet to animal product. The equilibrium transfer factor approach has been used widely but suffers a number of disadvantages when releases or intakes are variable with time or when intakes are short relative to the lifetime of the animal of interest. Dynamic models, especially those of the compartmental type, have been developed and used widely. Both approaches have benefited from experiences obtained after the Chernobyl accident but a number of uncertainties still exist. Whereas there is now extensive knowledge on the behaviour of radiocaesium in both domestic and wild animals, knowledge of the behaviour of other potentially important radionuclides remains limited. Further experimental and metabolic studies will be required to reduce uncertainties associated with the transfer of radionuclides other than radiocaesium and thereby produce a sound basis for radiological assessments. (author)

  7. Removal of heavy metals and radionuclides by seeded magnetic filtration

    International Nuclear Information System (INIS)

    Bibler, J.P.; Norrell, G.; Hemmings, R.L.; Bradbury, D.; Dunn, M.J.; Kalinauskas, G.L.

    1991-01-01

    Removal of traces of heavy metal or radionuclide contamination from solution at high flow rate presents a considerable technical challenge. Low flow methods of treatment such as particle gravity settling require expensive large volume equipment, whereas traditional methods of filtration can cause significant energy costs. Magnetic filtration can be used to provide a low cost method of solid-liquid separation at high flow rate, provided contaminants can be selectively bound to a magnetic solid particle. This paper describes the use of such selective magnetic particles made up of inorganic particles coupled with organic polymers

  8. Lifetime health risks from internally deposited beta-emitting radionuclides

    International Nuclear Information System (INIS)

    Boecker, B.B.; Griffith, W.C.; Hahn, F.F.; Nikula, K.J.; Lundgren, D.L.; Muggenburg, B.A.

    1997-01-01

    Much of our knowledge on the lifetime health risks resulting from internal depositions of beta- and gamma-emitting radionuclides has come from studies in laboratory animals conducted to provide information not available from human epidemiological studies. This paper is focused primarily on results of experiments in which laboratory animals (dogs and rodents) were exposed once, briefly, by inhalation or intravenous injection to an individual fission-product radionuclide and were studied for radionuclide metabolism, dosimetry, and lifetime health effects. The relative importance of many dose- and effect-modifying factors was studied. The main long-term biological effects were cancers in the organs and tissues receiving the highest doses. Results for three different patterns of irradiation (skeleton, lung, and whole-body) are presented. The risks of bone cancers produced by 90 Sr are compared with those from 238 Pu in dogs. Lung cancer risks for several beta emitters inhaled in a relatively insoluble form by dogs are compared with results for 144 CeO 2 inhaled by rats. Late-occurring biological effects from the relatively uniform whole-body irradiation from intravenously injected 137 Cs are also presented. In addition to radionuclide-specific results, cross-cutting analyses of these studies provide valuable information on broader issues such as dose protraction, relative biological effectiveness, threshold considerations, and inter-species comparisons including extrapolation to human exposure situations. (authors)

  9. Inhalation dose assessment for Maralinga and Emu

    International Nuclear Information System (INIS)

    Johnston, P.N.; Lokan, K.H.; Williams, G.A.

    1990-01-01

    Dose assessments for the inhalation of artificial radionuclides are presented for all types of contaminated areas at Maralinga and Emu. These enable Committed Effective Dose Equivalent (CEDE), to be estimated by scaling at any area of interest where activity concentrations are known. In the case of Aborigines, these dose are estimated assuming respirable dust loadings of 1 mg/m 3 for adults and 1.5 mg/m 3 for children and infants. Details of the calculations are presented in the appendix. The model of the respiratory system used in this assessment is that described in Interantional Commission on Radiological Protection (ICRP) Publication 30 (ICRP, 1979a). With the exception of Kuli, which is contaminated with uranium, at all other sites it is only the inhalation of plutonium and americium that contributes significantly to the dose, and of these 239 Pu is the largest contributor. Therefore, considering the long half lives of the radionuclides concerned, it appears that the inhalation problems highlighted by this dose assessment will not diminish significantly within any reasonable period of time and hence management strategies must be developed to deal with such problems. 32 refs., 5 tabs., 1 fig

  10. Lifetime tumor risk coefficients for beagle dogs that inhaled cerium-144 chloride

    Energy Technology Data Exchange (ETDEWEB)

    Boecker, B.B.; Hahn, F.F.; Griffith, W.C. [and others

    1995-12-01

    Reported here is one of the life-span radionuclide toxicology studies being conducted at ITRI in Beagle dogs. These studies are examining the life-span health risks of inhaled {Beta}-, {gamma}- and {alpha}-emitting radionuclides to expand available knowledge on these risks especially for the many cases for which human data are not available. The outcomes of these studies are providing important information on dosimetry and dose-response relationships for these inhaled radionuclides and the relative importance of a broad range of dose- and effect-modifying factors. A number of these studies are currently coming to completion. Much of the ITRI effort is being directed to final reviews of the dosimetric, clinical, and pathologic results and writing summary manuscripts. Radiation doses and effects in tissues adjacent to bone, specifically those of epithelial or marrow origin, should be considered when determining risks from internally deposited, bone-seeking radionuclides such as {sup 144}Ce.

  11. Inhalation Toxicology Research Institute. Annual report, October 1, 1981-September 30, 1982

    International Nuclear Information System (INIS)

    Snipes, M.B.; Marshall, T.C.; Martinez, B.S.

    1982-12-01

    Studies are presented of the effect on man of airborne particulates and gaseous emissions associated with the production of energy. Included in the report from the Inhalation Toxicology Research Institute are papers on: (1) the physical and chemical characterization of energy technology aerosols; (2) laboratory studies of aerosol generation and characterization; (3) in vitro predictors of toxicity; (4) disposition and fate of inhaled materials; (5) dose-response relationships for inhaled radionuclides; (6) dose-response relationships for inhaled chemical toxicants; (7) biological factors which influence dose-response relationships; and (8) risk assessment

  12. Biological effects of inhaled 144CeCl3 in beagle dogs

    International Nuclear Information System (INIS)

    Hahn, F.F.; Boecker, B.B.; Griffith, W.C.; Muggenburg, B.A.

    1997-01-01

    Data on biological effects in humans exposed briefly to high levels of external X or gamma irradiation provide the foundation of protection guidelines for low linear energy transfer (LET) radiation. Unfortunately, the extrapolation of the risk of these biological effects to humans exposed to internally deposited radionuclides is complicated by the protracted exposure and differences in local doses to organs and tissues that result from internal irradiation. Therefore, data from humans exposed to external radiation may not provide all of the information necessary to understand the long-term health effects of internally deposited, beta-particle-emitting radionuclides. Because of these uncertainties, it is important to determine the spatial and temporal distribution of radionuclides such as radiocerium in the body and the relationship of their distribution to biological effects that result from acute inhalation exposure. The radiation effects of inhaled cerium 144 were studied in beagles

  13. Physico-chemical forms of natural radionuclides in drilled well waters and their removal by ion exchange

    International Nuclear Information System (INIS)

    Vaaramaa, K.

    2003-01-01

    Appreciable concentrations of natural uranium and its daughter radionuclides may occur in drinking water obtained from drilled wells when the bedrock contains these nuclides. Effective methods are needed to remove these radionuclides. A wide range of ion exchange materials, both organic and inorganic, were evaluated for the removal of 234,238 U, 226 Ra, 210 Po and 210 Pb from ground waters. Screenin tests were carried out, in which distribution coefficients (KD) were determined for the ion exchangers. The ion exchangers that gave the highest KD's were tested in column-mode experiments for the removal of the radionuclides from drilled well water. The most efficient exchanger for the removal of U from neutral and slightly alkaline waters was the strong base anion resin. The chelating aminophosphonate resin removed uranium very efficiently from slightly acidic water. As well, it was an efficient exchanger for the removal of toxic and harmful transition metals from drilled well waters. The strong and weak acid cation resins and zeolite A removed radium most efficiently. Large fractions of the total activity of polonium and lead were found to adsorb on equipment in the ion exchange studies. In investigation of this, the well waters were filtered through membranes to determine the soluble and particle-bound forms of 234,238 U, 226 Ra, 210 Po and 210 Pb. Eight of the waters were of Ca type and two were of Na-Cl type. Some of the waters also had high concentrations of Fe, Mn and humic substances. Uranium was present entirely in soluble form, probably as uranyl ion in soluble carbonate complexes. 226 Ra was in soluble form in the waters with low concentrations of Fe and Mn, but 10% of the total radium activity was bound to particles in Fe-Mn-rich waters. The speciation of Po is complex in natural waters; polonium was present in both soluble and particle-bound forms. A correlation was observed between the fractions of particle-bound 210 Po and the concentrations of iron in

  14. Permissible annual depositions and radionuclide concentrations in air

    International Nuclear Information System (INIS)

    Belyaev, V.A.; Golovko, M.Yu.

    1993-01-01

    It is established that it necessary to take into account the other ways of radionuclide intake apart from the inhalation one when determining the standards for radionuclide contamination of the atmospheric air. Whereby it is proposed to standardize annual depositions rather than permissible concentration in the atmospheric air for the ways related to radionuclide releases on the ground surface, which is explained by ambiguity of their dry deposition rate from the air. Formulae and results of calculation of standard characteristics are presented. The permissible radionuclide depositions, related to the intake through food chains are calculated with account for diet diversity, agroclimatic and phenological parameters in different regions of the country

  15. Effects of building structures on radiation doses from routine releases of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1978-01-01

    Realistic assessments of radiation doses to the population from routine releases of radionuclides to the atmosphere require consideration of man's largely indoor environment. The effect of a building structure on radiation doses is described quantitatively by a dose reduction factor, which is the ratio of the dose to a reference individual inside a structure to the corresponding dose with no structure present. We have implemented models to estimate dose reduction factors for internal dose from inhaled radionuclides and for external photon dose from airborne and surface-deposited radionuclides. The models are particularly useful in radiological assessment applications, since dose reduction factors may readily be estimated for arbitrary mixtures and concentrations of radionuclides in the atmosphere and on the ground. The model for inhalation dose reduction factors accounts for radioactive decay, air ventilation into and out of the structure, and deposition of radionuclides on inside surfaces of the structure. External dose reduction factors are estimated using the point-kernel integration method including consideration of buildup in air and the walls of the building. The potential importance of deposition of radionuclides on inside surfaces of a structure on both inhalation and external dose reduction factors has been demonstrated. Model formulation and the assumptions used in the calculations are discussed. Results of model-parameter sensitivity studies and estimates of dose reduction factors for radionuclides occurring in routine releases from an LWR fuel reprocessing plant are presented. (author)

  16. Hot beta particles in the lung: Results from dogs exposed to fission product radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, F.F.; Griffith, W.C.; Hobbs, C.H. [and others

    1995-12-01

    The Chernobyl nuclear reactor accident resulted in the release of uranium dioxide fuel and fission product radionuclides into the environment with the fallout of respirable, highly radioactive particles that have been termed {open_quotes}hot beta particles.{close_quotes} There is concern that these hot beta particles (containing an average of 150-20,000 Bq/particle), when inhaled and deposited in the lung, may present an extraordinary hazard for the induction of lung cancer. We reviewed data from a group of studies in dogs exposed to different quantities of beta-emitting radionuclides with varied physical half-lives to determine if those that inhaled hot beta particles were at unusual risk for lung cancer. This analysis indicates that the average dose to the lung is adequate to predict biologic effects of lung cancer for inhaled beta-emitting radionuclides in the range of 5-50 Gy to the lung and with particle activities in the range of 0.10-50 Bq/particle.

  17. Inhaled transuranics in rodents

    International Nuclear Information System (INIS)

    Sanders, C.L.

    1983-01-01

    This project examines the interactions of external and internal radiation from mixtures of radionuclides present within the nuclear fuel inventory. The objective of the project is to evaluate the effects of mixed radiation insults, using key radiation sources as indicative of overall processes that may occur following release of nuclear fuel into the air. Previously initiated studies of immunological effects of plutonium inhalation are also being completed as part of this project

  18. Therapy for incorporated radionuclides: scope and need

    International Nuclear Information System (INIS)

    Smith, V.H.

    1981-03-01

    In the United States the recent termination of funding for research on therapy for incorporated radionuclides has virtually halted progress on improved or new agents and procedures for removing radioactivity from the body. Research was eliminated, but is still needed on new removal agents, improved delivery system, in vitro test systems, and the toxicology of treatments. For many radionuclides, no adequate therapy exists. The relationship between radionuclide removal and reduction in cancer risk is still unanswered. Without proper research support, needed improvements in the treatment for incorporated radionuclides in the US are uncertain

  19. Life-span health effects of relatively soluble forms of internally deposited beta-emitting radionuclides

    International Nuclear Information System (INIS)

    Boecker, B.B.; Muggenburg, B.A.; Hahn, F.F.; Nikula, K.J.; Griffith, W.C.

    1991-01-01

    As part of a large research effort to study the lifetime health risks of inhaled radionuclides, Beagle dogs inhaled 90 SrCl 2 or 144 CeCl 3 or were injected intravenously with 137 CsCl. Because these three compounds were soluble in body fluids, the resulting widely differing patterns of radionuclide distribution and dose reflected tissue affinities of the elements involved. Long-term health effects, predominantly cancers, were seen in the organs receiving the highest doses. Investigations are continuing on the extent to which other less irradiated organs may have also been affected

  20. Method of separating short half-life radionuclides from a mixture of radionuclides

    Science.gov (United States)

    Bray, L.A.; Ryan, J.L.

    1999-03-23

    The present invention is a method of removing an impurity of plutonium, lead or a combination thereof from a mixture of radionuclides that contains the impurity and at least one parent radionuclide. The method has the steps of (a) insuring that the mixture is a hydrochloric acid mixture; (b) oxidizing the acidic mixture and specifically oxidizing the impurity to its highest oxidation state; and (c) passing the oxidized mixture through a chloride form anion exchange column whereupon the oxidized impurity absorbs to the chloride form anion exchange column and the {sup 229}Th or {sup 227}Ac ``cow`` radionuclide passes through the chloride form anion exchange column. The plutonium is removed for the purpose of obtaining other alpha emitting radionuclides in a highly purified form suitable for medical therapy. In addition to plutonium, lead, iron, cobalt, copper, uranium, and other metallic cations that form chloride anionic complexes that may be present in the mixture are removed from the mixture on the chloride form anion exchange column. 8 figs.

  1. User's guide to the radionuclide inventory and hazard code INVENT

    International Nuclear Information System (INIS)

    Nancarrow, D.J.; Thorne, M.C.

    1986-05-01

    This report constitutes the user's guide to the radionuclide inventory and hazard index code INVENT and provides an explanation of the mathematical basis of the code, the database used and operation of the code. INVENT was designed to facilitate the post-closure radiological assessment of land-based repositories for low and intermediate-level wastes. For those radionuclides identified to be of potential significance, it allows the calculation of time-dependent radionuclide activities, hazard indices for both inhalation and ingestion of activity, and photon spectra. (author)

  2. Transfer of radionuclides into human milk

    International Nuclear Information System (INIS)

    Steiner, M.; Wirth, E.

    1998-01-01

    Up until now the potential radiation exposure to breast-fed babies due to contaminated human milk has not been taken into account, when deriving international limit values and reference levels for radionuclides in foodstuffs, in air at monitored work places or for exposures in the medical field. It was the aim of the research project 'Transfer of radionuclides into human milk' to quantify the transfer of incorporated radionuclides into mother's milk, and develop simple models to estimate the radiation exposure of babies through the ingestion of human milk. The study focused on considerations of the radiation exposure due to the ingestion of contaminated foodstuffs by the mother, the inhalation of radionuclides at monitored work places, and the administration of radiopharmaceuticals to breast-feeding mothers. The blocking of infant thyroid glands by stable iodine in the case of accidental releases of radioiodine was considered as well. (orig.) [de

  3. The application of polyelectrolytes to improve liquid radwaste treatment system radionuclide removal efficiency

    International Nuclear Information System (INIS)

    Homyk, W.A.; Spall, M.J.; Vance, J.N.

    1990-01-01

    At nuclear plants, miscellaneous waste water treated in the liquid radwaste processing system contains a significant fraction of suspended particulate materials ranging in size from a few microns down to the submicron region. The fewer particles that typically exist as colloids are generally negatively charged by virtue of inorganic and organic anions absorbed onto the particle surfaces. Because many of the radionuclides exist as colloids and resist agglomeration and settling they are not easily removed by mechanical filtration or ion exchange processes. The colloidal materials will easily pass through most filters with conventional pore size ratings and through most ion exchange media. This leads to poor decontamination Factors (dFs) and higher radionuclide releases to the environment. A laboratory-scale testing program was conducted at Indian Point Unit No. 2 to determine the effectiveness of the use of organic polyelectrolytes to destabilize colloidal suspensions in liquid radwaste. Destabilizing colloidal suspensions will improve the removal efficiencies of the suspended material by typical filtration and ion exchange processes. The increased removal efficiencies will provide increased dFs in the liquid radwaste treatment system. The testing focused on identifying the specific organic polyelectrolytes and the associated dosages which would be effective in destabilizing the colloidal suspensions on actual waste water samples. The testing also examined the filtration characteristics of the water source to determine filter parameters such as: body feed material, body feed dosages, specific flow rates, etc., which would provide the basis for the design of filtration systems for these applications. The testing effort and the major conclusions from this investigation are given. 4 refs., 8 figs., 2 tabs

  4. Removal of radionuclides by reverse osmosis using a cellulose acetate membrane, (2)

    International Nuclear Information System (INIS)

    Nishimaki, Kenzo; Koyama, Akio; Saji, Minoru; Tutui, Tenson.

    1990-01-01

    Experiments were performed on the removal of radionuclides from radioactive liquid waste by reverse osmosis using asymmetric cellulose acetate membranes. In previous papers, we reported such removal properties as the dependence on solute concentration and the influence of co-existing material. In this paper we performed experiments on some separation properties, especially on the formation and the disappearance of concentration polarization layer of membrane surface. These experiments are necessary for the theoretical explanation of findings shown in previous papers. Concentration polarization layer is formed on the surface of the membrane, when pressurized feed solution is not stirred during reverse osmosis operation. This layer grows with elapsed time and reaches the equilibrium. The thickness of this concentration polarization layer and solute concentrations in this layer are calculated by a simple model. The formation and disappearance of this layer are experimented with intermittent stirring. The influence of intensity of stirring on the formation of concentration polarization layer is observed. These are important information on property of membrane for removing solute by reverse osmosis. (author)

  5. Distribution of natural radionuclide in soil of Ukhimath region of Garhwali Himalaya and its radiological implications

    International Nuclear Information System (INIS)

    Yadav, Manjulata; Rawat, Mukesh; Prasad, Mukesh; Dangwal, Anoop; Gusain, G.S.; Ramola, R.C.

    2014-01-01

    The naturally occurring radionuclides present in soil include 226 Ra, 232 Th and 40 K some of these radionuclides are transferred to man through food chain or inhalations, while the extraterrestrial radiation originate from outer space as primary cosmic rays. External exposure will occur as a result of irradiation, and internal exposure will occurs as result of inhalation. Therefore, the assessment of gamma radiations dose from natural sources is of particular importance as natural radiation is the largest contributor to the external dose of world population

  6. Inhalation Toxicology Research Institute annual report, October 1, 1982-September 30, 1983

    International Nuclear Information System (INIS)

    1983-12-01

    The mission of the Inhalation Toxicology Research Institute (ITRI) is to investigate the nature and magnitude of human health effects that might result from inhalation of airborne materials encountered in the work place, special attention is directed toward airborne particulate and gaseous emissions released by various energy technologies or from national defense activities. Included are five papers on the physical and chemical characterization of energy technology aerosols, 10 papers on laboratory studies of aerosol generation and characterization, 11 papers on in vitro predictors of toxicity, 12 papers on disposition and fate of inhaled materials, 24 papers on dose-response relationships for inhaled radionuclides, 3 papers on dose-response relationships for inhaled chemical toxicants, 8 papers on biological factors that influence dose-response relationships, and 4 papers are concerned with risk assessment

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

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Boecker, B.B.; Hahn, F.F.; McClellan, R.O.

    1990-01-01

    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

  8. Naturally occurring radionuclides in food

    International Nuclear Information System (INIS)

    Djujic, I.

    1995-01-01

    The naturally occurring radionuclides are the major source of radiation exposure to humans. The principal way of natural radiation exposure is the inhalation of 222 Rn decay products (about 85% of the total). The remainder is equally divided between internally deposited radionuclides, cosmic and terrestrial sources. In the present study, the content of 40 K, 210 Pb, 226 Ra, 230 Th, 232 Th and 238 U in representative food samples (milk, pork, beef, potatoes, wheat and corn flour) and samples of different food items that do not represent entire national production but provide interesting additional data for approximative calculation of naturally occurring radionuclide intake is presented. Daily weight of food eaten, participation of food groups, as well as daily intake by food of mentioned naturally occurring radionuclides in the Serbian diet was obtained on the base of house hold budget surveys. The result obtained for daily intake estimates in mBq for Serbian population are 78.1 ( 40 K), 38.2( 210 Pb), 52.3( 226 Ra), 2.0( 230 Th) and 12.5( 238 U). (author)

  9. Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126

    Energy Technology Data Exchange (ETDEWEB)

    Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke [Hitachi Research Laboratory, Hitachi, Ltd., 7-2-1 Omika-cho, Hitachi, Ibaraki, 319-1221 (Japan); Asano, Takashi; Tamata, Shin [Hitachi Works, Hitachi-GE Nuclear Energy, Ltd. (Japan)

    2013-07-01

    Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K{sub d}s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K{sub d}s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K{sub d}s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K{sub d}s and it

  10. Removal of Radionuclides from Waste Water at Fukushima Daiichi Nuclear Power Plant: Desalination and Adsorption Methods - 13126

    International Nuclear Information System (INIS)

    Kani, Yuko; Kamosida, Mamoru; Watanabe, Daisuke; Asano, Takashi; Tamata, Shin

    2013-01-01

    Waste water containing high levels of radionuclides due to the Fukushima Daiichi Nuclear Power Plant accident, has been treated by the adsorption removal and reverse-osmosis (RO) desalination to allow water re-use for cooling the reactors. Radionuclides in the waste water are collected in the adsorbent medium and the RO concentrate (RO brine) in the water treatment system currently operated at the Fukushima Daiichi site. In this paper, we have studied the behavior of radionuclides in the presently applied RO desalination system and the removal of radionuclides in possible additional adsorption systems for the Fukushima Daiichi waste water treatment. Regarding the RO desalination system, decontamination factors (DFs) of the elements present in the waste water were obtained by lab-scale testing using an RO unit and simulated waste water with non-radioactive elements. The results of the lab-scale testing using representative elements showed that the DF for each element depended on its hydrated ionic radius: the larger the hydrated ionic radius of the element, the higher its DF is. Thus, the DF of each element in the waste water could be estimated based on its hydrated ionic radius. For the adsorption system to remove radionuclides more effectively, we studied adsorption behavior of typical elements, such as radioactive cesium and strontium, by various kinds of adsorbents using batch and column testing. We used batch testing to measure distribution coefficients (K d s) for cesium and strontium onto adsorbents under different brine concentrations that simulated waste water conditions at the Fukushima Daiichi site. For cesium adsorbents, K d s with different dependency on the brine concentration were observed based on the mechanism of cesium adsorption. As for strontium, K d s decreased as the brine concentration increased for any adsorbents which adsorbed strontium by intercalation and by ion exchange. The adsorbent titanium oxide had higher K d s and it was used for

  11. Pirbuterol Acetate Oral Inhalation

    Science.gov (United States)

    ... Pirbuterol is in a class of medications called beta-agonist bronchodilators. It works by relaxing and opening ... cleaning. Once a week, remove the mouthpiece cover, turn the inhaler upside down and wipe the mouthpiece ...

  12. Comparison of the effects of inhaled 239PuO2 and β- emitting radionuclides on the incidence of lung carcinomas in laboratory animals

    International Nuclear Information System (INIS)

    Hahn, F.F.; Griffith, W.C.; Boecker, B.B.; Muggenburg, B.A.; Lundgren, D.L.

    1991-01-01

    The health effects of inhaling radioactive particles when the lung is the primary organ irradiated were studied in rats and Beagle dogs. The animals were exposed to aerosols of 239 PuO 2 or fission-product radionuclides in insoluble forms and observed for their life span. Lung carcinomas were the primary late-occuring effect. The incidence rate for lung carcinomas was modeled using a proportional hazard rate model. Linear functions predominated below 5 Gy to the lung. The life-time risk for lung carcinomas per 10 4 Gy for beta emitters was 60 for rats and 65 for dogs, and for 239 PuO 2 it was 1500 for rats and 2300 for dogs

  13. Comparison of the effects of inhaled 239PuO2 and β-emitting radionuclides of the incidence of lung carcinomas in laboratory animals

    International Nuclear Information System (INIS)

    Hahn, F.F.; Griffith, W.C.; Boecker, B.B.; Muggenburg, B.A.; Lundgren, D.L.

    1992-01-01

    The health effects of inhaling radioactive particles when the lung is the primary organ irradiated were studied in rats and dogs. The animals were exposed to aerosols of 239 PuO 2 or fission-product radionuclides in insoluble forms and observed for their life span. Lung carcinomas were the primary late-occurring effect. The incidence rate for lung carcinomas was modeled using a proportional hazard rate model. Linear functions predominated below 5 Gy to the lung. The life-time risk for lung carcinomas per 10 4 Gy for beta emitters was 60 for rats and 65 for dogs, and for 239 PuO 2 it was 1500 for rats and 2300 for dogs. (author)

  14. Removal and recovery of radionuclides and toxic metals from wastes, soils and materials

    International Nuclear Information System (INIS)

    Francis, A.J.

    1993-07-01

    A process has been developed at Brookhaven National Laboratory (BNL) for the removal of metals and radionuclides from contaminated materials, soils, and waste sites (Figure 1). In this process, citric acid, a naturally occurring organic complexing agent, is used to extract metals such as Ba, Cd, Cr, Ni, Zn, and radionuclides Co, Sr, Th, and U from solid wastes by formation of water soluble, metal-citrate complexes. Citric acid forms different types of complexes with the transition metals and actinides, and may involve formation of a bidentate, tridentate, binuclear, or polynuclear complex species. The extract containing radionuclide/metal complex is then subjected to microbiological degradation followed by photochemical degradation under aerobic conditions. Several metal citrate complexes are biodegraded and the metals are recovered in a concentrated form with the bacterial biomass. Uranium forms binuclear complex with citric acid and is not biodegraded. The supernatant containing uranium citrate complex is separated and upon exposure to light, undergoes rapid degradation resulting in the formation of an insoluble, stable polymeric form of uranium. Uranium is recovered as a precipitate (uranium trioxide) in a concentrated form for recycling or for appropriate disposal. This treatment process, unlike others which use caustic reagents, does not create additional hazardous wastes for disposal and causes little damage to soil which can then be returned to normal use

  15. Removal of radionuclides from partitioning waste solutions by adsorption and catalytic oxidation methods

    Energy Technology Data Exchange (ETDEWEB)

    Yamagishi, Isao; Yamaguchi, Isoo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Kubota, Masumitsu [Research Organization for Information Science and Technology (RIST), Tokai, Ibaraki (Japan)

    2000-09-01

    Adsorption of radionuclides with inorganic ion exchangers and catalytic oxidation of a complexant were studied for the decontamination of waste solutions generated in past partitioning tests with high-level liquid waste. Granulated ferrocyanide and titanic acid were used for adsorption of Cs and Sr, respectively, from an alkaline solution resulting from direct neutralization of an acidic waste solution. Both Na and Ba inhibited adsorption of Sr but Na did not that of Cs. These exchangers adsorbed Cs and Sr at low concentration with distribution coefficients of more than 10{sup 4}ml/g from 2M Na solution of pH11. Overall decontamination factors (DFs) of Cs and total {beta} nuclides exceeded 10{sup 5} and 10{sup 3}, respectively, at the neutralization-adsorption step of actual waste solutions free from a complexant. The DF of total {alpha} nuclides was less than 10{sup 3} for a waste solution containing diethylenetriaminepentaacetic acid (DTPA). DTPA was rapidly oxidized by nitric acid in the presence of a platinum catalyst, and radionuclides were removed as precipitates by neutralization of the resultant solution. The DF of {alpha} nuclides increased to 8x10{sup 4} by addition of the oxidation step. The DFs of Sb and Co were quite low through the adsorption step. A synthesized Ti-base exchanger (PTC) could remove Sb with the DF of more than 4x10{sup 3}. (author)

  16. Radiation exposure by man-modified materials containing natural radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Becker, D.E. [Technical Inspection Agency of Bavaria, Munich (Germany); Eder, E. [Government of Bavaria, Ministry for State Development and Environmental Affairs Development, Munich (Germany); Reichelt, A. [Technical Inspection Agency of Bavaria, Munich (Germany)

    1992-07-01

    More than one hundred materials, containing natural radioactive nuclides, are being investigated due to radiation exposure to people. This paper deals with thoriated gas mantles and shows that the radiation exposure by inhalation of radionuclides released while burning and exchange is not negligible. (author)

  17. Inhalation Exposure Input Parameters for the Biosphere Model

    Energy Technology Data Exchange (ETDEWEB)

    K. Rautenstrauch

    2004-09-10

    This analysis is one of 10 reports that support the Environmental Radiation Model for Yucca Mountain, Nevada (ERMYN) biosphere model. The ''Biosphere Model Report'' (BSC 2004 [DIRS 169460]) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents development of input parameters for the biosphere model that are related to atmospheric mass loading and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the total system performance assessment (TSPA) for a Yucca Mountain repository. Inhalation Exposure Input Parameters for the Biosphere Model is one of five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the ERMYN is presented in Figure 1-1. This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling, and the plan for development of the biosphere abstraction products for TSPA, as identified in the Technical Work Plan for Biosphere Modeling and Expert Support (BSC 2004 [DIRS 169573]). This analysis report defines and justifies values of mass loading for the biosphere model. Mass loading is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Mass loading values are used in the air submodel of ERMYN to calculate concentrations of radionuclides in air inhaled by a receptor and concentrations in air surrounding crops. Concentrations in air to which the receptor is exposed are then used in the inhalation submodel to calculate the dose contribution to the receptor from inhalation of contaminated airborne particles. Concentrations in air surrounding plants are used in the plant submodel to calculate the concentrations of radionuclides in foodstuffs contributed from uptake by foliar interception.

  18. Inhalation Exposure Input Parameters for the Biosphere Model

    International Nuclear Information System (INIS)

    K. Rautenstrauch

    2004-01-01

    This analysis is one of 10 reports that support the Environmental Radiation Model for Yucca Mountain, Nevada (ERMYN) biosphere model. The ''Biosphere Model Report'' (BSC 2004 [DIRS 169460]) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents development of input parameters for the biosphere model that are related to atmospheric mass loading and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the total system performance assessment (TSPA) for a Yucca Mountain repository. Inhalation Exposure Input Parameters for the Biosphere Model is one of five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the ERMYN is presented in Figure 1-1. This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling, and the plan for development of the biosphere abstraction products for TSPA, as identified in the Technical Work Plan for Biosphere Modeling and Expert Support (BSC 2004 [DIRS 169573]). This analysis report defines and justifies values of mass loading for the biosphere model. Mass loading is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Mass loading values are used in the air submodel of ERMYN to calculate concentrations of radionuclides in air inhaled by a receptor and concentrations in air surrounding crops. Concentrations in air to which the receptor is exposed are then used in the inhalation submodel to calculate the dose contribution to the receptor from inhalation of contaminated airborne particles. Concentrations in air surrounding plants are used in the plant submodel to calculate the concentrations of radionuclides in foodstuffs contributed from uptake by foliar interception

  19. The removal of inhaled 239Pu and 238Pu from beagle dogs by lung lavage and chelation treatment

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Miglio, J.J.; Slauson, D.O.; McClellan, R.O.

    1976-01-01

    Studies were conducted in beagle dogs to determine the efficiency of treatment by lung lavage and injections of chelating agents in removing inhaled plutonium of varied chemical forms and particle sizes. Polydisperse aerosols of 239 Pu were produced at different temperatures from 325 0 C to 1150 0 C to evaluate the effect of the chemical form of the particles. Aerosols of 238 Pu were produced at 1150 0 C only but were of different particle size or size distributions. Three dogs that inhaled each different plutonium aerosol were treated by lung lavages starting two days after the exposure. Subsequent lavages were performed on days 7, 10, 14, 21, 28, 35, 42, and 49 after exposure. Intravenous injections of 100 mg of diethylenetriaminepentaacetic acid (DTPA) as the calcium salt were given on days 1, 2, 3 and 4 after exposure and twice weekly thereafter to the time of sacrifice, 56 days after exposure. The 10 lung lavages removed from 18 to 49% of the initial lung burden of plutonium. The recovery of plutonium by lavage was similar irrespective of the temperature at which the aerosol was produced, however, lavage recovery decreased somewhat with increasing particle size. The efficacy of DTPA treatment increased with decreasing production temperature of the 239 Pu. Treatment with DTPA was not affected by particle size of the 0.8- and 1.9-μm monodisperse 239 Pu aerosol. The effectiveness of lung lavage decreased as the solubility of the aerosol particles increased whereas the effectiveness of the DTPA treatment increased as the solubility of the inhaled aerosol increased as shown by the lowest temperature aerosol and the aerosol-containing soluble fraction. These findings correlated qualitatively with a 2-hour in-vitro solubility test on the exposure aerosols. (author)

  20. Natural radionuclides from the coal in atmospheric environment of the coal fired power plants

    International Nuclear Information System (INIS)

    Antic, D.; Kostic-Soskic, M.; Milovanovic, S.; Telenta, B.

    1995-01-01

    The inhalation radiation exposure of the public in the vicinity of the selected coal fired power plants near from Belgrade (30-50 km) has been studied, using a set of data for natural radionuclides from the analysed power plants. A generalised model for analysis of radiological impact of an energy source, that includes the two-dimensional version of the cloud model, has been used for simulation of the transport of radionuclides released to the atmosphere. The inhalation dose rates for an adult are assessed and analysed during fast changeable meteorological conditions. A set of realistic meteorological conditions (wind, radiosonde sounding temperature, pressure, and humidity data) has been used for the numerical simulations. (author)

  1. Removal of radionuclides from household water; Metoder foer avlaegsnande av radionuklider fraan hushaallsvatten

    Energy Technology Data Exchange (ETDEWEB)

    Vesterbacka, P.; Turtiainen, T.; Haemaelaeinen, K.; Salonen, L.; Arvela, H.

    2007-02-15

    Research upon methods for removing radionuclides from household water was initiated in Finland in 1995. Three research projects, of which two were carried out with National Technology Agency of Finland and one with CEC, have been completed by the end of 2002. One of the main objectives of the research was to compose a guidebook for consumers and water treatment companies. Radon can be removed from household water by aeration and by activated carbon filtration. Aerators that are well designed and set up can remove over 90% of waterborne radon. The best aerators have achieved removal efficiencies that are nearly 100%. However, setting up an aeration system requires thorough planning. Also, activated carbon filtration removes radon efficiently. The removal efficiencies have been over 90%, often nearly 100%. Depending on the water quality and usage, the carbon batch inside the filter needs to be changed every 2 - 3 years. Since activated carbon filters emit gamma radiation while in use, they should not be installed inside the dwelling but in a separate building or by the well. It is recommended that uranium be removed from drinking water by anion exchange, which is the most efficient removal method for this purpose. Typically, the removal efficiencies are nearly 100%. The one exception is the so called tap filter, the removal efficiency of which depends on uranium concentration in raw water and the rate of water flow. High saline concentration in water may extricate uranium from ion exchange resin. Changes in plumbing pressure or pH-value do not have any significant influence in uranium retention. Removal efficiencies of lead and polonium vary a lot depending on the chemical form in which they occur in water. They can be reliably removed from water by reverse osmosis only. Other treatment methods, such as ion exchange and activated carbon filtration, remove lead and polonium partly. Lead and polonium are removed more efficiently when they are bound onto smaller

  2. Composite materials based on inorganic sorbents and extractants - new sorbents for several radionuclides removal from liquid radioactive wastes

    International Nuclear Information System (INIS)

    Kopyrin, A.A.

    1999-01-01

    A short review of recent investigation concerned with liquid radioactive waste treatment by means of composite materials. It is considered different aspects of technology of selective radionuclides removal and its direction connected with usage of composites. Results of research works in this line carried out under the direction of author are presented. (author)

  3. Generator for radionuclide

    International Nuclear Information System (INIS)

    Weisner, P.S.; Forrest, T.R.F.

    1985-01-01

    This invention provides a radionuclide generator of the kind in which a parent radionuclide, adsorbed on a column of particulate material, generates a daughter radionuclide which is periodically removed from the column. This invention is particularly concerned with technetium generators using single collection vials. The generator comprises a column, a first reservoir for the eluent, a second reservoir to contain the volume of eluent required for a single elution, and means connecting the first reservoir to the second reservoir and the second reservoir to the column. Such a generator is particularly suitable for operation by vacuum elution

  4. Inhalation of sevoflurane in the removal of post-labioplasty and palatoplasty stitches in uncooperative children patients

    Directory of Open Access Journals (Sweden)

    Ediyana Nuryadi

    2007-11-01

    Full Text Available The technique of behaviour management in medical treatment, especially in dental treatment, is needed to eliminate uncooperative children behaviour. The main factor influencing children behaviour is fear of painful that usually related to dental treatment. Children patients who will have their post­labioplasty and palatoplasty stitches removed have more sensitive condition, they cry when the dentist gives treatment. Using general anesthesia is a method to manage uncooperative children behaviour. Inhalational anesthesia is often used in general anesthesia and sevoflurane is a drug of choice. Sevoflurane has low solubility in blood, pleasant odor, nonirritating airway, and has a rapid induction of and recovery from anesthesia. Some researches indicate that sevoflurane gives more calm condition and can be used as a sufficiently ideal induction and maintenance of anesthesia in children. Sevoflurane can therefore made as alternative procedure in the removal of post-labioplasty and palatoplasty stitches.

  5. Other impacts of soil-borne radionuclides

    International Nuclear Information System (INIS)

    Sheppard, S.C.; Macdonald, C.R.

    1996-01-01

    Soils surround us daily, and humans and animals are exposed to soil in more ways than simply through ingestion of plants. Despite strict personal and food-industry hygiene, some soil will always be present in our diet. This often involves the very fine soil particles known to be especially effective in sorbing radionuclides. The soil we ingest may come through skin contact or through soil adhering to crop plants and other foods. Inhalation of soil particles by humans and other animals must also be considered. Throughout the consideration of the impacts of soil-borne radionuclides, there must be recognition of potential impacts on non-human biota, and of non-radiological impacts. The chemical toxicity of long-lived radionuclides may be just as important as their radiological impact for non-human biota. These issues and associated assessment modelling approaches are discussed, with examples and data drawn from our research programs. (J.P.N.)

  6. Inhalation Exposure Input Parameters for the Biosphere Model

    Energy Technology Data Exchange (ETDEWEB)

    M. Wasiolek

    2006-06-05

    This analysis is one of the technical reports that support the Environmental Radiation Model for Yucca Mountain, Nevada (ERMYN), referred to in this report as the biosphere model. ''Biosphere Model Report'' (BSC 2004 [DIRS 169460]) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents development of input parameters for the biosphere model that are related to atmospheric mass loading and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the total system performance assessment (TSPA) for a Yucca Mountain repository. ''Inhalation Exposure Input Parameters for the Biosphere Model'' is one of five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the biosphere model is presented in Figure 1-1 (based on BSC 2006 [DIRS 176938]). This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling and how this analysis report contributes to biosphere modeling. This analysis report defines and justifies values of atmospheric mass loading for the biosphere model. Mass loading is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Mass loading values are used in the air submodel of the biosphere model to calculate concentrations of radionuclides in air inhaled by a receptor and concentrations in air surrounding crops. Concentrations in air to which the receptor is exposed are then used in the inhalation submodel to calculate the dose contribution to the receptor from inhalation of contaminated airborne particles. Concentrations in air surrounding plants are used in the plant submodel to calculate the concentrations of radionuclides in foodstuffs contributed from uptake by foliar interception. This

  7. Inhalation Exposure Input Parameters for the Biosphere Model

    International Nuclear Information System (INIS)

    M. Wasiolek

    2006-01-01

    This analysis is one of the technical reports that support the Environmental Radiation Model for Yucca Mountain, Nevada (ERMYN), referred to in this report as the biosphere model. ''Biosphere Model Report'' (BSC 2004 [DIRS 169460]) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents development of input parameters for the biosphere model that are related to atmospheric mass loading and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the total system performance assessment (TSPA) for a Yucca Mountain repository. ''Inhalation Exposure Input Parameters for the Biosphere Model'' is one of five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the biosphere model is presented in Figure 1-1 (based on BSC 2006 [DIRS 176938]). This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling and how this analysis report contributes to biosphere modeling. This analysis report defines and justifies values of atmospheric mass loading for the biosphere model. Mass loading is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Mass loading values are used in the air submodel of the biosphere model to calculate concentrations of radionuclides in air inhaled by a receptor and concentrations in air surrounding crops. Concentrations in air to which the receptor is exposed are then used in the inhalation submodel to calculate the dose contribution to the receptor from inhalation of contaminated airborne particles. Concentrations in air surrounding plants are used in the plant submodel to calculate the concentrations of radionuclides in foodstuffs contributed from uptake by foliar interception. This report is concerned primarily with the

  8. Long-term dose-response studies of inhaled or injected radionuclides. Biennial report, 1 October 1991--30 September 1993

    Energy Technology Data Exchange (ETDEWEB)

    Boecker, B.B.; Muggenburg, B.A.; Miller, S.C.; Bradley, P.L. [eds.

    1994-01-01

    This report describes the scientific progress in, and current status of, life-span studies of the long-term health risks in Beagle dogs of chronic irradiation from internally deposited radionuclides or from an external source. The reporting period for this document is the 2-year period from October 1, 1991 through September 30, 1993. Studies that were initiated at three different laboratories (Inhalation Toxicology Research Institute, ITRI, University of Utah, and Argonne National Laboratory, ANL) are presented here because they are being completed at ITRI. All living dogs in the Utah-initiated studies were transferred to the ITRI facility for the remainder of their life-span observations and measurements in September 1987. This report is the fourth in a series of reports dealing with the current status and progress of both the Utah and ITRI studies. Other life-span studies involving dogs exposed to gamma radiation from an external source were initiated and conducted for many years at ANL. In 1991, the decision was made to discontinue the chronic irradiation of the remaining living dogs and to transfer all remaining dogs to ITRI for care, clinical observations, and pathological observations at death or euthanasia. This report provides the current status of these dogs. Status reports on the Utah and ITRI studies comprise most of this report. The ITRI-related section presents brief statements of project objectives, the general procedures used in these studies, and some study-specific features for each of the 19 studies being conducted with either beta- or alpha-emitting radionuclides. Dose- and effect-modifying factors being addressed in these studies include total dose, dose rate, LET, solubility, nonuniformity of dose, species, age, sex, health status, and mode of exposure. Recent additions to experimental protocols for studies in which dogs are still alive involve the collection and analysis of tumor tissues using currently available molecular biology techniques.

  9. Deposition of inhaled radionuclides in bronchial airways: Implications for extrapolation modeling

    International Nuclear Information System (INIS)

    Balashazy, I.; Hofmann, W.; Heistracher, T.

    1996-01-01

    The laboratory rat has frequently been used as a human surrogate to estimate potential health effects following the inhalation of radioactive aerosol particles. Interspecies differences in biological response are commonly related to interspecies differences in particle deposition efficiencies. In addition, the documented site selectivity of bronchial carcinomas suggests that localized particle deposition patterns within bronchial airway bifurcations may have important implications for inhalation risk assessments. Interspecies differences in particle deposition patterns may be related primarily to differences in airway morphometries. Thus the validity of extrapolating rat deposition data to human inhalation conditions depends on their morphometric similarities and differences. It is well known that there are significant structural differences between the human - rather symmetric - and the rat - monopodial - airway systems. In the present approach, we focus on localized deposition patterns and deposition efficiencies in selected asymmetric bronchial airway bifurcations, whose diameters, lengths and branching angles were derived from the stochastic airway models of human and rat lungs (Koblinger and Hofmann, 1985;1988), which are based on the morphometric data of Raabe et al. (1976). The effects of interspecies differences in particle deposition patterns are explored in this study for two asymmetric bifurcation geometries in segmental bronchi and terminal bronchioles of both the human and rat lungs at different particle sizes. In order to examine the effect of flow rate on particle deposition in the human lung, we selected two different minute volumes, i.e., 10 and 60 1 min -1 , which are representative of low and heavy physical activity breathing conditions. In the case of the rat we used a minute volume of 0.234 1 min -1 (Hofmann et al., 1993)

  10. Reconstruction of the size of nuclear fuel particle aerosol by the investigation of a radionuclide behaviour in body of the Chernobyl accident witnesses

    International Nuclear Information System (INIS)

    Kutkov, V.A.

    1996-01-01

    As a result of the Chernobyl NPP (ChNPP) accident aerosol particles of dispersed nuclear fuel were released to the atmosphere. Inhalation of those aerosol became the source of internal exposure for witnesses of the Chernobyl accident. To assess correctly internal doses from a mixture of radionuclides present in air in the form of aerosol particles one mast assign each radionuclide to a certain inhalation class by its chemical speciation in aerosol and define the airborne characteristics (the activity median aerodynamic diameter, AMAD and the standard geometric deviation, fig) of that particular aerosol. Moreover, information on any particular radionuclide is useless for other components since, in such a mixture, the radionuclides are generally independent and may belong to different particles. On the contrary, all nuclear fuel particle (NFP) radionuclides belong to the same particle, being matrix-bound. The collective behaviour of the matrix-bound radionuclides in the environment and in the human barrier organs makes it possible to spread to the aerosol of NFP any estimates of AMAD and β g obtained for any particular NFP radionuclide. This is principal feature of NFP aerosol as distinguished from a mere mixture of aerosol particles carry different radionuclides. (author)

  11. Use of synthetic zeolites and other inorganic sorbents for the removal of radionuclides from aqueous wastes

    International Nuclear Information System (INIS)

    Samantha, S.K.; Singh, I.J.; Jain, S.; Sathi, S.; Venkatesan, K.; Ramaswamy, M.; Theyyunni, T.K.; Siddiqui, H.R.

    1997-01-01

    Several synthetic zeolites and inorganic sorbents were tested in the laboratory for the sorption of various radionuclides present in radioactive aqueous waste streams originating from nuclear installations. The sorption of the critical radionuclides like 137 Cs, 90 Sr and 60 Co from level waste solutions was studied using the synthetic zeolites 4A, 13X and AR1 of Indian origin. Granulated forms of ammonium molybdophosphate and CaSO 4 -BaSO 4 eutectoid were tested for the sorption of cesium and strontium respectively, from acidic solutions. The removal of radiostrontium from alkaline salt-loaded intermediate level reprocessing wastes was studied using hydrous ferric oxide-activated carbon composite sorbent, hydrous titania and hydrous manganese dioxide.. The results of these investigations are expected to be of value in formulating radioactive waste treatment schemes for achieving high decontamination and volume reduction factors. (author). 12 refs, 5 figs, 18 tabs

  12. Transuranic radionuclides dispersed into the aquatic environment, a bibliography

    Energy Technology Data Exchange (ETDEWEB)

    Noshkin, V.E.; Stoker, A.C.; Wong, Kai M. [and others

    1994-04-01

    The purpose of this project was to compile a bibliography of references containing environmental transuranic radionuclide data. Our intent was to identify those parameters affecting transuranic radionuclide transport that may be generic and those that may be dependent on chemical form and/or environmental conditions (i.e., site specific) in terrestrial, aquatic and atmospheric environments An understanding of the unique characteristics and similarities between source terms and environmental conditions relative to transuranic radionuclide transport and cycling will provide the ability to assess and predict the long term impact on man and the environment. An additional goal of our literature review, was to extract the ranges of environmental transuranic radionuclide data from the identified references for inclusion in a data base. Related to source term, these ranges of data can be used to calculate the dose to man from the radionuclides, and to perform uncertainty analyses on these dose assessments. On the basis of our reviews, we have arbitrarily outlined five general source terms. These are fallout, fuel cycle waste, accidents, disposal sites and resuspension. Resuspension of the transuranic radionuclides is a unique source term, in that the radionuclides can originate from any of the other source terms. If these transuranic radionuclides become resuspended into the air, they then become important as a source of inhaled radionuclides.

  13. Modeling The Inhalation Exposure Pathway In Performance Assessment Of Geologic Radioactive Waste Repository At Yucca Mountain

    International Nuclear Information System (INIS)

    M.A. Wasiolek

    2006-01-01

    Inhalation exposure pathway modeling has recently been investigated as one of the tasks of the BIOPROTA Project (BIOPROTA 2005). BIOPROTA was set up to address the key uncertainties in long term assessments of contaminant releases into the environment arising from radioactive waste disposal. Participants of this international Project include national authorities and agencies, both regulators and operators, with responsibility for achieving safe and acceptable radioactive waste management. The objective of the inhalation task was to investigate the calculation of doses arising from inhalation of particles suspended from soils within which long-lived radionuclides, particularly alpha emitters, had accumulated. It was recognized that site-specific conditions influence the choice of conceptual model and input parameter values. Therefore, one of the goals of the task was to identify the circumstances in which different processes included in specific inhalation exposure pathway models were important. This paper discusses evaluation of processes and modeling assumptions specific to the proposed repository at Yucca Mountain as compared to the typical approaches and other models developed for different assessments and project specific contexts. Inhalation of suspended particulates that originate from contaminated soil is an important exposure pathway, particularly for exposure to actinides such as uranium, neptunium and plutonium. Radionuclide accumulation in surface soil arises from irrigation of soil with contaminated water over many years. The level of radionuclide concentration in surface soil depends on the assumed duration of irrigation. Irrigation duration is one of the parameters used on biosphere models and it depends on a specific assessment context. It is one of the parameters addressed in this paper from the point of view of assessment context for the proposed repository at Yucca Mountain. The preferred model for the assessment of inhalation exposure uses

  14. Toxicity of 144Ce inhaled in a relatively insoluble form by immature Beagle dogs. XVII

    International Nuclear Information System (INIS)

    Boeker, B.B.; Muggenburg, B.A.; Hahn, F.F.; Mauderly, J.L.; McClellan, R.O.

    1988-01-01

    Immature Beagle dogs (3-mo old) received a single, brief inhalation exposure to 144 Ce in fused aluminosilicate particles as part of a series of studies designed to study the effects of age on dose response relationships for inhaled radionuclides. Forty-nine dogs inhaled graded levels of 144 Ce that resulted in initial lung burdens ranging from 0.004-140 μCi/kg 0.15-5200 kBq/kg) body weight. Five control dogs inhaled nonradioactive fused aluminosilicate particles. Forty-one of the 144 Ce-exposed dogs have died: 11 with lung tumors 4 with tumors of the tracheobronchial lymph nodes, with a nasal cavity tumor, and 9 with non neoplastic diseases of the respiratory tract. Observations are continuing on the 8 144 Ce-exposed dogs that are surviving at this time. (author)

  15. Evaluation and testing of HUMASORB-CS trademark for the removal of radionuclides from groundwater

    International Nuclear Information System (INIS)

    Mann, N.R.; Todd, T.A.; Wood, D.J.

    1998-01-01

    An independent experiment to demonstrate the combined removal of the radionuclides, 85 Sr and 137 Cs from groundwater has been conducted with the sorbent, HUMASORB-CS. Arctech, Inc. manufactures this humic acid-based sorbent material. This sorbent material is reported to have potential for remediation of contaminated groundwater present at DOE sites. The purpose of this work was to evaluate the removal efficiency and the capacity of the sorbent. Two ion-exchange columns were assembled at the Idaho Chemical Processing Plant (ICPP) to evaluate the sorbent technology. Initial 137 Cs breakthrough in both columns was observed after 22.0 and 30.2 bed volumes, respectively. Strontium-85 removal was slightly more efficient than 137 Cs removal. Initial 85 Sr breakthrough in both columns was observed after 29.4 and 22.7 bed volumes, respectively. Calcium, which is of concern, is the major constituent within the feed solution. Calcium is attributed to loading interference in addition to other alkaline and alkaline earth metals such as stable Sr, Mg, Na, K, and Ba. Interfering ions fill exchange sites that greatly reduce the sorbents efficiency to sorb targeted ions such as radioactive Cs and Sr. Despite high concentrations of Ca in the feed solution, Ca was not sorbed by HUMASORB-CS. Results indicate HUMASORB-CS does not sorb sodium or potassium. Sodium and potassium concentrations were consistently observed at 100% breakthrough throughout the test

  16. Lung dose and lung cancer risk by inhalation of radon daughters

    International Nuclear Information System (INIS)

    Jacobi, W.

    1983-01-01

    The inhalation of short-lived radon daughters constitutes the most important occupational radiation exposure in mines, particularly in uranium mines. Among some groups of miners exposed in the past to relatively high radon levels, an excess lung cancer incidence has been observed. In addition to this occupational hazard, the observed radon levels in domestic houses indicate that the inhalation of short-lived radon daughters seems to be the most important component of the radiation exposure of the population from natural sources. For the quantification and judgment of the radiological impact by inhalation of radon daughters in mines as well as in houses, it is necessary to estimate the relationships between the inhaled activity or potential alpha (α) energy of these radionuclides, the dose to target tissues in the lung, and the possible associated lung cancer (LC) risk. It is the purpose of this paper to give a condensed review of our present knowledge in this field and to indicate the main gaps and uncertainties where future research seems necessary

  17. The use of radionuclide skeleton visualization method in hygienic studies

    International Nuclear Information System (INIS)

    Likutova, I.V.; Bobkova, T.E.; Belova, E.A.; Bogomazov, M.Ya.

    1984-01-01

    Inhalation, intragastric and combined effect of two cadmium compounds on rats is studied. Investigations are performed by biochemical methods and the method of radionuclide visualization of the skeleton which was performed delta hours after RPP introduction in gamma-chamber with computer tape recording for the following mathematical treatment of the image. Using the method of radionuclide skeleton visualization pronounced quantitative characteristics of changes in the bone tissue are obtained, it is found that dose dependence of these changes is especially important when estimating the complex effect. Biochemical methods, are used to find alterations, however they have not been assessed quantitatively

  18. Analysis of radionuclide dispersion at normal condition for AEC 1000 MW reactor power

    International Nuclear Information System (INIS)

    Sri Kuntjoro

    2010-01-01

    Analysis for radionuclide dispersion for the Atomic Energy Agency (AEC) 3,568 MWth Power Reactor, equal to the 1,000 MWe at normal condition has been done. Analysis was done for two piles that is separated by 500 m distance and angle of 90° one to other. Initial pace in doing the analysis is to determine reactors source term using ORIGEN2 and EMERALD NORMAL. computer code program. ORIGEN2 applied to determine radionuclide inventory emerged in the reactor. Hereinafter, by using Emerald Normal Computer code is calculated source term reaching the reactor stack. To analyze dose received by population is done by using PC-CREAM computer code. Calculation done for one and two PLTN attached in site candidate of plants. The result showed is that the highest radionuclide release for one PLTN is at 1 km distance and to 9 th zone toward ( 19.25° ) and for two PLTN is at 1 km distance and to 10 th zone toward (21.75° ). Radionuclide which up to population through two pathways that are foodstuff and inhalation. To foodstuff comes from radionuclide I 131 , and the biggest passed from milk product with 53.40 % for one and also two PLTN For inhalation pathway the highest radionuclide contribution come from Kr 85m is about 53.80 %. The highest total dose received by population is at 1 Km distance received by baby that is 4.10 µSi and 11.26 µSi for one and two PLTN respectively. Those result are very small compared to the maximum permission dose to population issued by regulatory body that is equal to 1 mSi. (author)

  19. Retention and translocation of inhaled uranyl nitrate (233U and 232U) in rats

    International Nuclear Information System (INIS)

    Ballou, J.E.; Gies, R.A.; Wogman, N.A.

    1978-01-01

    The uranium-thorium breeder reactors proposed for nuclear power production, and other thorium fuel systems in conventional reactors, utilize fuels and fuel recycle process solutions that have not been evaluated for biological hazard. This project emphasizes studies of the metabolism of the oxide fuels and the nitrate solutions of the major radionuclides, following inhalation, ingestion, or cutaneous application in rodents. Preliminary data are reported for the clearance of inhaled 233 UO 2 (NO 3 ) 2 and 232 UO 2 (NO 3 ) 2 from the lung and their translocation to skeleton

  20. Comparison of bone cancer risks in beagle dogs for inhaled plutonium-238 dioxide, inhaled strontium-90 chloride, and injected strontium-90

    Energy Technology Data Exchange (ETDEWEB)

    Griffith, W.C.; Muggenburg, B.A.; Hahn, F.F. [and others

    1995-12-01

    There is a continuing need to understand dose-response relationships for ionizing radiation in order to protect the health of the public and nuclear workers from undue exposures. However, relatively few human populations have been exposed to doses of radiation high enough to cause observable, long-term health effects from which to derive dose-response relationships. This is particularly true for internally deposited radionuclides, although much effort has been devoted to epidemiological studies of the few types of exposures available, including lung cancers in uranium miners form the inhalation of the radioactive decay products of Ra, liver cancers in patients injected with Thorotrast X-ray contrast medium containing Th, bone cancers in radium dial painters who ingested Ra, and bone cancers in patients who received therapeutic doses of Ra. These four types of exposures to internally deposited radionuclides provide a basis for understanding the health effects of many other radionuclides for which a potential for exposure exists. However, potential exposures to internally deposited radionuclides may differ in many modifying factors, such as route of exposure, population differences, and physical, chemical, and elemental forms of radionuclides. The only means available to study many of these modifying factors has been in laboratory animals, and to then extrapolate the results to humans. Three conclusions can be drawn from this example.

  1. Comparison of bone cancer risks in beagle dogs for inhaled plutonium-238 dioxide, inhaled strontium-90 chloride, and injected strontium-90

    International Nuclear Information System (INIS)

    Griffith, W.C.; Muggenburg, B.A.; Hahn, F.F.

    1995-01-01

    There is a continuing need to understand dose-response relationships for ionizing radiation in order to protect the health of the public and nuclear workers from undue exposures. However, relatively few human populations have been exposed to doses of radiation high enough to cause observable, long-term health effects from which to derive dose-response relationships. This is particularly true for internally deposited radionuclides, although much effort has been devoted to epidemiological studies of the few types of exposures available, including lung cancers in uranium miners form the inhalation of the radioactive decay products of Ra, liver cancers in patients injected with Thorotrast X-ray contrast medium containing Th, bone cancers in radium dial painters who ingested Ra, and bone cancers in patients who received therapeutic doses of Ra. These four types of exposures to internally deposited radionuclides provide a basis for understanding the health effects of many other radionuclides for which a potential for exposure exists. However, potential exposures to internally deposited radionuclides may differ in many modifying factors, such as route of exposure, population differences, and physical, chemical, and elemental forms of radionuclides. The only means available to study many of these modifying factors has been in laboratory animals, and to then extrapolate the results to humans. Three conclusions can be drawn from this example

  2. 40 CFR 141.66 - Maximum contaminant levels for radionuclides.

    Science.gov (United States)

    2010-07-01

    ... beta particle and photon radioactivity from man-made radionuclides in drinking water must not produce.../year). (2) Except for the radionuclides listed in table A, the concentration of man-made radionuclides... may make this technology too complex for small surface water systems. e Removal efficiencies can vary...

  3. Radionuclide Sensors for Subsurface Water Monitoring. Final report

    International Nuclear Information System (INIS)

    Timothy DeVol

    2006-01-01

    Contamination of the subsurface by radionuclides is a persistent and vexing problem for the Department of Energy. These radionuclides must be measured in field studies and monitored in the long term when they cannot be removed. However, no radionuclide sensors existed for groundwater monitoring prior to this team's research under the EMSP program. Detection of a and b decays from radionuclides in water is difficult due to their short ranges in condensed media

  4. Accumulation of zirconium phosphate by a Serratia sp.: a benign system for the removal of radionuclides from aqueous flows.

    Science.gov (United States)

    Mennan, Claire; Paterson-Beedle, Marion; Macaskie, Lynne E

    2010-10-01

    Metal phosphate deposited enzymatically on Serratia sp. has been used successfully for the removal of radionuclides from aqueous flows. Previous studies using biogenic hydrogen uranyl phosphate (HUP) on Serratia sp. biofilm showed removal of 100% of (90)Sr, (137)Cs, and (60)Co via their intercalation into biogenic HUP crystals. Zirconium phosphates (ZrP) offer a potential non-toxic and non-radioactive alternative to HUP for water decontamination. A method was developed for biomanufacturing ZrP. Biogenic ZrP removed ca. 100% of Sr(2+) and Co(2+) (0.5 mM) from solutions to a molar ratio at saturation of ca. 1:0.6 for both Zr:Sr and Zr:Co. The potential for drinking water decontamination via bio-ZrP is discussed with respect to bio-HUP and also other commercially available materials.

  5. Inhalation Exposure Input Parameters for the Biosphere Model

    International Nuclear Information System (INIS)

    M. A. Wasiolek

    2003-01-01

    This analysis is one of the nine reports that support the Environmental Radiation Model for Yucca Mountain Nevada (ERMYN) biosphere model. The ''Biosphere Model Report'' (BSC 2003a) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents a set of input parameters for the biosphere model, and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the Total System Performance Assessment (TSPA) for a Yucca Mountain repository. This report, ''Inhalation Exposure Input Parameters for the Biosphere Model'', is one of the five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the ERMYN is presented in Figure 1-1. This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling, and the plan for development of the biosphere abstraction products for TSPA, as identified in the ''Technical Work Plan: for Biosphere Modeling and Expert Support'' (BSC 2003b). It should be noted that some documents identified in Figure 1-1 may be under development at the time this report is issued and therefore not available at that time. This figure is included to provide an understanding of how this analysis report contributes to biosphere modeling in support of the license application, and is not intended to imply that access to the listed documents is required to understand the contents of this analysis report. This analysis report defines and justifies values of mass loading, which is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Measurements of mass loading are used in the air submodel of ERMYN to calculate concentrations of radionuclides in air surrounding crops and concentrations in air inhaled by a receptor. Concentrations in air to which the

  6. Incidence of bone cancer in beagles after inhalation of 90SrCl2 or 238PuO2: Implications for estimation of risk to humans

    International Nuclear Information System (INIS)

    Mewhinney, J.A.; Griffith, W.C.; Hahn, F.F.; Snipes, M.B.; Boecker, B.B.; McClellan, R.O.

    1986-01-01

    Among the life-span studies conducted with beagle dogs, bone cancer has been in two studies the predominant effect at death. These studies involved dogs that inhaled 90 SrCl 2 , which is very soluble in body fluids; and dogs that inhaled 238 PuO 2 , which is initially insoluble but eventually becomes fragmented and more soluble. Both radionuclides were deposited in the skeleton after dissolution in the lung and absorption into the bloodstream. All dogs in the 90 Sr study are dead, and all living dogs in the 238 Pu study are at least 7 years postexposure. Results from these two studies were compared to determine the relative biological effectiveness (RBE) of chronic beta and alpha radiation delivered from these two radionuclides. These data also were used to estimate the risk of bone cancer in man by using comparisons with data from the 90 Sr-, 239 Pu-, and 226 Ra-injected dogs at the University of Utah and data on humans who ingested 226 Ra or were injected with 224 Ra. Such comparisons provided a link between studies in laboratory animals and the available human data. In this way risks of bone cancer in humans from inhaled plutonium or strontium were estimated, even though currently no human cases of bone cancer are known to have resulted from the inhalation of either of these radionuclides. 15 refs., 7 figs., 7 tabs

  7. Toxicity of {sup 144}Ce inhaled in a relatively insoluble form by immature Beagle dogs. XVII

    Energy Technology Data Exchange (ETDEWEB)

    Boeker, B B; Muggenburg, B A; Hahn, F F; Mauderly, J L; McClellan, R O

    1988-12-01

    Immature Beagle dogs (3-mo old) received a single, brief inhalation exposure to {sup 144}Ce in fused aluminosilicate particles as part of a series of studies designed to study the effects of age on dose response relationships for inhaled radionuclides. Forty-nine dogs inhaled graded levels of {sup 144}Ce that resulted in initial lung burdens ranging from 0.004-140 {mu}Ci/kg 0.15-5200 kBq/kg) body weight. Five control dogs inhaled nonradioactive fused aluminosilicate particles. Forty-one of the {sup 144}Ce-exposed dogs have died: 11 with lung tumors 4 with tumors of the tracheobronchial lymph nodes, with a nasal cavity tumor, and 9 with non neoplastic diseases of the respiratory tract. Observations are continuing on the 8 {sup 144}Ce-exposed dogs that are surviving at this time. (author)

  8. Phytoremediation of radionuclides: an emerging alternative

    International Nuclear Information System (INIS)

    Singh, Shraddha

    2013-01-01

    Proliferation of nuclear power industry, nuclear weapon testing, dismantling of existing nuclear weapons and occasional accidents have contributed to an enhancement in the level of radionuclides in the environment. The radionuclides due to their long half life and transfer through the food chain effect adversely to normal biological systems. Hence, it is essential to effectively remove the radionuclides from contaminated soils and solutions. Phytoremediation - the use of plants for remediation of toxic metals and radionuclides has been recognized as an aesthetically pleasing, low cost and environment friendly in situ method. Phytoremediation is an umbrella term which covers several plant based approaches. Plants have shown the potential of remediation of these radionuclides from spiked solutions, low level nuclear waste and soil. Various aspects of phytoremediation as well as potential of various plants for remediation of radionuclides will be discussed here. (author)

  9. Reliability of Current Biokinetic and Dosimetric Models for Radionuclides: A Pilot Study

    Energy Technology Data Exchange (ETDEWEB)

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Meck, Robert A. [U.S. Nuclear Regulatory Commission

    2008-10-01

    This report describes the results of a pilot study of the reliability of the biokinetic and dosimetric models currently used by the U.S. Nuclear Regulatory Commission (NRC) as predictors of dose per unit internal or external exposure to radionuclides. The study examines the feasibility of critically evaluating the accuracy of these models for a comprehensive set of radionuclides of concern to the NRC. Each critical evaluation would include: identification of discrepancies between the models and current databases; characterization of uncertainties in model predictions of dose per unit intake or unit external exposure; characterization of variability in dose per unit intake or unit external exposure; and evaluation of prospects for development of more accurate models. Uncertainty refers here to the level of knowledge of a central value for a population, and variability refers to quantitative differences between different members of a population. This pilot study provides a critical assessment of models for selected radionuclides representing different levels of knowledge of dose per unit exposure. The main conclusions of this study are as follows: (1) To optimize the use of available NRC resources, the full study should focus on radionuclides most frequently encountered in the workplace or environment. A list of 50 radionuclides is proposed. (2) The reliability of a dose coefficient for inhalation or ingestion of a radionuclide (i.e., an estimate of dose per unit intake) may depend strongly on the specific application. Multiple characterizations of the uncertainty in a dose coefficient for inhalation or ingestion of a radionuclide may be needed for different forms of the radionuclide and different levels of information of that form available to the dose analyst. (3) A meaningful characterization of variability in dose per unit intake of a radionuclide requires detailed information on the biokinetics of the radionuclide and hence is not feasible for many infrequently

  10. Transport of the radionuclides and doses for some coal fired power plants

    International Nuclear Information System (INIS)

    Antic, D.; Telenta, B.; Sokcic-Kostic, M.

    1994-01-01

    The radiation exposure of the public in the vicinity of the selected coal fired power plants near from Belgrade has been studied. The contents of natural radionuclides according to experimental data have been used and dose rates from inhalation have been calculated using a two dimensional version of the cloud model. (author)

  11. Surfactant-impregnated activated carbon for enhanced adsorptive removal of Ce(IV) radionuclides from aqueous solutions

    International Nuclear Information System (INIS)

    Mahmoud, Mamdoh R.; Sharaf El-deen, Gehan E.; Soliman, Mohamed A.

    2014-01-01

    Highlights: • Activated carbon (AC) was impregnated in this work with CTAB and NaLS surfactants. • The materials were evaluated as a sorbent for adsorption of Ce(IV) radionuclides. • Adsorption capacity of AC–NaLS for Ce(IV) is two-times the capacity of AC. • The kinetic and equilibrium data are fitted to pseudo-second-order and D–R models. • The results suggest the applicability of surface modified AC for waste treatment. - Abstract: The surfactants cetyltrimethylammonium bromide (CTAB) and sodium lauryl sulfate (NaLS) were utilized for modifying the activated carbon’s surface. The materials were characterized using BET–N 2 , scanning electron microscope, and Fourier transform infrared (FT-IR) spectroscopy. Adsorption of Ce(IV) radionuclides from aqueous solutions by activated carbon (AC) and surfactant-impregnated AC was studied. The obtained data showed that adsorption of Ce(IV) is strongly dependent on the solution pH and AC–NaLS exhibits the widest pH-range of maximum removal. The experimental adsorption capacity of AC–NaLS (0.069 mmol/g) for Ce(IV) is found to be nearly twice greater than that of AC (0.036 mmol/g). The adsorption kinetics of Ce(IV) onto AC and AC–NaLS were analyzed by linear and non-linear fittings to the pseudo-first-order, pseudo-second-order and Elovich kinetic models. Of these models, the pseudo-second-order is the best kinetic expression for describing the experimental data. The diffusion studies indicated that adsorption of Ce(IV) radionuclides on AC and AC–NaLS is controlled by film diffusion. Linear and non-linear fittings of the adsorption equilibrium data for Ce(IV) onto AC and AC–NaLS revealed that the Dubinin–Radushkevich (D–R) isotherm model fits the experimental data better than Freundlich and Langmuir models. The values of adsorption free energy, E, calculated from both linear and non-linear methods suggested that Ce(IV) radionuclides are physically adsorbed onto AC and AC–NaLS

  12. Exposure of F344 rats to aerosols of 239PuO2 and chronically inhaled cigarette smoke

    International Nuclear Information System (INIS)

    Finch, G.L.; Nikula, K.J.; Barr, E.B.; Bechtold, W.E.; Chen, B.T.; Griffith, W.C.; Hobbs, C.H.; Hoover, M.D.; Mauderly, J.L.

    1994-01-01

    Nuclear workers may be accidently exposed to radioactive materials such as 239 PuO 2 by inhalation, and thus have increased risk for lung cancer compared to the general population. Of additional concern is the possibility that interactions between radionuclides and other carcinogens may increase the risk of cancer induction. An important and common lung carcinogen is cigarette smoke. This study is being conducted to better determine the combined effects of inhaled 239 PuO 2 and cigarette smoke on the induction of lung cancer in rats

  13. Marine biogeochemistry of radionuclides

    International Nuclear Information System (INIS)

    Fowler, S.W.

    1997-01-01

    Radionuclides entering the ocean from runoff, fallout, or deliberate release rapidly become involved in marine biogeochemical cycles. Sources, sinks and transport of radionuclides and analogue elements are discussed with emphasis placed on how these elements interact with marine organisms. Water, food and sediments are the source terms from which marine biota acquire radionuclides. Uptake from water occurs by surface adsorption, absorption across body surfaces, or a combination of both. Radionuclides ingested with food are either assimilated into tissue or excreted. The relative importance of the food and water pathway in uptake varies with the radionuclide and the conditions under which exposure occurs. Evidence suggests that, compared to the water and food pathways, bioavailability of sediment-bound radionuclides is low. Bioaccumulation processes are controlled by many environmental and intrinsic factors including exposure time, physical-chemical form of the radionuclide, salinity, temperature, competitive effects with other elements, organism size, physiology, life cycle and feeding habits. Once accumulated, radionuclides are transported actively by vertical and horizontal movements of organisms and passively by release of biogenic products, e.g., soluble excreta, feces, molts and eggs. Through feeding activities, particles containing radionuclides are ''packaged'' into larger aggregates which are redistributed upon release. Most radionuclides are not irreversibly bound to such particles but are remineralized as they sink and/or decompose. In the pelagic zones, sinking aggregates can further scavenge particle-reactive elements thus removing them from the surface layers and transporting them to depth. Evidence from both radiotracer experiments and in situ sediment trap studies is presented which illustrates the importance of biological scavenging in controlling the distribution of radionuclides in the water column. (author)

  14. Internal dosimetry contamination: update of revision of the dose coefficients for intakes of radionuclides by workers

    International Nuclear Information System (INIS)

    Gomez Parada, I.; Rojo, A.M.; Sanguineti, R.

    1995-01-01

    ICRP publication 60 introduces new biological information related to the detriment associated with radiation exposures. The International Commission on Radiological Protection has also issued, in publications 57, 67 y 69, new biokinetic models for selected radionuclides since the issue of publication 30. In publication 66 the new human respiratory tract model for radiological protection is described. The aim of the present paper is to compare values of dose coefficients for workers calculated using the new tissue weighting factors, biokinetic models and lung model with those given in publication 30.The software package LUPED 1.1 was used to calculate dose coefficients for inhalation and ingestion. When possible, some changes in the biokinetic models were made trying to incorporate new parameters. The following radionuclides were analysed: 60 Co, 90 Sr, 99m Tc, 131 I, 137 Cs, 239 Pu y 241 Am. Most of the inhalation dose coefficients calculated with the new assumptions are within a factor of three of those calculated using the ICRP 30 lung and biokinetic models. Generally, the inhalation dose coefficients calculated with the new respiratory tract model and assuming a 5μm AMAD are lower than those calculated using the ICRP 30 model and parameters. The inhalation dose coefficients are generally within 10-90 % of the corresponding Publication 61 values, the difference tending to increase for relative insoluble compounds. (author). 10 refs., 4 tabs

  15. Proceedings of Soil Decon `93: Technology targeting radionuclides and heavy metals

    Energy Technology Data Exchange (ETDEWEB)

    1993-09-01

    The principal objective for convening this workshop was to exchange ideas and discuss with scientists and engineers methods for removing radionuclides and/or toxic metals from soils. Over the years there have been numerous symposia, conferences, and workshops directed at soil remediation. However, this may be the first where the scope was narrowed to the removal of radionuclides and toxic metals from soils. The intent was to focus on the separation processes controlling the removal of the radionuclide and/or metal from soil. Its purpose was not intended to be a soil washing/leaching workshop, but rather to identify a variety or combination of processes (chemical, physical, and biological) that can be used in concert with the applicable engineering approaches to decontaminate soils of radionuclides and toxic metals. Abstracts and visual aids used by the speakers of the workshop are presented in this document.

  16. Proceedings of Soil Decon '93: Technology targeting radionuclides and heavy metals

    International Nuclear Information System (INIS)

    1993-09-01

    The principal objective for convening this workshop was to exchange ideas and discuss with scientists and engineers methods for removing radionuclides and/or toxic metals from soils. Over the years there have been numerous symposia, conferences, and workshops directed at soil remediation. However, this may be the first where the scope was narrowed to the removal of radionuclides and toxic metals from soils. The intent was to focus on the separation processes controlling the removal of the radionuclide and/or metal from soil. Its purpose was not intended to be a soil washing/leaching workshop, but rather to identify a variety or combination of processes (chemical, physical, and biological) that can be used in concert with the applicable engineering approaches to decontaminate soils of radionuclides and toxic metals. Abstracts and visual aids used by the speakers of the workshop are presented in this document

  17. Toxicity of inhaled Ca-DTPA in the beagle dog

    International Nuclear Information System (INIS)

    Smith, V.H.; Ragan, H.A.; Lund, J.E.; Hackett, P.L.

    1975-01-01

    There are several advantages to the administration of Ca- DTPA by inhalation rather than intravenous drip for the decorporation of certain radionuclides. Among these are the possibility of treating very promptly following an accidental incorporation to achieve maximum treatment effectiveness and convenince for medical management, even to the extent that treatment can be self-administered. The present investigational New Drug permit allows treatment of humans only by the intravenous route and animal studies are required to justify the new route. Earlier work in rats and hamsters showed five successive daily inhalations of Ca-DTPA aerosols (dose 1 to 4 times human i.v. dose) produced a transitory emphysema in 17/40 rats serially sacrificed up to 3 weeks following the last exposure and in 10/20 hamsters up to 1 week after exposure. No emphysema was seen in rats sacrificed after 3 weeks and in hamsters after 1 week following the exposures. Results of tests in dogs administered DTPA by inhalation showed hyperplasia of the gastric submucosal lymphoid follicles observed 1 week following the last exposure may be treatment-related, but other observed changes were considered unrelated. (U.S.)

  18. Monte Carlo calculation of received dose from ingestion and inhalation of natural uranium

    International Nuclear Information System (INIS)

    Trobok, M.; Zupunski, Lj.; Spasic-Jokic, V.; Gordanic, V.; Sovilj, P.

    2009-01-01

    For the purpose of this study eighty samples are taken from the area Bela Crkva and Vrsac. The activity of radionuclide in the soil is determined by gamma- ray spectrometry. Monte Carlo method is used to calculate effective dose received by population resulting from the inhalation and ingestion of natural uranium. The estimated doses were compared with the legally prescribed levels. (author) [sr

  19. Phytoremediation of soil contaminated with low concentrations of radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Entry, J A; Vance, N C; Hamilton, M A; Zabowski, D; Watrud, L S; Adriano, D C [Auburn University, Auburn, AL (United States). Dept. of Agronomy and Soils

    1996-03-01

    Ecsosytems throughout the world have been contaminated with radionuclides by above-ground nuclear testing, nuclear reactor accidents and nuclear power generation. Radioisotopes characteristics of nuclear fission, such as {sup 137}Cs and {sup 90}Sr, that are released into the environment can become more concentrated as they move up the food chain often becoming human health hazards. Natural environmental processes will redistribute long lived radionuclides that are released into the environment among soil, plants and wildlife. Numerous studies have shown that {sup 137}Cs and {sup 90}Sr are not removed from the top 0.4 metres of soil even under high rainfall, and migration rate from the top few centimetres of soil is slow. The top 0.4 meters of the soil is where plant roots actively accumulate elements. Since plants are known to take up and accumulate {sup 137}Cs and {sup 90}Sr, removal of these radionuclides from contaminated soils by plants could provide a reliable and economical method of remediation. One approach is to use fast growing plants inoculated with mycorrhizal fungi combined with soil organic amendments to maximize the plant accumulation and removal of radionuclides from contaminated soils, followed by harvest of above-ground portion of the plants. High temperature combustion would be used to oxidize plant material concentrating {sup 137}Cs and {sup 90}Sr in ash for disposal. When areas of land have been contaminated with radionuclides are large, using energy intensive engineering solutions to mediate huge volumes of soil is not feasible or economical. Plants are proposed as a viable and cost effective method to remove radionuclides from the soils that have been contaminated by nuclear testing and nuclear reactor accidents. 40 refs.

  20. Estimating inhalation hazards for space nuclear power systems

    International Nuclear Information System (INIS)

    Hoover, M.D.; Cuddihy, R.G.; Seiler, F.Z.

    1989-01-01

    Minimizing inhalation hazards is a major consideration in the design, development, transportation, handling, testing, storage, launch, use, and ultimate disposition of nuclear space power systems (NSPSs). An accidental dispersion of 238 Pu is of concern for missions involving the radioisotope thermoelectric generators (RTGs) or lightweight radioisotope heater units. Materials of concern for missions involving a nuclear reactor might include other radionuclides, such as uranium, or chemically toxic materials, such as beryllium or lithium. This paper provides an overview of some of the current approaches and uncertainties associated with estimating inhalation hazards from potential NSPS accidents. The question of whether inhalation risks can be acceptable for nuclear space power systems is still open and active. The inherently low toxicity of the uranium fuel of a space nuclear reactor is a desirable feature of that option. The extensive engineering and testing that have contributed to the current generation of plutonium RTGs provide a measure of confidence that dispersion of the RTG fuel would be unlikely in an accident. The use of nuclear reactors or RTGs in space, however, requires society to assume a risk (albeit low) for dispersion of the fuel material. It can be argued that any additional risks from the use of nuclear power in space are far less than the risks we face daily

  1. Comparison of Different Internal Dosimetry Systems for Selected Radionuclides Important to Nuclear Power Production

    Energy Technology Data Exchange (ETDEWEB)

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Manger, Ryan P [ORNL

    2013-08-01

    This report compares three different radiation dosimetry systems currently applied by various U.S. Federal agencies and dose estimates based on these three dosimetry systems for a set of radionuclides often identified in power reactor effluents. These dosimetry systems were developed and applied by the International Commission on Radiological Protection at different times over the past six decades. Two primary modes of intake of radionuclides are addressed: ingestion in drinking water and inhalation. Estimated doses to individual organs and to the whole body based on each dosimetry system are compared for each of four age groups: infant, child, teenager, and adult. Substantial differences between dosimetry systems in estimated dose per unit intake are found for some individual radionuclides, but differences in estimated dose per unit intake generally are modest for mixtures of radionuclides typically found in nuclear power plant effluents.

  2. Siting criteria based on the prevention of deterministic effects from plutonium inhalation exposures

    International Nuclear Information System (INIS)

    Sorensen, S.A.; Low, J.O.

    1998-01-01

    Siting criteria are established by regulatory authorities to evaluate potential accident scenarios associated with proposed nuclear facilities. The 0.25 Sv (25 rem) siting criteria adopted in the United States has been historically based on the prevention of deterministic effects from acute, whole-body exposures. The Department of Energy has extended the applicability of this criterion to radionuclides that deliver chronic, organ-specific irradiation through the specification of a 0.25 Sv (25 rem) committed effective dose equivalent siting criterion. A methodology is developed to determine siting criteria based on the prevention of deterministic effects from inhalation intakes of radionuclides which deliver chronic, organ-specific irradiation. Revised siting criteria, expressed in terms of committed effective dose equivalent, are proposed for nuclear facilities that handle primarily plutonium compounds. The analysis determined that a siting criterion of 1.2 Sv (120 rem) committed effective dose equivalent for inhalation exposures to weapons-grade plutonium meets the historical goal of preventing deterministic effects during a facility accident scenario. The criterion also meets the Nuclear Regulatory Commission and Department of Energy Nuclear Safety Goals provided that the frequency of the accident is sufficiently low

  3. Inhalation Toxicology Research Institute annual report 1987-1988

    International Nuclear Information System (INIS)

    Mauderly, J.L.; Mewhinney, J.A.; Bechtold, W.E.; Sun, J.D.; Coons, T.A.

    1988-12-01

    section, Deposition and Fate of Inhaled Toxicants, describes factors influencing the uptake of inhaled materials and their initial interactions in the body. The third and fourth sections, Health Effects of Inhaled Radionuclides and Health Effects of Inhaled Chemical Toxicants, describe recent progress in the fields of radiation and chemical toxicology, respectively. The fifth section, Mechanisms of Carcinogenesis, reflects progress in the understanding of the mechanisms by which radiation and chemicals induce cancer. Similarly, the sixth section, Mechanisms of Non-Carcinogenic Responses to Inhaled Toxicants describes research on the development of diseases other than cancer. The seventh section, The Application of Mathematical Modeling to Health Issues, describes efforts to predict health risks by using computer-based models and limited experimental or epidemiological data. The final section, Studies at the University of Utah, describes progress in studies conducted by University of Utah scientists funded by subcontract through this Institute

  4. Inhalation Toxicology Research Institute annual report 1987-1988

    Energy Technology Data Exchange (ETDEWEB)

    Mauderly, J L; Mewhinney, J A; Bechtold, W E; Sun, J D; Coons, T A [eds.

    1988-12-01

    section, Deposition and Fate of Inhaled Toxicants, describes factors influencing the uptake of inhaled materials and their initial interactions in the body. The third and fourth sections, Health Effects of Inhaled Radionuclides and Health Effects of Inhaled Chemical Toxicants, describe recent progress in the fields of radiation and chemical toxicology, respectively. The fifth section, Mechanisms of Carcinogenesis, reflects progress in the understanding of the mechanisms by which radiation and chemicals induce cancer. Similarly, the sixth section, Mechanisms of Non-Carcinogenic Responses to Inhaled Toxicants describes research on the development of diseases other than cancer. The seventh section, The Application of Mathematical Modeling to Health Issues, describes efforts to predict health risks by using computer-based models and limited experimental or epidemiological data. The final section, Studies at the University of Utah, describes progress in studies conducted by University of Utah scientists funded by subcontract through this Institute.

  5. Preparation of modified polymer- Alumino silicate composite and their application in removal of some radionuclides from aqueous solutions

    International Nuclear Information System (INIS)

    El- Masry, E.H.

    2012-01-01

    Ion exchange is one of the most common and effective treatment methods for radioactive liquid waste. This technique is well developed and has been employed for many years in both the nuclear industry and in other industries. In this thesis polyacrylamide- zeolite and polyacrylamide- bentonite composites were prepared and characterized using advanced analytical techniques. The prepared materials were used as composite ion exchangers for removal of Cesium, Cobalt and Strontium ions from simulated waste solution. Effect of ph of the medium on the removal of aforementioned ions was investigated. The sorption kinetic was studied and the data were analyzed by different kinetic models which rivaled that the mechanism of the sorption processes is mainly controlled by pseudo-second order reaction, and particle diffusion might be involved in the sorption processes. The values of diffusion coefficient of the three metal ions were calculated and suggested that chemisorption was the predominated sorption mechanism. Several isotherm models were applied for the sorption, and thermodynamic parameters were determined. The positive values of enthalpy change, δH, for the three metal ions confirmed the endothermic nature of the sorption processes. The results indicated that the prepared materials can be used as efficient ion exchange materials for the removal of cesium, cobalt and strontium ions from simulated waste solution. In the present study, immobilization of polyacrylamide- zeolite and/ or polyacrylamide- bentonite composites loaded with cesium, cobalt and/or strontium radionuclides with Ordinary Portland Cement (OPC) has been carried out. Several factors affecting the characteristics of the final solidified waste product towards safe disposal such as mechanical strength and leaching behavior of the radioisotopes have been studied. The obtained results showed that the presence of polyacrylamide- zeolite and/ or polyacrylamide- bentonite composites in the cemented wastes

  6. Selective separation of radionuclides from nuclear waste solutions with inorganic ion exchangers

    International Nuclear Information System (INIS)

    Lehto, J.; Harjula, R.

    1999-01-01

    Nuclear industry produces and stores large volumes of radioactive waste solutions. Removal of radionuclides from the solutions is an important and challenging task for two main reasons: reductions in the volumes of solidified waste, which have to be disposed of, and reductions in the radioactive discharges into the environment. Since the radioactive elements in most waste solutions are in trace concentrations and the waste solutions contain large excesses of inactive metal ions, highly selective separation methods are needed for the removal of radionuclides. A number of inorganic ion exchange materials are very selective to key radionuclides and they can play an important role in solving these problems. The spectrum of nuclear waste solutions is rather wide considering their radionuclide contents, concentrations of interfering salts and acidity/alkalinity. Therefore, several inorganic ions exchangers are needed for the removal of most harmful radionuclides from a variety of solutions. This paper discusses the use and requirements of inorganic ion exchange materials in nuclear waste management. Special attention is paid to the novel ion exchange materials developed in the Laboratory of Radiochemistry, University of Helsinki. (orig.)

  7. Radiation load of the electro-thermal production of phosphorus. Part 1. The inhalation dose for operators

    International Nuclear Information System (INIS)

    Erkens, W.H.H.

    2003-01-01

    The phosphate ore which is processed by Thermphos International in Vlissingen, Netherlands, to produce element phosphorus contains circa 1 Bq per gram uranium 238. As a result of this production process radionuclides are emitted and slags that contain natural radioisotopes are formed. The slags can be used as a building material for roads and water works. During the production of phosphorus the waste material calcinate is formed as well. Operators, working in the production process of phosphorus and laborers, working in road construction and hydraulic engineering inhale radioisotopes. In two articles attention will be paid to the inhalation doses, how the doses are measured, measures that were taken to reduce and control the doses, and the ALARA-principles. This article is focused on the inhalation doses for operators in the phosphorus production industry [nl

  8. Gut-related studies of radionuclide toxicity

    International Nuclear Information System (INIS)

    Sullivan, M.F.

    1985-01-01

    The behavior of radioactive materials that may be ingested as a consequence of a reactor accident, unavoidable occupational exposure, or after release to the environment and incorporation into the food chain is investigated. Current emphasis is on evaluating hazards from ingested actinides as a function of animal age, species, nutrition, and diet, or chemicophysical state of the actinide. The authors are also concerned with the behavior of actinides that are inhaled and pass through the gastro-intestinal tract after clearance from the lungs. The radionuclides being investigated are 238 Pu, 241 Am, 244 Cm, 147 Pm, 109 Cd, and 210 Pb. 2 tables

  9. The removal of radionuclides from foodstuffs during technological treatment and culinary processing

    International Nuclear Information System (INIS)

    Perepelyatnikova, L.V.; Lazarev, N.M.; Ivanova, T.N.; Fedin, F.A.; Long, S.; Pollard, D.

    1996-01-01

    Comparative data on the efficiency of industrial and domestic processing techniques of plant and animal products, which reduce radionuclides content foodstuffs, are summarized. Methods, which provide the greatest decrease of radionuclides content in the final products with minimum losses of nutritional value, were identified

  10. Inhalation Exposure Input Parameters for the Biosphere Model

    Energy Technology Data Exchange (ETDEWEB)

    M. A. Wasiolek

    2003-09-24

    This analysis is one of the nine reports that support the Environmental Radiation Model for Yucca Mountain Nevada (ERMYN) biosphere model. The ''Biosphere Model Report'' (BSC 2003a) describes in detail the conceptual model as well as the mathematical model and its input parameters. This report documents a set of input parameters for the biosphere model, and supports the use of the model to develop biosphere dose conversion factors (BDCFs). The biosphere model is one of a series of process models supporting the Total System Performance Assessment (TSPA) for a Yucca Mountain repository. This report, ''Inhalation Exposure Input Parameters for the Biosphere Model'', is one of the five reports that develop input parameters for the biosphere model. A graphical representation of the documentation hierarchy for the ERMYN is presented in Figure 1-1. This figure shows the interrelationships among the products (i.e., analysis and model reports) developed for biosphere modeling, and the plan for development of the biosphere abstraction products for TSPA, as identified in the ''Technical Work Plan: for Biosphere Modeling and Expert Support'' (BSC 2003b). It should be noted that some documents identified in Figure 1-1 may be under development at the time this report is issued and therefore not available at that time. This figure is included to provide an understanding of how this analysis report contributes to biosphere modeling in support of the license application, and is not intended to imply that access to the listed documents is required to understand the contents of this analysis report. This analysis report defines and justifies values of mass loading, which is the total mass concentration of resuspended particles (e.g., dust, ash) in a volume of air. Measurements of mass loading are used in the air submodel of ERMYN to calculate concentrations of radionuclides in air surrounding crops and concentrations in air

  11. Objective measurement of inhaler inhalation flow profile using acoustic methods

    Energy Technology Data Exchange (ETDEWEB)

    Lacalle, H.; Taylor, T.E.; Marco, S.; Reilly, R.B.

    2016-07-01

    Patients with asthma and chronic obstructive pulmonary diseases (COPD) are mostly treated with inhalers that deliver medication directly to their airways. Drug delivery from dry powder inhalers (DPIs) is very much reliant on the inhalation manoeuvre, specifically the peak inspiratory flow rate (PIFR), inspiratory capacity (IC) and inhalation rise time (IRT) of the inhalation. It has been widely reported that patients may not follow correct inhalation technique while using their inhaler. In this study, a novel acoustic method is proposed to accurately estimate inhalation flow profile using only one inhalation recording for calibration. An Ellipta DPI was placed inside an airtight container with a spirometer connected in order to measure inhalation flow parameters. An acoustic recording device (Inhaler Compliance Assessment (INCA)) was also attached to the DPI. Inhalation audio and flow signals were recorded simultaneously. The data were collected from 20 healthy subjects while performing inhaler inhalations at a range of inspiratory flow rates. A power law regression model was computed to obtain the relationship between the acoustic envelope of the inhalation and flow profile of each recording. Each model was tested on the remaining audio signals to estimate flow profile. The average estimation error was found to be 10.5±0.3% for estimating flow profile from audio signals. Inhalation flow profile parameters (PIFR, IC and IRT) could then be measured from the estimated flow profile with high accuracy giving information on user inhalation technique. This method may assist in improving patient inhaler adherence and overall disease control. (Author)

  12. Radiation dose estimates and hazard evaluations for inhaled airborne radionuclides. Annual progress report, July 1980-June 1981

    International Nuclear Information System (INIS)

    Mewhinney, J.A.

    1982-04-01

    The objective of this project is to conduct confirmatory research on aerosol characteristics and the resulting radiation dose distribution in animals following inhalation and to provide prediction of health consequences in humans due to airborne radioactivity which might be released in normal operations or under accident conditions during production of nuclear fuel composed of mixed oxides of U and Pu. Four research reports summarize the results of specific areas of research being conducted. The first presents final results for several types of physical chemical characterization accomplished on samples of aerosols collected at an industrial facility during normal fabrication of mixed oxide fuel. Many of these characterizations were also done on aerosol samples collected during animal inhalation exposure procedures for biological studies using these aerosol materials. The second paper reports on the methods development process used for establishing a capability for measurement of the specific surface area of aerosols, an important determinant in the rate of dissolution of particulates deposited in lung. The third paper provides updated information on the retention, distribution and excretion of Pu after inhalation by Beagles of aerosols of either 750 0 C treated UO 2 + PuO 2 , 1750 0 C treated (U,Pu)O 2 or 850 0 C treated pure PuO 2 . This paper also reports the results of the formulation of a biomathematical model useful in describing the results of these three inhalation studies. The fourth paper describes the early results from two studies in which Fischer-344 rats received inhalation exposure to aerosols of (U,Pu)O 2 or pure PuO 2 to determine the relationship of radiation dose to biological response

  13. Radionuclides: Accumulation and Transport in Plants.

    Science.gov (United States)

    Gupta, D K; Chatterjee, S; Datta, S; Voronina, A V; Walther, C

    Application of radioactive elements or radionuclides for anthropogenic use is a widespread phenomenon nowadays. Radionuclides undergo radioactive decays releasing ionizing radiation like gamma ray(s) and/or alpha or beta particles that can displace electrons in the living matter (like in DNA) and disturb its function. Radionuclides are highly hazardous pollutants of considerable impact on the environment, food chain and human health. Cleaning up of the contaminated environment through plants is a promising technology where the rhizosphere may play an important role. Plants belonging to the families of Brassicaceae, Papilionaceae, Caryophyllaceae, Poaceae, and Asteraceae are most important in this respect and offer the largest potential for heavy metal phytoremediation. Plants like Lactuca sativa L., Silybum marianum Gaertn., Centaurea cyanus L., Carthamus tinctorius L., Helianthus annuus and H. tuberosus are also important plants for heavy metal phytoremediation. However, transfer factors (TF) of radionuclide from soil/water to plant ([Radionuclide]plant/[Radionuclide]soil) vary widely in different plants. Rhizosphere, rhizobacteria and varied metal transporters like NRAMP, ZIP families CDF, ATPases (HMAs) family like P1B-ATPases, are involved in the radio-phytoremediation processes. This review will discuss recent advancements and potential application of plants for radionuclide removal from the environment.

  14. An electrochemical approach for removal of radionuclidic contaminants of Eu from 153Sm for effective use in metastatic bone pain palliation.

    Science.gov (United States)

    Chakravarty, Rubel; Chakraborty, Sudipta; Khan, Mohammed Sahiralam; Ram, Ramu; Sarma, Haladhar Dev; Dash, Ashutosh

    2018-03-01

    Thermal neutron activation of 152 Sm [ 152 Sm(n,γ) 153 Sm] using natural or isotopically enriched (by 152 Sm) samarium target is the established route for production of 153 Sm used for preparation of 153 Sm-EDTMP for pain palliation in cancer patients with disseminated bone metastases. However, some long-lived radionuclidic contaminants of Eu, such as, 154 Eu (t ½ =8.6y) are also produced during the target activation process. This leads to detectable amount of Eu radionuclidic contaminants in patients' skeleton even years after administration with therapeutic doses of 153 Sm-EDTMP. Further, the presence of such contaminants in 153 Sm raises concerns related to radioactive waste management. The aim of the present study was to develop and demonstrate a viable method for large-scale purification of 153 Sm from radionuclidic contaminants of Eu. A radiochemical separation procedure adopting electroamalgamation approach has been critically evaluated. The influence of different experimental parameters for the quantitative removal radionuclidic contaminants of Eu from 153 Sm was investigated and optimized. The effectiveness of the method was demonstrated by purification of ~37 GBq of 153 Sm in several batches. As a proof of concept, 153 Sm-EDTMP was administered in normal Wistar rats and ex vivo γ-spectrometry of bone samples were carried out. After carrying out the electrolysis under the optimized conditions, the radionuclidic contaminants of Eu could not be detected in purified 153 Sm solution by γ-spectrometry. The overall yield of 153 Sm obtained after the purification process was >85%. The reliability of this approach was amply demonstrated in several batches, wherein the performance remained consistent. Ex vivo γ-spectrometry of bone samples of Wistar rats administered with 153 Sm-EDTMP (prepared using electrochemically purified 153 Sm) did not show photo peaks corresponding to radionuclidic contaminants of Eu. A viable electrochemical strategy for the large

  15. Benefits and risks of bronchopulmonary lavage: a review

    International Nuclear Information System (INIS)

    Nolibe, D.; Metivier, H.; Masse, R.; Chretien, J.

    1989-01-01

    Studies were conducted in beagle dogs and baboons over a period of 20 years to determine the efficiency of treatment by lung lavage after inhalation of insoluble radioactive particles. The radionuclides tested were 144 Ce in fused clay, 238 Pu, 239 Pu, 241 Am, Pu-TBP, Pu0 2 , UO 2 , and (Pu,U)0 2 . After inhalation of any of these radionuclides, a single lavage of the two lungs removed almost a quarter of the intitial lung burden (ILB) in the two species. When lavage was repeated five times, it removed up to half of the ILB. However, the individual variation was large. For the same radionuclide, lavage efficiency was independent of the ILB. Particle removal was better and continued longer for particles with a long retention half-time. The use of lavage can be combined with that of chelating agents like DTPA. The removal of radioactive particles lenghtened survival time and reduced the severity of pathology. The lavage in itself is safe, and does not induce permanent or progressive pathology. The biomedical risk of the lavage mainly depends on the risks inherent in anaesthesia and the health status of the patient. (author)

  16. Bronchopulmonary lavage and DTPA treatment for the removal of inhaled 239Pu of varied solubility in beagle dogs. II

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Miglio, J.J.; Slauson, D.O.; McClellan, R.O.

    1974-01-01

    The efficacy of bronchopulmonary lavage and chelation therapy was determined for removing 239 Pu from Beagle dogs after inhalation of 239 Pu aerosols of differing in vivo solubility. The four aerosols used were nebulized from a solution of 239 PuCl 4 and heat treated at temperatures of 325, 600, 900, and 1150 0 C, respectively. Six dogs were exposed to each of the four aerosols and three dogs in each group were treated subsequently by lavage and intravenous diethylenetriaminepentaacetic acid (DTPA); three dogs served as untreated controls. Tissue accumulation of 239 Pu in the untreated control dogs at sacrifice 56 days post-exposure, expressed as a percentage of the initial lung burden (ILB), was 6 percent in liver and 9 percent in skeleton for the 325 0 C aerosol group, 1 percent in liver and 2 percent in the skeleton for the 600 0 C group, and less than 0.6 percent in these tissues for the 900 0 and 1150 0 C aerosol groups. Tissue accumulation was 1.0 percent or less of the ILB for all organs in the treated groups of dogs. The urinary excretion of 239 Pu was increased in the treated dogs compared to the control dogs that inhaled the 325 0 C and 600 0 C aerosols and was low in all dogs exposed to the 900 0 and 1150 0 C treated aerosol particles. Ten bronchopulmonary lavage procedures removed a mean of 44 percent of the ILB of 239 Pu from the lungs. The aerosol temperature and resulting differences in solubility of the particles did not influence the efficacy of the lavage procedure. An in vitro solubility test predicted the relative in vivo solubility of the four aerosols. These results are discussed in relation to the choice of therapy and its timing. (U.S.)

  17. Respiratory tract tumors in Syrian hamsters following inhalation of Pu--ZrO2 particles

    International Nuclear Information System (INIS)

    Thomas, R.G.; Smith, D.M.

    1979-01-01

    Inhalation of radionuclide-bearing particles remains one of the most intensely pursued problems concerning the nuclear industry. This route of entry is generally accepted as the most probable, in case of human exposure, with ingestion being the other prominent source of concern. Many laboratory investigations, such as those reported here, continue to evaluate the possible consequences that may present health problems to the public domain. Syrian hamsters of both sexes received either inhaled (INH) PuO 2 /ZrO 2 particles, intravenous (IV) PuO 2 /ZrO 2 microspheres, a combination of INH PuO 2 /ZrO 2 particles and injected PuO 2 /ZrO 2 microspheres, or no radionuclides (controls). The INH particles and IV microspheres were tagged with γ-emitting 57 Co to facilitate whole body counting and establishment of retention curves. Total lung burdens ranged from 8 nCi to 143 nCi. Significant numbers of primary lung tumors (5 to 50% per group) were induced in those animals that received INH exposures. Additional α radiation administered via Pu-laden IV microspheres had little or no effect on tumor production or nonneoplastic, degenerative changes in the respiratory tract

  18. Nonparametric statistical techniques used in dose estimation for beagles exposed to inhaled plutonium nitrate

    International Nuclear Information System (INIS)

    Stevens, D.L.; Dagle, G.E.

    1986-01-01

    Retention and translocation of inhaled radionuclides are often estimated from the sacrifice of multiple animals at different time points. The data for each time point can be averaged and a smooth curve fitted to the mean values, or a smooth curve may be fitted to the entire data set. However, an analysis based on means may not be the most appropriate if there is substantial variation in the initial amount of the radionuclide inhaled or if the data are subject to outliers. A method has been developed that takes account of these problems. The body burden is viewed as a compartmental system, with the compartments identified with body organs. A median polish is applied to the multiple logistic transform of the compartmental fractions (compartment burden/total burden) at each time point. A smooth function is fitted to the results of the median polish. This technique was applied to data from beagles exposed to an aerosol of 239 Pu(NO 3 ) 4 . Models of retention and translocation for lungs, skeleton, liver, kidneys, and tracheobronchial lymph nodes were developed and used to estimate dose. 4 refs., 3 figs., 4 tabs

  19. Model to estimate the local radiation doses to man from the atmospheric release of radionuclides (LWBR development program)

    International Nuclear Information System (INIS)

    Rider, J.L.; Beal, S.K.

    1977-04-01

    A model was developed to estimate the radiation dose commitments received by people in the vicinity of a facility that releases radionuclides into the atmosphere. This model considers dose commitments resulting from immersion in the plume, ingestion of contaminated food, inhalation of gaseous and suspended radioactivity, and exposure to ground deposits. The dose commitments from each of these pathways is explicitly considered for each radionuclide released into the atmosphere and for each daughter of each released nuclide. Using the release rate of only the parent radionuclide, the air and ground concentrations of each daughter are calculated for each position of interest. This is considered to be a significant improvement over other models in which the concentrations of daughter radionuclides must be approximated by separate releases

  20. Radiation load of the electro-thermal production of phosphorus. Part 2. The inhalation dose in road construction

    International Nuclear Information System (INIS)

    Erkens, W.H.H.; Hermans, P.M.J.A.; Timmermans, C.W.M.

    2003-01-01

    The phosphate ore which is processed by Thermphos International in Vlissingen, Netherlands, to produce element phosphorus contains circa 1 Bq per gram uranium 238. As a result of this production process radionuclides are emitted and slags that contain natural radioisotopes are formed. The slags can be used as a building material for roads and water works. During the production of phosphorus the waste material calcinate is formed as well. Operators, working in the production process of phosphorus and laborers, working in road construction and hydraulic engineering inhale radioisotopes. In two articles attention will be paid to the inhalation doses, how the doses are measured, measures that were taken to reduce and control the doses, and the ALARA-principles. This article is focused on the inhalation doses for road construction workers [nl

  1. Vegetation concentration and inventory of metals and radionuclides in the old F-area seepage basin, 904-49G

    International Nuclear Information System (INIS)

    Murphy, C.E. Jr.

    1994-01-01

    Measured concentrations of radionuclides and toxic metals are used to calculate the total inventory of in the vegetation growing on the Old F-Area Seepage Basin. Air concentrations and inhalation doses from exposure to smoke from burning the vegetation are calculated to evaluate the effect of open air burning. Radionuclide inventory is one order of magnitude (10 x) less than those necessary to produce a 1 mrem dose. Air concentrations of toxic metals are less than one third the permissible occupational dose

  2. The modelling of external exposure and inhalation pathways in COSYMA

    International Nuclear Information System (INIS)

    Brown, J.; Simmonds, JR.; Ehrhardt, J.; Hasemann, I.

    1991-01-01

    Following an accidental release of radionuclides to atmosphere the major direct exposure pathways of concern are: external irradiation from material in the cloud; internal exposure following inhalation of material in the cloud; external irradiation from material deposited on the ground; and external irradiation due to contamination of skin and clothes. In addition material resuspended from the ground can be inhaled and lead to internal exposure. In this paper the way that these exposure pathways are modelled in COSYMA is described. At present in COSYMA external exposure from deposited material is modelled using a dataset of doses per unit deposit of various radionuclides. This dataset, is based on activity deposited on undisturbed soil. The basic data are for doses outdoors and shielding factors are used to estimate doses for people indoors. Various groups of people spending different amounts of time indoors and out can be considered and shielding factors appropriate to three building types can be adopted. A more complex model has also been developed to predict radiation exposure following deposition to different surfaces in the environment. This model called EXPURT is briefly described in this paper. Using EXPURT, doses as a function of time after a single deposit have been calculated for people living in three types of area. These results are described in the paper and compared with those that are currently used in COSYMA. The paper will also discuss what future work is required in this area and the adequacy of existing models

  3. Technetium removal from aqueous wastes

    International Nuclear Information System (INIS)

    Fletcher, P.A.; Jones, C.P.; Junkison, A.R.; Turner, A.D.; Kavanagh, P.R.

    1992-03-01

    The research discussed in this report has compared several ''state of the art'' techniques for the removal of traces of the radionuclide, technetium, from aqueous wastes. The techniques investigated were: electrochemical reduction to an insoluble oxide, electrochemical ion exchange, seeded ultrafiltration and chemical reduction followed by filtration. Each technique was examined using a simulant based upon the waste generated by the Enhanced Actinide Removal Plant (EARP) at Sellafield. The technique selected for further investigation was direct electrochemical reduction which offers an ideal route for the removal of technetium from the stream (DFs 10-100) and can be operated continuously with a low power consumption 25 kW for the waste generated by EARP. Cell designs for scale up have been suggested to treat the 1000m 3 of waste produced every day. Future work is proposed to investigate the simultaneous removal of other key radionuclides, such as ruthenium, plutonium and cobalt as well as scale up of the resulting process and to investigate the effect of these other radionuclides on the efficiency of the electrochemical reduction technique for the removal of technetium. Total development and full scale plant costs are estimated to be of the order of 5 pounds - 10M, with a time scale of 5 -8 years to realisation. (author)

  4. TESTING OF A FULL-SCALE ROTARY MICROFILTER FOR THE ENHANCED PROCESS FOR RADIONUCLIDES REMOVAL

    Energy Technology Data Exchange (ETDEWEB)

    Herman, D; David Stefanko, D; Michael Poirier, M; Samuel Fink, S

    2009-01-01

    Savannah River National Laboratory (SRNL) researchers are investigating and developing a rotary microfilter for solid-liquid separation applications in the Department of Energy (DOE) complex. One application involves use in the Enhanced Processes for Radionuclide Removal (EPRR) at the Savannah River Site (SRS). To assess this application, the authors performed rotary filter testing with a full-scale, 25-disk unit manufactured by SpinTek Filtration with 0.5 micron filter media manufactured by Pall Corporation. The filter includes proprietary enhancements by SRNL. The most recent enhancement is replacement of the filter's main shaft seal with a John Crane Type 28LD gas-cooled seal. The feed material was SRS Tank 8F simulated sludge blended with monosodium titanate (MST). Testing examined total insoluble solids concentrations of 0.06 wt % (126 hours of testing) and 5 wt % (82 hours of testing). The following are conclusions from this testing.

  5. Radionuclide concentration in ground-level air in 1991 in North Germany

    International Nuclear Information System (INIS)

    Kolb, W.; Wershofen, H.

    1992-03-01

    The activity concentration of various fission products and some other radionuclides (e.g. Be-7, Na-22, K-40 and Pb-210) contained in ground-level air were determined by gamma-ray spectroscopy. Weekly and mean monthly activity concentrations measured in Brunswick and Berlin are tabulated. From 1990 to 1991 the Cs-137 concentration in Brunswick decreased only slightly. It was less than 0.1% of that in 1986 but due to resuspended soil dust still three times higher than in 1985. Occasionally, traces of activation products were detected such as Cr-51, Mn-54 or Co-60 in Januray and February in Brunswick and Berlin. The effective equivalent dose due to the inhalation of fission products is estimated to be less than 0.1% of the Pb-210 inhalation dose. (orig.) [de

  6. Application of radionuclide imaging in hyperparathyroidism

    International Nuclear Information System (INIS)

    Zheng Yumin; Yan Jue

    2011-01-01

    Hyperparathyroidism (HPT) is overactivity of the parathyroid glands resulting in excess production of parathyroid hormone. Excessive parathyroid hormone secretion may be due to problems in the glands themselves, or may be secondary HPT. The diagnosis is mainly based on the patient's medical history and biochemical tests. The best treatment nowadays is surgical removal of the overactive parathyroid glands or adenoma. The imaging methods for the preoperative localization diagnosis include radionuclide imaging,ultrasonography, CT, MRI, etc. This article was a summary of HPT radionuclide imaging. (authors)

  7. Tumorigenic responses from single or repeated inhalation exposures to relatively insoluble aerosols of Ce-144

    International Nuclear Information System (INIS)

    Boecker, B.B.; Hahn, F.F.; Mauderly, J.L.; McClellan, R.O.

    1980-01-01

    Human occupational or environmental inhalation exposures may involve repeated or chronic exposures, but most laboratory studies of inhaled radionuclides have involved single exposures. This study was designed to compare the biological effects of repeated inhalation exposures of dogs to a relatively insoluble form of 144 Ce with existing data for singly-exposed dogs that had the same cumulative dose to the lungs two years after exposure. To date, the biological effects observed in these repeatedly-exposed dogs have been substantially different from those seen in singly-exposed dogs, particularly during the first 5 years after the initial exposure. Although pulmonary hemangiosarcoma was the prominent biological effect seen in singly-exposed dogs between 2 and 4 years after exposure, no lung tumors were seen during the 5 years after the first of the repeated exposures. This response plus other clinical observations are discussed in relation to the patterns of dose rate and cumulative dose for the different exposure conditions. (H.K.)

  8. Early diagnosis of morphologic-functional changes of the airways by a simple method of inhalation scintigraphy

    International Nuclear Information System (INIS)

    Flierdt, E. van de; Bauer, R.; Laubenbacher, C.; Didic, M.; Langhammer, H.R.; Pabst, H.W.

    1992-01-01

    In order to validate a method of inhalation scintigraphy with 99m Tc-labeled human serum albumin in the early diagnosis of morphologic-functional changes of the airways 35 volunteers and patients (12 healthy non-smokers and smokers each, 11 patients with bronchitis) were studied. Deposition of the aerosol immediately after inhalation was calculated quantitatively by a ROI technique and qualitatively (scoring of central deposition, homogeneity, and recognizability of lung outline). Additionally, the regional clearance of the inhaled aerosol was determined by continuous lung imaging up to 60 min (mainly regional mucociliary removal rates). Discrimination between healthy volunteers and patients with bronchitis was possible by means of deposition patterns immediately after inhalation. On the other hand, no differences could be recognized in this way between healthy non-smokers and smokers. Regional mucociliary removal was higher in non-smokers than in smokers, but there was no difference between smokers and patients with bronchitis. (orig.) [de

  9. Sorbent application on the base of chitosan for radionuclides separation

    International Nuclear Information System (INIS)

    Pivarciova, L.

    2016-01-01

    Radioactive waste contains enormous amounts of radionuclides, which pollute the environment and can cause serious chemical and radiological toxicity threats to lower and higher living organism. Alternative process for the removal of heavy metal ions and radionuclides is sorption, which utilizes various certain natural materials of biological origin. Amino-polysaccharide-based sorbents e.g. chitosan represent suitable materials for binding of metal oxo-anion species because of numerous functional groups -OH and -NH_2 because of their suitable H-bond donor and acceptor sites. The sorbents on the base chitosan prepared through chemical modification were used for removal and separation certain radionuclides from aqueous media. The aim of this work was the study of physicochemical properties of prepared sorbents. The specific surface of sorbents was characterized with BET methods. Point of zero charge was identified with potentiometric titration. The size of particles and shape of sorbents were determined by scanning electron microscope. The sorption experiments for selected radionuclides were conducted under static and dynamic conditions. The effect of various parameters on the sorption "9"9"mTc, "6"0Co and the effect of pH on the separation of radionuclide mixture in the solution were studied. (author)

  10. Dose conversion factors for inhalation applicable to the mining and milling of radioactive ores

    International Nuclear Information System (INIS)

    Hartley, B.M.

    1992-01-01

    The ICRP recommended revised dose limits for exposure to ionising radiation in November 1990. As well as reducing the annual occupational dose equivalent limit to an average of 20 mSv over 5 years, modified organ weighting factors were recommended, reflecting improved understanding of cancer risk factors for tissues and organs. The adjustment of weighting factors means that derived air concentrations conversion factors and annual limits on intake for exposure to airborne radionuclides are not simply modified by the ratio of the old to the new limits. A recalculation of these factors for radionuclides of interest in the mining and milling of radioactive ores is presented. A computer program for this purpose, based on the ICRP 30 inhalation model, is described. Rapid calculations of dose conversion factors are possible for the naturally occurring radionuclides in the 235 U, 238 U and 232 Th decay chains for which data are given in the supplements to ICRP 30. 7 refs., 12 tabs., 5 figs

  11. Selective flotation for the removal of radionuclides from contaminated soil

    International Nuclear Information System (INIS)

    Miller, J.D.; Yu, Q.; Lu, Y.Q.

    1995-01-01

    Low-level radioactive contaminated soils (10--500 pci/gm) created by defense-related activities at certain Superfund sites, such as Nevada Test Site (NTS), is a current environmental concern. Many of these contaminated sites may require appropriate cleanup and restoration, which could cost billions of dollars and put tremendous pressure on limited financial resources. Therefore, the development of a selective flotation process to separate such radionuclides from contaminated soils should be considered. In this study, both a pure depleted UO 2 sample and three synthetic UO 2 /soil mixtures were used to evaluate surface chemistry features and to examine the possibility for the flotation of fine UO 2 particles from selected soils. It was intended that this model system would be a reasonable representation of contaminated soils such as those found the Nevada Test Site which are reported to be contaminated by PuO 2 fallout. The effect of reagent schedule, particle size distribution, and surface charge are discussed with respect to the flotation separation of the UO 2 /soil mixtures. It was found that both commercial fatty acids and reagent grade sodium oleate are effective collectors for UO 2 flotation provided the pH is adjusted to the range of pH 8--9. The bench-scale flotation results successfully demonstrated that froth flotation technology can be used to remove UO 2 from such model contaminated soils with appropriate flotation chemistry conditions which depend on the soil characteristics and other pretreatment procedures

  12. Inhaled Steroids

    Science.gov (United States)

    ... considerations when your dosage changes. What about side effects and inhaled steroids? The most common side effects with inhaled steroids ... inhaled steroid has much less potential for side effects than steroid pills or syrups. There have been concerns regarding ...

  13. Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

    International Nuclear Information System (INIS)

    Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

    1988-09-01

    Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs

  14. Limiting values of radionuclide intake and air concentration and dose conversion factors for inhalation, submersion, and ingestion: Federal guidance report No. 11

    Energy Technology Data Exchange (ETDEWEB)

    Eckerman, K.F.; Wolbarst, A.B.; Richardson, A.C.B.

    1988-09-01

    Radiation protection programs for workers are based, in the United States, on a hierarchy of limitations stemming from Federal guidance approved by the President. This guidance, which consists of principles, policies, and numerical primary guides, is used by Federal agencies as the basis for developing and implementing their own regulatory standards. The primary guides are usually expressed in terms of limiting doses to workers. The protection of workers against taking radioactive materials into the body, however, is accomplished largely through the use of regulations based on derived guides expressed in terms of quantities or concentrations of radionuclides. The values of these derived guides are chosen so as to assure that workers in work environments that conform to them are unlikely to receive radiation doses that exceed the primary guides. The purpose of the present report is to set forth derived guides that are consistent with current Federal radiation protection guidance. They are intended to serve as the basis for regulations setting upper bounds on the inhalation and ingestion of, and submersion in, radioactive materials in the workplace. The report also includes tables of exposure-to-dose conversion factors, for general use in assessing average individual committed doses in any population that is adequately characterized by Reference Man. 38 refs.

  15. Inhalant Abuse

    Science.gov (United States)

    ... is when you pour the product into a bag, hold it over your mouth and nose, and inhale. How is inhalant abuse diagnosed? If you think your child is abusing inhalants, talk to them. Be honest and open. Tell them ...

  16. Case report: Inhaled foreign body mismanaged as TB, finally removed using a rigid bronchoscopy after 6 years of impaction

    Directory of Open Access Journals (Sweden)

    Justin Rubena Lumaya

    2016-02-01

    Full Text Available Foreign body aspiration is an important cause of mortality in children aged less than three years. Foreign body (FB inhalation can pose diagnostic and therapeutic challenges, especially in longstanding cases and complications such as recurrent pneumonia, lung collapse and lung abscess may develop. We report a case of an 11-year old boy with foreign body impacted in his bronchus for six years, which was mistakenly managed as pulmonary tuberculosis. Radiological evidence confirmed the diagnosis and a rigid bronchoscopy was used to remove the metallic foreign body. The standard of care for the management of a FB in a bronchus is a rigid bronchoscopy; however flexible bronchoscopy can be used, especially in adults. A thorough history with radiological evidence are essential and sometimes, followed by a diagnostic bronchoscopy.

  17. Granulometric determinations and inhalation dose assessment for atmospheric aerosol contaminated by 137Cs

    International Nuclear Information System (INIS)

    Castellani, C.M.; Luciani, A.; Oliviero, L.; Donato, R.

    1996-07-01

    During the redevelopment of Brescia freight-yard a measurement campaign of atmospheric aerosol was carried out: in fact a 137 Cs ground contamination, caused by the permanence of wagons carrying iron materials contaminated by this radionuclide, had been found out. During the redevelopment phases of excavation and can filling the workers were exposed to the danger of radioactive aerosol inhalation. The aim of the measurement campaign was to test the aerosol sampling and granulometric analysis methodologies with their sensitivity related to the inhalation dose assessments. The results of both aerosuspended mass and activity, evaluated by means of a portable cascade impactor, are presented. The granulometries have been interpolated with a log normal distribution using an iterative routine minimizing the square deviation between the calculated and experimental data. The results related to the dose assessments are also presented. These evaluations have been carried out using both the granulometric information obtained and the more recent models (ICRP 66) both the total concentration data and the dose coefficients referring to the standard conditions of ICRP 68 and of the Italian law (D.Lgs. 230/95). Furthermore the significance and the reliability of the dose assessments referring to the different methodologies are discussed, also in relation to the possibility of using this sampling methodologies for other radionuclides and different exposure conditions

  18. Radionuclide contaminant analysis of small mammels, plants and sediments within Mortandad Canyon, 1994

    International Nuclear Information System (INIS)

    Bennett, K.; Biggs, J.; Fresquez, P.

    1996-01-01

    Small mammals, plants and sediments were sampled at one upstream location (Site 1) and two downstream locations (Site 2 and Site 3) from the National Pollution Discharge Elimination System outfall number-sign 051-051 in Mortandad Canyon, Los Alamos County, New Mexico. The purpose of the sampling was to identify radionuclides potentially present, to quantitatively estimate and compare the amount of radionuclide uptake at specific locations (Site 2 and Site 3) within Mortandad Canyon to an upstream site (Site 1), and to identify the primary mode (inhalation ingestion, or surface contact) of contamination to small mammals. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. In addition, three composite samples were also collected for plants and sediments at each site. Samples were analyzed for 241 Am, 90 Sr, 238 Pu, 239 Pu, and total U. With the exception of total U, all mean radionuclide concentrations in small mammal carcasses and sediments were significantly higher at Site 2 than Site 1 or Site 3. No differences were detected in the mean radionuclide concentration of plant samples between sites. However, some radionuclide concentrations found at all three sites were higher than regional background. No differences were found between mean carcass radionuclide concentrations and mean pelt radionuclide concentrations, indicating that the two primary modes of contamination may be equally occurring

  19. RADIONUCLIDE DISPERSION RATES BY AEOLIAN, FLUVIAL, AND POROUS MEDIA TRANSPORT

    International Nuclear Information System (INIS)

    Walton, J.; Goodell, P.; Brashears, C.; French, D.; Kelts, A.

    2005-01-01

    Radionuclide transport was measured from high grade uranium ore boulders near the Nopal I Site, Chihuahua, Mexico. High grade uranium ore boulders were left behind after removal of a uranium ore stockpile at the Prior High Grade Stockpile (PHGS). During the 25 years when the boulder was present, radionuclides were released and transported by sheetflow during precipitation events, wind blown resuspension, and infiltration into the unsaturated zone. In this study, one of the boulders was removed, followed by grid sampling of the surrounding area. Measured gamma radiation levels in three dimensions were used to derive separate dispersion rates by the three transport mechanisms

  20. RADIONUCLIDE DISPERSION RATES BY AEOLIAN, FLUVIAL, AND POROUS MEDIA TRANSPORT

    Energy Technology Data Exchange (ETDEWEB)

    J. Walton; P. Goodell; C. Brashears; D. French; A. Kelts

    2005-07-11

    Radionuclide transport was measured from high grade uranium ore boulders near the Nopal I Site, Chihuahua, Mexico. High grade uranium ore boulders were left behind after removal of a uranium ore stockpile at the Prior High Grade Stockpile (PHGS). During the 25 years when the boulder was present, radionuclides were released and transported by sheetflow during precipitation events, wind blown resuspension, and infiltration into the unsaturated zone. In this study, one of the boulders was removed, followed by grid sampling of the surrounding area. Measured gamma radiation levels in three dimensions were used to derive separate dispersion rates by the three transport mechanisms.

  1. Particle count monitoring of reverse osmosis water treatment for removal of low-level radionuclides

    International Nuclear Information System (INIS)

    Moritz, E.J.; Hoffman, C.R.; Hergert, T.R.

    1995-01-01

    Laser diode particle counting technology and analytical measurements were used to evaluate a pilot-scale reverse osmosis (RO) water treatment system for removal of particulate matter and sub-picocurie low-level radionuclides. Stormwater mixed with Waste Water Treatment Plant (WWTP) effluent from the Rocky Flats Environmental Technology Site (RFETS), formerly a Department of Energy (DOE) nuclear weapons production facility, were treated. No chemical pretreatment of the water was utilized during this study. The treatment system was staged as follows: multimedia filtration, granular activated carbon adsorption, hollow tube ultrafiltration, and reverse osmosis membrane filtration. Various recovery rates and two RO membrane models were tested. Analytical measurements included total suspended solids (TSS), total dissolved solids (TDS), gross alpha (α) and gross beta (β) activity, uranium isotopes 233/234 U and 238 U, plutonium 239/240 Pu, and americium 241 Am. Particle measurement between 1--150 microns (μ) included differential particle counts (DPC), and total particle counts (TPC) before and after treatment at various sampling points throughout the test. Performance testing showed this treatment system produced a high quality effluent in clarity and purity. Compared to raw water levels, TSS was reduced to below detection of 5 milligrams per liter (mg/L) and TDS reduced by 98%. Gross α was essentially removed 100%, and gross β was reduced an average of 94%. Uranium activity was reduced by 99%. TPC between 1-150μ were reduced by an average 99.8% to less than 1,000 counts per milliliter (mL), similar in purity to a good drinking water treatment plant. Raw water levels of 239/240 Pu and 241 Am were below reliable quantitation limits and thus no removal efficiencies could be determined for these species

  2. Activity concentrations of radionuclides in energy production from peat, wood chips and straw

    International Nuclear Information System (INIS)

    Hedvall, R.

    1997-04-01

    In this thesis quantitative analyses of radionuclide concentrations in bioenergy fuels such as peat, wood chips and straw are presented. For comparison a brief description is included of radionuclide concentrations and radiation doses from other sources of power and also from some industrial applications. Radioactive potassium is found in most materials and is the most easily detected radionuclide in fuels. It's activity concentration in Bq/kg normally dominates over the concentration of other natural radionuclides. The radiation dose from K in emission from combustion is nevertheless negligible. The most important radionuclides in the dose to man are the U- and Th-isotopes and 210 Pb and 210 Po. 137 Cs is the most common nuclide among the fission products in fallout from the Chernobyl accident. Compared to natural nuclides, the contribution from emission of 137 Cs is less than a few percent of the total dose to the population. A total dose of approx. only a few μSv from inhalation can be calculated from the emission of a district heating plant in Sweden. This dose can be compared with the annual dose limit to the public from nuclear industry, which is 0.1 mSv and the global collective effective dose of 5 manSv/year. 143 refs

  3. Uncertainties in Cancer Risk Coefficients for Environmental Exposure to Radionuclides. An Uncertainty Analysis for Risk Coefficients Reported in Federal Guidance Report No. 13

    Energy Technology Data Exchange (ETDEWEB)

    Pawel, David [U.S. Environmental Protection Agency; Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL; Nelson, Christopher [U.S. Environmental Protection Agency

    2007-01-01

    Federal Guidance Report No. 13 (FGR 13) provides risk coefficients for estimation of the risk of cancer due to low-level exposure to each of more than 800 radionuclides. Uncertainties in risk coefficients were quantified in FGR 13 for 33 cases (exposure to each of 11 radionuclides by each of three exposure pathways) on the basis of sensitivity analyses in which various combinations of plausible biokinetic, dosimetric, and radiation risk models were used to generate alternative risk coefficients. The present report updates the uncertainty analysis in FGR 13 for the cases of inhalation and ingestion of radionuclides and expands the analysis to all radionuclides addressed in that report. The analysis indicates that most risk coefficients for inhalation or ingestion of radionuclides are determined within a factor of 5 or less by current information. That is, application of alternate plausible biokinetic and dosimetric models and radiation risk models (based on the linear, no-threshold hypothesis with an adjustment for the dose and dose rate effectiveness factor) is unlikely to change these coefficients by more than a factor of 5. In this analysis the assessed uncertainty in the radiation risk model was found to be the main determinant of the uncertainty category for most risk coefficients, but conclusions concerning the relative contributions of risk and dose models to the total uncertainty in a risk coefficient may depend strongly on the method of assessing uncertainties in the risk model.

  4. Dependence on age at intake of committed dose equivalents from radionuclides

    International Nuclear Information System (INIS)

    Adams, N.

    1981-01-01

    The dependence of committed dose equivalents on age at intake is needed to assess the significance of exposures of young persons among the general public resulting from inhaled or ingested radionuclides. The committed dose equivalents, evaluated using ICRP principles, depend on the body dimensions of the young person at the time of intake of a radionuclide and on subsequent body growth. Representation of growth by a series of exponential segments facilitates the derivation of general expressions for the age dependence of committed dose equivalents if metabolic models do not change with age. The additional assumption that intakes of radionuclides in air or food are proportional to a person's energy expenditure (implying age-independent dietary composition) enables the demonstration that the age of the most highly exposed 'critical groups' of the general public from these radionuclides is either about 1 year or 17 years. With the above assumptions the exposure of the critical group is less than three times the exposure of adult members of the general public. Approximate values of committed dose equivalents which avoid both underestimation and excessive overestimation are shown to be obtainable by simplified procedures. Modified procedures are suggested for use if metabolic models change with age. (author)

  5. Characteristics of particulate radionuclides in the atmospheric surface layer of the 30-km zone of Chernobyl

    International Nuclear Information System (INIS)

    Garger, E.K.; Kashpur, V.A.; Sazhenyuk, A.D.; Paretzke, H.G.; Roth, P.; Tschiersch, J.

    2002-01-01

    For the inhalation dose assessment, reliable estimations are necessary of the average volume concentration of particle bound radionuclides in the atmosphere specifying the nuclide composition, the activity distribution in the different particle size ranges and the solubility characteristics of the nuclides. For that purpose, the analysis of measurement series is presented of the daily average activity concentrations of 137 Cs and 144 Ce and their temporal and spatial variability. From 1986 till 1994, samples were taken with high-volume samplers and multicascade impactors; the number concentrations of aerosol particles and the number concentrations of 'hot' particles were determined for different conditions with an Aerosol Particle Sizer and a Rotating Arm Impactor. The data demonstrate a decrease the atmospheric concentrations of 137 Cs and 144 Ce with time larger than caused by radioactive decay alone. A statistical analysis showed a high level of fluctuations in the concentration of radionuclides in air with maxima exceeding the annual average by 10 to 20 times. The analysis of 88 experimental radioactivity size distributions at Zapolie and Pripyat for winddriven resuspension conditions have shown that the measured distributions are generally very wide and differ from the log-normal distribution in the most cases. At Zapolie, the mean air concentrations of 137 Cs, discriminated in four size ranges, showed an increasing part of inhalable particles with time since the accident. In 1993, the inhalable fraction was about 48% of the total concentration. The size distribution of atmospheric 137 Cs particulate activity during these periods of enhanced resuspension showed a similar common shape with two maxima, the first in the 2-4 μm range, and the second in the 12-20 μm range. The estimated radioactive loading of particles showed an enrichment of resuspended radionuclides compared with soil particles. The highest enrichment factor was found for large particles, the

  6. Removal of contaminated asphalt layers by using heat generating powder metallic systems

    International Nuclear Information System (INIS)

    Barinov, A.S.; Karlina, O.K.; Ojovan, M.I.

    1996-01-01

    Heat generating systems on the base of powder metallic fuel were used for the removal of contaminated asphalt layers. Decontamination of spots which had complex geometric form was performed. Asphalt layers with deep contamination were removed essentially all radionuclides being retained in asphalt residue. Only a small part (1 - 2 %) of radionuclides could pass to combustion slag. No radionuclides were detected in aerosol-gas phase during decontamination process

  7. Ecological reconcentrations of radionuclides released by nuclear industry

    International Nuclear Information System (INIS)

    Schaeffer, R.

    1977-01-01

    An attempt is made to assess the relative importance of the various pathways to man by relating the doses that in the most unfavorable conditions might result from long-term environmental accumulation of the radionuclides to the doses resulting from air inhalation or water ingestion only. For instance, for 131 I released in air, the ratio may reach a value of 1,000 from milk consumption and 3 from consumption of leafy vegetables. For 137 Cs released in water, the ratio may reach a value of 20 from the food chain contamination and 500 on account of external exposure from sediments. However, in spite of these high ratios, the absolute values of the total doses received remain low since the exposures corresponding to air inhalation or water ingestion are usually unsignificant. For water releases, attention is called on the misinterpretations that might result from generalizing the concentration factor values reported in the literature on account of their variations both in time and space: this factor ought to be calculated for each point of the environment on the basis of hydrological data [fr

  8. RADTRAD: A simplified model for RADionuclide Transport and Removal And Dose estimation

    International Nuclear Information System (INIS)

    Humphreys, S.L.; Miller, L.A.; Monroe, D.K.; Heames, T.J.

    1998-04-01

    This report documents the RADTRAD computer code developed for the U.S. Nuclear Regulatory Commission (NRC) Office of Nuclear Reactor Regulation (NRR) to estimate transport and removal of radionuclides and dose at selected receptors. The document includes a users' guide to the code, a description of the technical basis for the code, the quality assurance and code acceptance testing documentation, and a programmers' guide. The RADTRAD code can be used to estimate the containment release using either the NRC TID-14844 or NUREG-1465 source terms and assumptions, or a user-specified table. In addition, the code can account for a reduction in the quantity of radioactive material due to containment sprays, natural deposition, filters, and other natural and engineered safety features. The RADTRAD code uses a combination of tables and/or numerical models of source term reduction phenomena to determine the time-dependent dose at user-specified locations for a given accident scenario. The code system also provides the inventory, decay chain, and dose conversion factor tables needed for the dose calculation. The RADTRAD code can be used to assess occupational radiation exposures, typically in the control room; to estimate site boundary doses; and to estimate dose attenuation due to modification of a facility or accident sequence

  9. Infant doses from the transfer of radionuclides in mothers' milk

    International Nuclear Information System (INIS)

    Harrison, J.D.; Smith, T.J.; Phipps, A.W.

    2003-01-01

    Assessments of potential internal exposures of the child following radionuclide intakes by the mother require consideration of transfers during lactation as well as during pregnancy. Current ICRP work on internal dosimetry includes the estimation of radiation doses to newborn infants from radionuclides ingested in mothers' milk. Infant doses will be calculated for maternal intakes by ingestion or inhalation of the radionuclides, radioisotopes of 31 elements, for which fetal dose coefficients have been published. In this paper, modelling approaches are examined, concentrating on models developed for iodine, caesium, polonium, alkaline earth elements and the actinides. Comparisons of model predictions show maximum overall transfer to milk following maternal ingestion during lactation of about 30% of ingested activity for 131 I, 20% for 45 Ca and 137 Cs, 10% for 90 Sr, 1% for 210 Po and low values of less than 0.01% for 239 Pu and 241 Am. The corresponding infant doses from milk consumption are estimated in preliminary calculations to be about two to three times the adult dose for 45 Ca and 131 I, 70-80% of the adult dose for 90 Sr, about 40% for 137 Cs, 20% for 210 Po, and 239 Pu and 241 Am. Infant doses from radionuclides in breast milk are compared with doses to the offspring resulting from in utero exposures during pregnancy. (author)

  10. Removal of radionuclides from radioactive effluents of Purex origin using biomass banana pith as sorbant

    International Nuclear Information System (INIS)

    Ramanujam, A.; Dhami, P.S.; Kannan, R.; Das, S.K.; Naik, P.W.; Gopalakrishnan, V.; Kansra, V.P.; Balu, K.

    1998-06-01

    Investigations have been carried out on the applicability of dried banana pith (inner stem) for the sorption of various radionuclides viz. U, Pu, 241 Am, 144 Ce, 147 Pm, 152+154 Eu and 137 Cs which are generally present at trace level in Purex process waste effluents. The sorption of trivalent radionuclides as well as tetravalent plutonium was found to be high at pH 2, whereas sorption of uranium was found to be maximum at pH 6. Cesium was not found to be sorbed. 241 Am sorption was investigated in detail as a representative element of trivalent actinides and fission products to study the general trend. Though its sorption was kinetically slow, near-quantitative sorption was observed on prolonged contact. 241 Am sorption was studied in presence of NaNO 3 (up to 1 M) and Nd(III) up to 500 mg/l. Whereas no significant change in distribution ratios (D) was observed in the presence of NaNO 3 , it increased with neodymium concentration in the range tested. This indicates the effectiveness of the biomass as sorbent even in presence of sodium salts. Sorbed metal ions could be recovered by leaching with 2 M nitric acid. The dried biomass samples prepared from different sources were found to be stable for months and gave similar results on testing. The biomass was tested for its applicability for sorbing radionuclides present in Purex evaporator condensate and diluted high level waste solution on once through basis. The sorption capacity of banana pith for trivalent actinide-lanthanide is in the range of 60 mg/g banana pith. The results indicate that the biomass can be used effectively for the treatment of Purex Waste effluents for the removal of strontium, tri- and tetravalent actinides and fission products. The biomass was also tested for the sorption of toxic metal ions viz. Sr, Hg, Pb, Cr, Cd, and As from a nitrate solution at pH 2 and 4. D values followed the order Hg>Sr>Cd>Pb at pH 2, with Cr and As showing no uptake. These results indicate the potential of this

  11. Radionuclides in peat bogs and energy peat

    International Nuclear Information System (INIS)

    Helariutta, K.; Rantavaara, A.; Lehtovaara, J.

    2000-06-01

    The study was aimed at improving the general view on radionuclides contents in energy peat produced in Finland. The annual harvest of fuel peat in 1994 was studied extensively. Also thirteen peat bogs used for peat production and one bog in natural condition were analysed for vertical distributions of several radionuclides. These distributions demonstrate the future change in radioactivity of energy peat. Both natural nuclides emitting gamma radiation ( 238 U, 235 U, 232 Th, 226 Ra, 40 K) and radiocaesium ( 137 Cs, 134 Cs) origin in fallout from a nuclear power plant accident (1986) and in atmospheric nuclear weapon tests were analysed. The beta and alpha active natural nuclides of lead and polonium ( 210 Pb, 210 Po) were determined on a set of peat samples. These nuclides potentially contribute to radiation exposure through inhalation when partially released to atmosphere during combustion of peat. The activity concentrations of natural radionuclides often increased towards the deepest peat bog layers whereas the radioactive caesium deposited from atmosphere was missing in the deep layers. In undisturbed surface layers of a natural bog and peat production bogs the contents of 210 Pb and 210 Po exceeded those of the deeper peat layers. The nuclides of the uranium series in the samples were generally not in radioactive equilibrium, as different environmental processes change their activity ratios in peat. Radiation exposure from handling and utilisation of peat ash was estimated with activity indices derived from the data for energy peat harvested in 1994. Intervention doses were exceeded in a minor selection of samples due to 137 Cs, whereas natural radionuclides contributed very little to the doses. (orig.)

  12. RIVER-RAD, Radionuclide Transport in Surface Waters

    International Nuclear Information System (INIS)

    1996-01-01

    1 - Description of program or function: RIVER-RAD assesses the potential fate of radionuclides released to rivers. The model is simplified in nature and is intended to provide guidance in determining the potential importance of the surface water pathway, relevant transport mechanisms, and key radionuclides in estimating radiological dose to man. 2 - Method of solution: A compartmental linear transfer model is used in RIVER-RAD. The river system model in the code is divided into reaches (compartments) of equal size, each with a sediment compartment below it. The movement of radionuclides is represented by a series of transfers between the reaches, and between the water and sediment compartments of each reach. Within each reach (for both the water and sediment compartments), the radionuclides are assumed to be uniformly mixed. Upward volatilization is allowed from the water compartment, and the transfer of radionuclides between the reaches is determined by the flow rate of the river. Settling and resuspension velocities determine the transfer of absorbed radionuclides between the water and sediment compartments. Radioactive decay and decay-product buildup are incorporated into all transport calculations for all radionuclide chains specified by the user. Each nuclide may have unique input and removal rates. Volatilization and radiological decay are considered as linear rate constants in the model. 3 - Restrictions on the complexity of the problem: None noted

  13. Characterisation of working conditions for handling radionuclides

    International Nuclear Information System (INIS)

    Feer, Y. van der

    1980-01-01

    In this paper simple formulae are given for estimating the limiting amount for different working conditions. The formulae are based on a rude estimation of the radiation hazard for different modes of exposure. The hazards considered are external radiation hazard for workers and inhalation hazard for workers and members of the public. For radiation workers exposure is considered to be acceptable if the average effective dose-equivalent is limited to 5 m Sv (0.5 rem) per year. For members of the public it is assumed that the average effective dose-equivalent must be limited to 50 Sv (5 mrem) per year. Correction factors are provided for situations where more than one radionuclide is being handled. (U.K.)

  14. Estimation of inhalation flow profile using audio-based methods to assess inhaler medication adherence

    Science.gov (United States)

    Lacalle Muls, Helena; Costello, Richard W.; Reilly, Richard B.

    2018-01-01

    Asthma and chronic obstructive pulmonary disease (COPD) patients are required to inhale forcefully and deeply to receive medication when using a dry powder inhaler (DPI). There is a clinical need to objectively monitor the inhalation flow profile of DPIs in order to remotely monitor patient inhalation technique. Audio-based methods have been previously employed to accurately estimate flow parameters such as the peak inspiratory flow rate of inhalations, however, these methods required multiple calibration inhalation audio recordings. In this study, an audio-based method is presented that accurately estimates inhalation flow profile using only one calibration inhalation audio recording. Twenty healthy participants were asked to perform 15 inhalations through a placebo Ellipta™ DPI at a range of inspiratory flow rates. Inhalation flow signals were recorded using a pneumotachograph spirometer while inhalation audio signals were recorded simultaneously using the Inhaler Compliance Assessment device attached to the inhaler. The acoustic (amplitude) envelope was estimated from each inhalation audio signal. Using only one recording, linear and power law regression models were employed to determine which model best described the relationship between the inhalation acoustic envelope and flow signal. Each model was then employed to estimate the flow signals of the remaining 14 inhalation audio recordings. This process repeated until each of the 15 recordings were employed to calibrate single models while testing on the remaining 14 recordings. It was observed that power law models generated the highest average flow estimation accuracy across all participants (90.89±0.9% for power law models and 76.63±2.38% for linear models). The method also generated sufficient accuracy in estimating inhalation parameters such as peak inspiratory flow rate and inspiratory capacity within the presence of noise. Estimating inhaler inhalation flow profiles using audio based methods may be

  15. Radionuclide characterization and associated dose from long-lived radionuclides in close-in fallout delivered to the marine environment at Bikini and Enewetak Atoll

    International Nuclear Information System (INIS)

    Noshkin, V. E.; Robison, W. L.

    1998-01-01

    Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the United States as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 Mt (Mt TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for 10's of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarse sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently about 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is dominated by

  16. RSAC-6, Gamma doses, inhalation and ingestion doses, fission products inventory after fission products release

    International Nuclear Information System (INIS)

    Wenzel, Douglas R.; Schrader, Brad J.

    2007-01-01

    1 - Description of program or function: RSAC-6 is the latest version of the program RSAC (Radiological Safety Analysis Computer Program). It calculates the consequences of a release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory; decay and in-grow the inventory during transport through processes, facilities, and the environment; model the downwind dispersion of the activity; and calculate doses to downwind individuals. Internal dose from the inhalation and ingestion pathways is calculated. External dose from ground surface and plume gamma pathways is calculated. New and exciting updates to the program include the ability to evaluate a release to an enclosed room, resuspension of deposited activity and evaluation of a release up to 1 meter from the release point. Enhanced tools are included for dry deposition, building wake, occupancy factors, respirable fraction, AMAD adjustment, updated and enhanced radionuclide inventory and inclusion of the dose-conversion factors from FOR 11 and 12. 2 - Methods: RSAC6 calculates meteorological dispersion in the atmosphere using Gaussian plume diffusion for Pasquill-Gifford, Hilmeier-Gifford and Markee models. A unique capability is the ability to model Class F fumigation conditions, the meteorological condition that causes the highest ground level concentrations from an elevated release. Doses may be calculated for various pathways including inhalation, ingestion, ground surface, air immersion, water immersion pathways. Dose calculations may be made for either acute or chronic releases. Internal doses (inhalation and ingestion) are calculated using the ICRP-30 model with dose conversion factors from FOR 11. External factors are calculated using FOR 12. 3 - Unusual Features: RSAC6 calculates complete progeny in-growth and decay during all accident phases. The calculation of fission product inventories in particularly useful in the analysis of accidents where the

  17. Radionuclide concentration in ground-level air from 1986 to 1987 in North Germany and North Norway

    International Nuclear Information System (INIS)

    Kolb, W.

    1988-03-01

    The activity concentration of various fission products and some other radionuclides (e.g. Be-7, Na-22, K-40 and Pb-210) contained in surface air were determined by γ-spectroscopy. The mean monthly acitvity concentrations of up to 30 radionuclides measured in 1986 and 1987 in Brunswick, Berlin and Skibotn (North Norway) are tabulated. The Chernobyl accident of April 26, 1986, resulted in 1986 in an annual mean Cs-137 activity concentration of 2.4 mBq/m 3 in Brunswick, 8.8 mBq/m 3 in Berlin and 0.3 mBq/m 3 at Skibotn. In 1987 the Cs-137 concentrations were just about 1% of these values. Occasionally fresh fission products from other sources were detected as e.g. I-131 in March 1987 (very likely released from a reactor site in Ukraine) and in August 1987 (released from an underground nuclear test on Novaja Zemlya together with other short-lived fission products). The effective dose equivalent due to inhalation of fission products is estimated for all three sites and compared with the Pb-210 inhalation dose. (orig./HP) [de

  18. The biotic factors role in radionuclide migration of natural-vegetable complexes

    International Nuclear Information System (INIS)

    Yakushev, B.I.; Kazej, A.I.; Sak, M.M.; Kuz'mich, O.T.; Golushko, R.M.

    1992-01-01

    In Byelorussiyn from first months after the Chernobyl' accident investigation are conducting on the radionuclide de dynamics in the soil-plant-soil system. The isotope composition of soil contamination density and specific plants radioactivity are studying, the radionuclide migration dynamic through the soil profile is investigating. The data are shown on considerable reduction of the plants radioactivity (1986-91 years) in connection with the reduction in the soil contamination density with gamma-spectrum radionuclides, accounting for Ce-144, Pr-144, Ru-106, Cs-134 decay; information is done on gamma-spectrum radionuclides of organs in natural pine and meadows system. It is shown, that the radionuclides are actively absorbed by roots in a zone of the highest radionuclide concentration and are delivered into the overground plant parts, then actively are removed into environment in the breathing process. 11 refs.; 4 tabs

  19. Radiation-dose estimates and hazard evaluations for inhaled airborne radionuclides. Annual progress report, July 1981-June 1982

    International Nuclear Information System (INIS)

    Mewhinney, J.A.

    1983-06-01

    The objective was to conduct confirmatory research on aerosol characteristics and the resulting radiation dose distribution in animals following inhalation and to provide prediction of health consequences in humans due to airborne radioactivity which might be released in normal operations or under accident conditions during production of nuclear fuel composed of mixed oxides of U and Pu. Four research reports summarize the results of specific areas of research. The first paper details development of a method for determination of specific surface area of small samples of mixed oxide or pure PuO 2 particles. The second paper details the extension of the biomathematical model previously used to describe retention, distribution and excretion of Pu from these mixed oxide aerosols to include a description of Am and U components of these aerosols. The third paper summarizes the biological responses observed in radiation dose pattern studies in which dogs, monkeys and rate received inhalation exposures to either 750 0 C heat treated UO 2 + PuO 2 , 1750 0 C heat-treated (U,Pu)O 2 or 850 0 C heat-treated pure PuO 2 . The fourth paper described dose-response studies in which rats were exposed to (U,Pu)O 2 or pure PuO 2 . This paper updates earlier reports and summarizes the status of animals through approximately 650 days after inhalation

  20. Water purification from radionuclides with using fibroid sorbents

    International Nuclear Information System (INIS)

    Khaydarov, R. A.; Gapurova, O.U.; Khaydarov, R.R.

    2005-01-01

    Full text: Purification waste water and drinking water from radionuclides, heavy metal ions, organic contamination is one of the important problems today. For solving this problem we have created three types of fibroid sorbents on the base of Polyester: cationic and anionic exchange and carbonic. Main properties of these sorbents are described in this article. For example characteristics of the sorbents for removing radionuclides Co-60,57, Zn-65, Sr-89,90, Cs-134,137, etc., radionuclides containing organic molecules M-P-32, M-I-131, M-Mo-99+Tc-99m, M-C-14, etc., heavy metal ions Zn, Ni, Cu, Sb, Pb, Cd, Cr, U, etc., organic molecules (pesticides, phenols, dioxin, benzene, toluene, etc.) were investigated. Influence of pH on percent removal, influence of K, Na and another ions concentrations in the liquid on the percent removal, decreasing of the saturation capacity from number of regeneration and another characteristics are described. Static exchange capacity of the cationic sorbents is 1-2 mg-equ/g and anionic - 0.5-1 mg-equ/g. Capacity of the carbonic sorbents for benzene is 100 mg/g. Time of chemical balance setting is 1-2 s. The sorbents are effective in removing the low concentrations of contamination from the water (lower than 100-200 mg/l) and the air (lower than 100 mg/m 3 ). The use of sorbents in drinking water filters and mini-systems is described. The industrial water purification system consists of coagulating unit, sorbent unit and disinfectant unit. The systems are used in atomic power stations, electroplating plants, matches plants, leather and skin treating plants, car-washing stations, etc

  1. A simplified model for calculating atmospheric radionuclide transport and early health effects from nuclear reactor accidents

    International Nuclear Information System (INIS)

    Madni, I.K.; Cazzoli, E.G.; Khatib-Rahbar, M.

    1995-01-01

    During certain hypothetical severe accidents in a nuclear power plant, radionuclides could be released to the environment as a plume. Prediction of the atmospheric dispersion and transport of these radionuclides is important for assessment of the risk to the public from such accidents. A simplified PC-based model was developed that predicts time-integrated air concentration of each radionuclide at any location from release as a function of time integrated source strength using the Gaussian plume model. The solution procedure involves direct analytic integration of air concentration equations over time and position, using simplified meteorology. The formulation allows for dry and wet deposition, radioactive decay and daughter buildup, reactor building wake effects, the inversion lid effect, plume rise due to buoyancy or momentum, release duration, and grass height. Based on air and ground concentrations of the radionuclides, the early dose to an individual is calculated via cloudshine, groundshine, and inhalation. The model also calculates early health effects based on the doses. This paper presents aspects of the model that would be of interest to the prediction of environmental flows and their public consequences

  2. Purification of radionuclides for nuclear medicine

    International Nuclear Information System (INIS)

    Horwitz, E.P.; Bond, A.H.

    2002-01-01

    Novel systems for the rapid separation of 67 Cu, 90 Y, 188 Re, 212 Bi, 213 Bi, and 223 Ra are described. To achieve the high levels of decontamination required of radionuclides used in radioimmunotherapy, we have utilised combinations of ion exchange (IX) and novel extraction chromatographic (EXC) resins. The objective of each separation system is to remove by many orders of magnitude the parent isotopes and to reduce the concentrations of stable, sometimes adventitious impurities, to low levels. The latter objective is particularly important to achieve a high degree of bonding of radionuclide onto a monoclonal antibody. The purification of 212 Bi (60.6 min half-life) furnishes a good example of the level of purity that we have achieved using tandem combinations of EXC and IX resins. Bismuth-212 was separated from its daughters, 212 Pb, 224 Ra, 228 Th and 232 U at the 50 mCi level. The resultant 212 Bi decayed to background in a few days indicative of high purity. Another example of extraordinary removal of parent nuclide from daughter nuclide and subsequent purification of daughter from stable elements is the preparation of 90 Y. Strontium-90 was removed from 90 Y by > 10 9 . The purified 90 Y uptake by monoclonal antibodies was close to 100%

  3. Dendrimer-coated magnetic particles for radionuclide separation

    NARCIS (Netherlands)

    Grüttner, Cordula; Böhmer, Volker; Casnati, Alessandro; Dozol, Jean-Francois; Reinhoudt, David; Reinoso garcia, M.M.; Rudershausen, Sandra; Teller, Joachim; Ungaro, Rocco; Verboom, Willem; Wang, Pingshan

    2005-01-01

    Magnetic particles were synthesised for radionuclide removal from nuclear wastes by magnetic separation. Dendrimers with terminal amino groups attached to the particle surface were used to bind chelating groups for lanthanides and actinides. This led to a 50–400-fold increase of the distribution

  4. Methods for the calculation of derived working limits for surface contamination by low-toxicity radionuclides

    International Nuclear Information System (INIS)

    Gibson, J.A.B.; Wrixon, A.D.

    1979-01-01

    Surface contamination is often measured as an indication of the general spread of radioactive contamination in a particular place. Derived working limits, (DWLs) for surface contamination provide figures against which to assess the significance of measurements. Derived working limits for surface contamination were first established for use in the nuclear energy industry. They were designed to cope with a wide range of unspecified radionuclides and were therefore based on the assumption that the contamination was due to the presence of the most hazardous radionuclides, e.g. 90 Sr, 210 Pb, 226 Ra and 239 Pu. While this assumption may still be appropriate when the radionuclide mixture is unknown, there are now many specialized uses of particular low-toxicity radionuclides in universities, hospitals and general industry. If it is known that only a particular radionuclide is present, the general DWL can be replaced by a more specific value. The methods for calculating DWLs for some of the more commonly employed low-toxicity radionuclides are described. The exposure pathways considered are (a) external radiation of the skin and inhalation of airborne material from contaminated surfaces in active areas; (b) external irradiation of the skin and ingestion from contaminated skin. Some consideration is given to the effect of the revised dose equivalent limits in the most recent recommendations of ICRP. (author)

  5. Transport of the radionuclides and doses for some coal fired power plants; Transport radionuklida i doze u okolini nekih termoelektrana

    Energy Technology Data Exchange (ETDEWEB)

    Antic, D [Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia); Telenta, B [Savezni hidrometeoroloski zavod, Belgrade (Yugoslavia); Sokcic-Kostic, M [Institute of Nuclear Sciences VINCA, Belgrade (Yugoslavia)

    1994-07-01

    The radiation exposure of the public in the vicinity of the selected coal fired power plants near from Belgrade has been studied. The contents of natural radionuclides according to experimental data have been used and dose rates from inhalation have been calculated using a two dimensional version of the cloud model. (author)

  6. Inhalation Therapy in Horses.

    Science.gov (United States)

    Cha, Mandy L; Costa, Lais R R

    2017-04-01

    This article discusses the benefits and limitations of inhalation therapy in horses. Inhalation drug therapy delivers the drug directly to the airways, thereby achieving maximal drug concentrations at the target site. Inhalation therapy has the additional advantage of decreasing systemic side effects. Inhalation therapy in horses is delivered by the use of nebulizers or pressured metered dose inhalers. It also requires the use of a muzzle or nasal mask in horses. Drugs most commonly delivered through inhalation drug therapy in horses include bronchodilators, antiinflammatories, and antimicrobials. Copyright © 2016 Elsevier Inc. All rights reserved.

  7. Toxicity of inhaled 91YCl3 in beagle dogs. VII

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Benjamin, S.A.; Boecker, B.B.; McClellan, R.O.

    1974-01-01

    Studies on the metabolism, dosimetry, and effects of inhaled 91 YCl 3 in Beagle dogs are being continued to provide information that will aid in assessing the biological consequences of nuclear accidents in which 91 Y or other radionuclides that produce a similar radiation dose pattern may be released. Forty-two dogs with 91 Y initial body burdens from 64 to 1300 μCi/kg body weight were placed in four groups with mean lung burdens of 310, 180, 75, and 40 μCi/kg body weight. These dogs and 12 control dogs are being maintained for lifetime observation. An additional group of four dogs with a mean initial 91 Y body burden of 180 μCi/kg body weight were placed in a sacrifice study. Eleven dogs within the highest activity level groups died or were euthanized at 12 to 33 days after inhalation of 91 Y with changes related to severe bone marrow damage and associated paycytopenia. Two dogs died approximately one year after 91 Y inhalation with convulsive seizures that were presumed to be unrelated to the 91 Y exposure. Four 91 Y-exposed dogs died or were euthanized due to neoplasms 2000 to 2560 days after exposure. Two dogs had squamous cell carcinomas involving the maxillary and nasal regions, one a bronchiolo-alveolar carcinoma of the lung and another, a mast cell sarcoma. One control dog died of empyema. Serial observations are continuing on all surviving dogs. (U.S.)

  8. Toxicity of inhaled 91YCl3 in beagle dogs. X

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Benjamin, S.A.; Boecker, B.B.; McClellan, R.O.

    1976-01-01

    Studies on the metabolism, dosimetry, and effects of inhaled 91 YCl 3 in Beagle dogs are being continued to provide information that will aid in assessing the biological consequences of nuclear accidents in which 91 Y or other radionuclides that produce a similar radiation dose pattern may be released. Forty-two dogs with 91 Y initial body burdens from 64 to 1300 μCi/kg body weight were placed in four groups with mean lung burdens of 310, 180, 75 and 40 μCi/kg body weight. These dogs and 12 control dogs are being maintained for lifetime observation. An additional group of four dogs with a mean initial 91 Y body burden of 180 μCi/kg body weight were placed in a sacrifice study. Eleven dogs within the highest activity level groups died or were euthanized at 12 to 33 days after inhalation of 91 Y with changes related to severe bone marrow damage and associated pancytopenia. Two dogs died approximately 1 yr after 91 Y inhalation with convulsive seizures that were presumed to be unrelated to the 91 Y exposure. Five 91 Y-exposed dogs died or were euthanized due to neoplasms 2000 to 3341 days after exposure. Three dogs had nasal squamous cell carcinomas, one had a bronchioloalveolar carcinoma and another, a mast cell sarcoma. One dog died of renal failure 2660 days after exposure and one control dog died of empyema. Serial observations are continuing on all surviving dogs

  9. Guidebook for the treatment of accidental internal radionuclide contamination of workers

    Energy Technology Data Exchange (ETDEWEB)

    Bhattacharyya, M H [Argonne National Lab., IL (United States); Breitenstein, B D [Brookhaven National Lab., Upton, NY (United States); Metivier, H [CEA Centre d' Etudes Nucleaires de Fontenay-aux-Roses, 92 (France). Inst. de Protection et de Surete Nucleaire; Muggenburg, B A [ITRI, Albuquerque, NM (United States); Stradling, G N [National Radiological Protection Board, Chilton (United Kingdom); Volf, V [Kernforschungszentrum Karlsruhe GmbH (Germany)

    1992-01-01

    This book is intended as a guide to the treatment of victims following an accident in which radionuclides have entered the body. It is a practical guide based on a review of current treatments to remove radionuclides from the body and prevent radiation-induced disease. This book should be used by occupational physicians, emergency room physicians, health physicists, paramedics and emergency personnel, nurses, and other related medical personnel. It is intended to provide an overview of the subject and practical information for treating and caring for persons exposed to radionuclides. (author).

  10. Revised age-dependent doses to members of the public from intake of radionuclides using the new tissue weighting factors

    International Nuclear Information System (INIS)

    Jain, S.C.; Gupta, M.M.; Nagaratnam, A.; Reddy, A.R.; Mehta, S.C.

    1992-01-01

    ICRP 56 gave age-dependent dose coefficients to members of the public from intake of most radiologically significant radionuclides that might be released to the environment due to various human activities. It has computed effective dose equivalent (now called effective dose) from these dose coefficients utilising the tissue weighting factors as given by ICRP 26. The recent ICRP 1990 recommendations have revised the tissue weighting factors based on new information on risk estimates of fatal cancer and hereditary disorders. This change in the tissue weighting factors will subsequently affect the computation of effective dose due to intake of various radio-nuclides considered by ICRP 56. The revised effective doses for ingested as well as inhaled radionuclides have been worked out and compared from corresponding earlier values. No change was found in the case of tritiated water, organically bound tritium and 14 C. For the majority of the radionuclides, the revised effective dose was within ± 20% of the earlier values. Larger variations in effective dose were noted for radionuclides which deposit preferentially in one or two organs. (author)

  11. External accumulation of radionuclide in hepatic hydrothorax

    International Nuclear Information System (INIS)

    Albin, R.J.; Johnston, G.S.

    1989-01-01

    Hepatic hydrothorax is a complication in approximately 5% of patients with cirrhosis. Ascites is almost always present and helps to suggest the correct diagnosis. However, when ascites is absent, radionuclide imaging has proven to be helpful in establishing that the pleural effusion originated from ascitic fluid. When pleural fluid is rapidly removed, such as by thoracostomy tube drainage, the radioisotope may accumulate outside the thorax and produce a negative scan of the chest. When the radionuclide scan is nondiagnostic and the pleural space is being rapidly drained, the pleural fluid collecting system should always be imaged before rejecting a diagnosis of hepatic hydrothorax

  12. Contaminative Influence of Beef Due to the Inhalation of Air and the Ingestion of Soil of Livestock from an Acute Release of Radioactive Materials

    International Nuclear Information System (INIS)

    Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Jeong, Hyo Jeon; Han, Moon Hee

    2004-01-01

    The contaminative influence of beef due to the inhalation of air and the ingestion of soil of livestock, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of livestock. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide '1 31 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. On the other hand, in the case of an accidental release during the grazing period of livestock, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible, like the cases of milk.

  13. Contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle in an accidental release of radioactive materials

    International Nuclear Information System (INIS)

    Hwang, W. T.; Kim, E. H.; Seo, K. S.; Jung, H. J.; Lee, S. M.; Hang, M. H.

    2004-01-01

    The contaminative influence of beef due to the inhalation of air and the ingestion of soil of cattle, both of which are dealt with as minor contaminative pathways in most radioecological models but may not be neglected, was comprehensively investigated with the improvement of the Korean dynamic food chain model DYNACON. As the results, it was found that both pathways can not be neglected at all in the contamination of beef in the case of an accidental release during the non-grazing period of cattle. The ingestion of soil was more influential in the contamination of beef than the inhalation of air over most time following an release. If precipitation is encountered during an accidental release, contaminative influence due to the ingestion of soil was far greater compared with the cases of no precipitation. This fact was more distinct for a long-lived radionuclide 137 Cs than a short-lived radionuclide 131 I (elemental iodine). Compared with the results for milk performed prior to this study, the contaminative pathways due to the inhalation of air and the ingestion of soil were more important in beef because of longer biological half-lives. In the meantime, in the case of an accidental release during the grazing period of cattle, radioactive contamination due to the ingestion of pasture was dominant irrespective of the existence of precipitation during an accidental release. It means that contaminative influence due to the inhalation of air and the ingestion of soil is negligible like the cases of milk

  14. Doses from intakes of radionuclides by adults and young people

    CERN Document Server

    Greenhalgh, J R; Fell, T P

    1985-01-01

    This report describes a methodology for calculating doses from ingestion and inhalation of radionuclides by adults, children (aged 10) and infants (aged 1). The calculation scheme follows the procedures and uses the models described in ICRP Publication 30, except in a few instances which are discussed in detail. The methods described in this report have been used to calculate organ doses and effective doses per unit intake for a wide variety of nuclides and compounds. A selection of these doses is given in this report. It is intended that the full dose data base should be made generally available in due course.

  15. Radionuclides incorporation in activated natural nanotubes

    International Nuclear Information System (INIS)

    Silva, Jose Parra

    2016-01-01

    Natural palygorskite nanotubes show suitable physical and chemical properties and characteristics to be use as potential nanosorbent and immobilization matrix for the concentration and solidification of radionuclides present in nuclear wastes. In the development process of materials with sorption properties for the incorporation and subsequent immobilization of radionuclides, the most important steps are related with the generation of active sites simultaneously to the increase of the specific surface area and suitable heat treatment to producing the structural folding. This study evaluated the determining parameters and conditions for the activation process of the natural palygorskite nanotubes aiming at the sorption of radionuclides in the nanotubes structure and subsequent evaluation of the parameters involve in the structural folding by heat treatments. The optimized results about the maximum sorption capacity of nickel in activated natural nanotubes show that these structures are apt and suitable for incorporation of radionuclides similar to nickel. By this study is verified that the optimization of the acid activation process is fundamental to improve the sorption capacities for specifics radionuclides by activated natural nanotubes. Acid activation condition optimized maintaining structural integrity was able to remove around 33.3 wt.% of magnesium cations, equivalent to 6.30·10 -4 g·mol -1 , increasing in 42.8% the specific surface area and incorporating the same molar concentration of nickel present in the liquid radioactive waste at 80 min. (author)

  16. Radionuclide transport and retardation in tuff

    International Nuclear Information System (INIS)

    Vine, E.N.; Bayhurst, B.P.; Daniels, W.R.; DeVilliers, S.J.; Erdal, B.R.; Lawrence, F.O.; Wolfsberg, K.

    1980-01-01

    Batch measurements provide an understanding of which experimental variables are important. For example, sorption ratios vary little with particle size (and surface area); however, groundwater composition and rock composition are quite important. A general correlation has been identified between mineralogy (major phases) and degree of sorption for strontium, cesium, and barium. Although these are approximate, a more detailed analysis may be possible as more samples are studied and the data base increased. Data from crushed tuff columns indicate that, except in simple cases where sorption coefficients are relatively low, and ion-exchange equilibria not only exist but are the dominant mechanism for removal of radioisotopes from solution, the simple relation between the sorption ratio R/sub d/ (or K/sub d/) and the relative velocity of radionuclides with respect to groundwater velocity may be insufficient to permit accurate modeling of the retardation of radionuclides. Additional work on whole core columns and larger blocks of intact material is required to better understand radionuclide sorption and transport through rock

  17. The Q system and the radiotoxicity of the radionuclides

    International Nuclear Information System (INIS)

    Hamard, J.

    1989-01-01

    The first edition of the International Atomic Energy Agency (IAEA) Regulations for the safe transport of radioactive materials was issued in 1962. The transported radionuclides were distributed into three groups according to their radiotoxicity. The radiotoxicity was evaluated by means of an injury index taking into account the dose equivalent received following a mean accident by incorporation, by inhalation, by ingestion or by wound. The 1962 regulations introduced the terminology of type A and type B packages and the nature of mean accident during which a person can incorporate an activity equal to 1/10 6 of the activity contained in the type A package. The reference dose equivalent was equal to 1/4 of the annual limit of equivalent dose for workers (in the following, they use dose in place of equivalent dose). Following these criteria the transported radionuclides were distributed into three groups of radiotoxicity: Very high - High - Low or moderate. The nature of special form materials and of low specific activity materials (LSA) was also introduced by reference to the incorporation of mass superior to 1 mg

  18. Dry deposition and fate of radionuclides within spruce canopies

    International Nuclear Information System (INIS)

    Ould-Dada, Z.; Shaw, G.; Kinnersley, R.P.; Minski, M.J.

    1997-01-01

    The assessment of radiation dose to human populations from the release of radionuclides into the atmosphere following a nuclear accident relies on the use of simulation models. These need to be calibrated and tested using experimental data. In this study, the deposition and resuspension of radionuclides within a forest environment was investigated. Forests were identified in the aftermath of the Chernobyl accident as a specific type of semi-natural ecosystem for which radiological data were lacking within the countries of the European Union. Wind tunnel and field data have been collected for small model canopies of Norwegian spruce saplings using uranium and silica aerosol particles. These have provided quantitative estimates of the potential of a tree canopy to constitute an airborne inhalation hazard and a secondary source of airborne contamination after the initial deposition. Using these results, a multi-layer compartmental model of aerosol flux (CANDEP) has been developed and calibrated. It combines the processes of dry deposition, resuspension and field loss in individual layers of the model canopy. (5 figures; 4 tables; 15 references). (UK)

  19. Inhalants in Peru.

    Science.gov (United States)

    Lerner, R; Ferrando, D

    1995-01-01

    In Peru, the prevalence and consequences of inhalant abuse appear to be low in the general population and high among marginalized children. Inhalant use ranks third in lifetime prevalence after alcohol and tobacco. Most of the use appears to be infrequent. Among marginalized children, that is, children working in the streets but living at home or children living in the street, the problem of inhalant abuse is a serious problem. Among children working in the streets but living at home, the lifetime prevalence rate for inhalant abuse is high, ranging from 15 to 45 percent depending on the study being cited. For children living in the streets, the use of inhalant is even more severe. As mentioned earlier in this chapter, most of these street children use inhalants on a daily basis. The lack of research on the problem of inhalant abuse is a serious impediment to development of intervention programs and strategies to address this problem in Peru. Epidemiologic and ethnographic research on the nature and extent of inhalant abuse are obvious prerequisites to targeted treatment and preventive intervention programs. The urgent need for current and valid data is underscored by the unique vulnerability of the youthful population at risk and the undisputed harm that results from chronic abuse of inhalants. Nonetheless, it is important to mention several programs that work with street children. Some, such as the Information and Education Center for the Prevention of Drug Abuse, Generation, and Centro Integracion de Menores en Abandono have shelters where street children are offered transition to a less marginal lifestyle. Teams of street educators provide the children with practical solutions and gain their confidence, as well as offer them alternative socialization experiences to help them survive the streets and avoid the often repressive and counterproductive environments typical of many institutions. Most of the children who go through these programs tend to abandon

  20. Assessment of Dose to the Nursing Infant from Radionuclides in Breast Milk

    Energy Technology Data Exchange (ETDEWEB)

    Leggett, Richard Wayne [ORNL; Eckerman, Keith F [ORNL

    2010-03-01

    A computer software package was developed to predict tissue doses to an infant due to intake of radionuclides in breast milk based on bioassay measurements and exposure data for the mother. The package is intended mainly to aid in decisions regarding the safety of breast feeding by a mother who has been acutely exposed to a radionuclide during lactation or pregnancy, but it may be applied to previous intakes during the mother s adult life. The package includes biokinetic and dosimetric information needed to address intake of Co-60, Sr-90, Cs-134, Cs-137, Ir-192, Pu-238, Pu-239, Am-241, or Cf-252 by the mother. It has been designed so that the library of biokinetic and dosimetric files can be expanded to address a more comprehensive set of radionuclides without modifying the basic computational module. The methods and models build on the approach used in Publication 95 of the International Commission on Radiological Protection (ICRP 2004), Doses to Infants from Ingestion of Radionuclides in Mothers Milk . The software package allows input of case-specific information or judgments such as chemical form or particle size of an inhaled aerosol. The package is expected to be more suitable than ICRP Publication 95 for dose assessment for real events or realistic planning scenarios in which measurements of the mother s excretion or body burden are available.

  1. Preparation, characterization and application of superparamagnetic iron oxide nanoparticles modified with natural polymers for removal of {sup 60}Co-radionuclides from aqueous solution

    Energy Technology Data Exchange (ETDEWEB)

    Sharaf El-Deen, Gehan E. [Atomic Energy Authority, Cairo (Egypt). Radioactive Waste Management Dept.; Imam, Neama G. [Atomic Energy Authority, Cairo (Egypt). Experimental Physics Dept.; Elettra, Sincrotrone, Trieste (Italy); Ayoub, Refaat R. [Atomic Energy Authority, Cairo (Egypt). Nuclear Chemistry Dept.

    2017-04-01

    Superparamagnetic iron oxide nanoparticles (IO-MNPs) coated with natural polymers, starch (IO-S MNPs) and dextrin (IO-D MNPs), were synthesized by modified co-precipitation method. IO and hybrid-IO-MNPs were characterized by XRD, SEM, HRTEM, FT-IR spectroscopy, vibrating sample magnetometer (VSM) and zeta potential (ZP). IO-S MNPs and IO-D MNPs have IO core-shell structure with core of 10.8 nm and 13.8 nm and shell of 7.5 nm and 5.9 nm, respectively. The efficiency of the hybrid IO-MNPs for sorption of {sup 60}Co(II)-radionuclides from aqueous solution was investigated under varying experimental conditions. Kinetic data were described well by pseudo-second-order mode, sorption isotherms were fitted quite with Freundlich model with maximum adsorption capacity 36.89 (mmol.g{sup -1})/(L.mmol{sup -1}){sup n} for IO-S MNPs and 24.9 (mmol.g{sup -1})/(L.mmol{sup -1}){sup n} for IO-D MNPs. Sorption of {sup 60}Co-radionuclides by IO-S MNPs was suppressed with salinity and most of the adsorbed {sup 60}Co onto IO-S MNPs could be remove with 0.1 M HCl solution. IO-S MNPs exhibits superparamagnetic properties, easier separation according to higher saturation magnetization (47 emu/g) and better adsorption for {sup 60}CO-radionuclides than IO-D MNPs.

  2. Hydrazine inhalation hepatotoxicity.

    Science.gov (United States)

    Kao, Yung Hsiang; Chong, C H; Ng, W T; Lim, D

    2007-10-01

    Abstract Hydrazine is a hazardous chemical commonly used as a reactant in rocket and jet fuel cells. Animal studies have demonstrated hepatic changes after hydrazine inhalation. Human case reports of hydrazine inhalation hepatotoxicity are rare. We report a case of mild hepatotoxicity following brief hydrazine vapour inhalation in a healthy young man, which resolved completely on expectant management.

  3. Radionuclide characterization and associated dose from long-lived radionuclides in close-in fallout delivered to the marine environment at Bikini and Enewetak Atolls

    International Nuclear Information System (INIS)

    Robison, W.L.; Noshkin, V.E.

    1999-01-01

    Between June 1946 and October 1958, Enewetak and Bikini Atolls were used by the US as testing grounds for 66 nuclear devices. The combined explosive yield from these tests was 107 million t (million t TNT equivalents). This testing produced close-in fallout debris that was contaminated with quantities of radioactive fission and particle activated products, and unspent radioactive nuclear fuel that entered the aquatic environment of the atolls. Today, the sediments in the lagoons are reservoirs for tens of TBq of the transuranics and some long-lived fission and activation products. The larger amounts of contamination are associated with fine and coarse sediment material adjacent to the locations of the high yield explosions. Radionuclides are also distributed vertically in the sediment column to various depths in all regions of the lagoons. Concentrations greater than fallout background levels are found in filtered water sampled over several decades from all locations and depths in the lagoons. This is a direct indication that the radionuclides are continuously mobilized to solution from the solid phases. Of particular importance is the fact that the long-lived radionuclides are accumulated to different levels by indigenous aquatic plants and organisms that are used as food by resident people. One might anticipate finding continuous high contamination levels in many of the edible marine organisms from the lagoons, since the radionuclides associated with the sediments are not contained and are available to the different organisms in a relatively shallow water environment. This is not the case. We estimate that the radiological dose from consumption of the edible parts of marine foods at Enewetak and Bikini is presently approximately 0.05% of the total 50-year integral effective dose from all other exposure pathways that include ingestion of terrestrial foods and drinking water, external exposure and inhalation. The total radiological dose from the marine pathway is

  4. Accumulation of nuclear fission products by vegetable crops and their removal during processing

    International Nuclear Information System (INIS)

    Weaver, C.M.

    1978-01-01

    The accumulation and turn over of 90 Sr and 137 Cs throughout the growth cycle of a vegetable crop was studied as well as the removal of these radionuclides in several vegetables by washing, blanching, freezing, canning, and pickling procedures. The results indicated that radiocontamination of vegetable crops with 137 Cs would result in greatest internal concentrations if exposure occurred early in the growth cycle of the plant, whereas, the greatest contamination by 90 Sr would occur from exposure during the middle of the growing period. Pulse labelling experiments were employed to examine turn over of radionuclides in kale. No net efflux of radionuclides from plants following exposure to either radionuclide was observed. Of the processing treatments employed on several types of vegetables, a combination of pickling and canning of cucumbers resulted in the greatest decontamination - 94% for 137 Cs and 65% for 90 Sr. Canning was highly effective in reducing radionuclide concentrations in beans and kale. However, freezing significantly reduced the radionuclide content of only 137 Cs in kale. Preparatory procedures prior to processing did not significantly reduce radionuclide levels except for 137 Cs in beans. The combination of washing, blanching, and canning sweet potatoes exposed to radionuclides resulted in the removal of 1.4% 137 Cs and 26.5% 90 Sr relative to unprocessed controls. The blanching process resulted in a transfer of radioactivity from the peel to the core, indicating that skins of contaminated potatoes should be removed prior to thermal treatment

  5. Actinides and long-lived radionuclides in tissues of the Japanese population. Summary of the past 20-year studies

    International Nuclear Information System (INIS)

    Takizawa, Y.; Abe, T.; Yamashita, J.

    2000-01-01

    Radioactive fallout constitutes the major source of contamination of the environment with fission products. Our primary interest was in selected fission products, such as 131 I, 89 Sr, 90 Sr, and 137 Cs, and neutron activation products, such as 3 H and 14 C. Plutonium-239,240, 241 Am and 90 Tc are generated from nuclear tests, and they are important by-products on nuclear industries. Polonium-210, 210 Pb and 232 Th, 230 Th and 228 Th occur widely in nature. These radionuclides enter the human body through inhalation and the ingestion through food and water. These nuclides may cause radiation doses to certain organs of the body. Assessment of the resulting health hazards is an essential public health activity, which demands reliable techniques for the assay of the various radionuclides in man and his environment. Accumulation of radionuclides from man-made sources and primordial radionuclides in various tissues of the Japanese population is presented. The studies were performed at the Department of Public Health, Akita University School of Medicine, during the periods from 1973 to 1995. (author)

  6. Annual research and development report 1978

    International Nuclear Information System (INIS)

    1979-06-01

    The work of the National Radiological Protection Board is reviewed under the following headings:- deposition and clearance of radioactive materials from lungs, metabolism and effects of incorporated radionuclides, removal of incorporated radionuclides, radioactivity in the environment, radiation-induced chromosome aberrations in human peripheral blood, biological effects of microwaves, calculations of radiation dose and risk, inhalation of radon and daughter products, doses to patients, personal monitoring, radiation physics and a national registry for radiation workers. (U.K.)

  7. Water Distribution and Removal Model

    International Nuclear Information System (INIS)

    Y. Deng; N. Chipman; E.L. Hardin

    2005-01-01

    The design of the Yucca Mountain high level radioactive waste repository depends on the performance of the engineered barrier system (EBS). To support the total system performance assessment (TSPA), the Engineered Barrier System Degradation, Flow, and Transport Process Model Report (EBS PMR) is developed to describe the thermal, mechanical, chemical, hydrological, biological, and radionuclide transport processes within the emplacement drifts, which includes the following major analysis/model reports (AMRs): (1) EBS Water Distribution and Removal (WD and R) Model; (2) EBS Physical and Chemical Environment (P and CE) Model; (3) EBS Radionuclide Transport (EBS RNT) Model; and (4) EBS Multiscale Thermohydrologic (TH) Model. Technical information, including data, analyses, models, software, and supporting documents will be provided to defend the applicability of these models for their intended purpose of evaluating the postclosure performance of the Yucca Mountain repository system. The WD and R model ARM is important to the site recommendation. Water distribution and removal represents one component of the overall EBS. Under some conditions, liquid water will seep into emplacement drifts through fractures in the host rock and move generally downward, potentially contacting waste packages. After waste packages are breached by corrosion, some of this seepage water will contact the waste, dissolve or suspend radionuclides, and ultimately carry radionuclides through the EBS to the near-field host rock. Lateral diversion of liquid water within the drift will occur at the inner drift surface, and more significantly from the operation of engineered structures such as drip shields and the outer surface of waste packages. If most of the seepage flux can be diverted laterally and removed from the drifts before contacting the wastes, the release of radionuclides from the EBS can be controlled, resulting in a proportional reduction in dose release at the accessible environment

  8. Water Distribution and Removal Model

    Energy Technology Data Exchange (ETDEWEB)

    Y. Deng; N. Chipman; E.L. Hardin

    2005-08-26

    The design of the Yucca Mountain high level radioactive waste repository depends on the performance of the engineered barrier system (EBS). To support the total system performance assessment (TSPA), the Engineered Barrier System Degradation, Flow, and Transport Process Model Report (EBS PMR) is developed to describe the thermal, mechanical, chemical, hydrological, biological, and radionuclide transport processes within the emplacement drifts, which includes the following major analysis/model reports (AMRs): (1) EBS Water Distribution and Removal (WD&R) Model; (2) EBS Physical and Chemical Environment (P&CE) Model; (3) EBS Radionuclide Transport (EBS RNT) Model; and (4) EBS Multiscale Thermohydrologic (TH) Model. Technical information, including data, analyses, models, software, and supporting documents will be provided to defend the applicability of these models for their intended purpose of evaluating the postclosure performance of the Yucca Mountain repository system. The WD&R model ARM is important to the site recommendation. Water distribution and removal represents one component of the overall EBS. Under some conditions, liquid water will seep into emplacement drifts through fractures in the host rock and move generally downward, potentially contacting waste packages. After waste packages are breached by corrosion, some of this seepage water will contact the waste, dissolve or suspend radionuclides, and ultimately carry radionuclides through the EBS to the near-field host rock. Lateral diversion of liquid water within the drift will occur at the inner drift surface, and more significantly from the operation of engineered structures such as drip shields and the outer surface of waste packages. If most of the seepage flux can be diverted laterally and removed from the drifts before contacting the wastes, the release of radionuclides from the EBS can be controlled, resulting in a proportional reduction in dose release at the accessible environment. The purposes

  9. The principal radionuclides in high level radioactive waste management

    International Nuclear Information System (INIS)

    Mulyanto

    1998-01-01

    The principal radionuclides in high level radioactive waste management. The selection of the principal radionuclides in the high level waste (HLW) management was developed in order to improve the disposal scenario of HLW. In this study the unified criteria for selection of the principal radionuclides were proposed as; (1) the value of hazard index estimated by annual limit of intake (ALI) for long-term tendency,(2) the relative dose factor related to adsorbed migration rate transferred by ground water, and (3) heat generation in the repository. From this study it can be concluded that the principal radionuclides in the HLW management were minor actinide (MA=Np, Am, Cm, etc), Tc, I, Cs and Sr, based on the unified basic criteria introduced in this study. The remaining short-lived fission product (SLFPs), after the selected nuclides are removed, should be immobilized and solidified in a glass matrix. Potential risk due to the remaining SLFPs can be lower than that of uranium ore after about 300 year. (author)

  10. An optimization strategy for a biokinetic model of inhaled radionuclides

    International Nuclear Information System (INIS)

    Shyr, L.J.; Griffith, W.C.; Boecker, B.B.

    1991-01-01

    Models for material disposition and dosimetry involve predictions of the biokinetics of the material among compartments representing organs and tissues in the body. Because of a lack of human data for most toxicants, many of the basic data are derived by modeling the results obtained from studies using laboratory animals. Such a biomathematical model is usually developed by adjusting the model parameters to make the model predictions match the measured retention and excretion data visually. The fitting process can be very time-consuming for a complicated model, and visual model selections may be subjective and easily biased by the scale or the data used. Due to the development of computerized optimization methods, manual fitting could benefit from an automated process. However, for a complicated model, an automated process without an optimization strategy will not be efficient, and may not produce fruitful results. In this paper, procedures for, and implementation of, an optimization strategy for a complicated mathematical model is demonstrated by optimizing a biokinetic model for 144Ce in fused aluminosilicate particles inhaled by beagle dogs. The optimized results using SimuSolv were compared to manual fitting results obtained previously using the model simulation software GASP. Also, statistical criteria provided by SimuSolv, such as likelihood function values, were used to help or verify visual model selections

  11. Task summary: Hot demonstration of proposed commercial nuclide removal technology

    International Nuclear Information System (INIS)

    Lee, D.D.; Travis, J.R.

    1995-11-01

    Radionuclides represent only a small fraction of the components in millions of gallons of storage tank supernatant at various sites, including Oak Ridge, Hanford, Savannah River, and Idaho. Most of the radioactivity is contributed by cesium, strontium, and technetium along with high concentrations of sodium and potassium salts. The purpose of this task is to test and select sorbents and commercial removal technologies supplied by ESP for removing and concentrating the radionuclides, thereby reducing the volume of waste to be stored or disposed

  12. Hydrotalcite formation facilitates effective contaminant and radionuclide removal from acidic uranium mine barren lixiviant

    International Nuclear Information System (INIS)

    Douglas, Grant; Shackleton, Mark; Woods, Peter

    2014-01-01

    Highlights: • Remediation of barren lixiviant using hydrotalcite precipitation. • High U and rare earth element concentration factor. • Hydrotalcite may be further modified for long-term disposal. • Potential application to U and other commodities. - Abstract: An assessment of hydrotalcite (HT) formation as a method to neutralise acidity and remove trace elements was undertaken using barren lixiviant from Heathgate Resources’ Beverley North in situ recovery (ISR) U mine in South Australia. This study demonstrated proof of concept in terms of the neutralisation of acidity and concomitant removal of a range of trace elements and U–Th series radionuclides from the barren lixiviant using MgCl 2 as a supplementary Mg source to optimise Mg:Al mol ratios and NaOH as the neutralising agent. Hydrotalcite was the predominant mineral formed during neutralisation, hosting a range of elements including substantial U (∼0.2%) and rare earth elements (REE ∼0.1%). High U and REE recovery (∼99%) from barren lixiviant after HT precipitation indicates a potential to both remediate barren lixiviant and to offset remediation costs. Alternatively, HT precipitates formed during barren lixiviant neutralisation may be further stabilised via calcination, silicification or a combination thereof forming minerals potentially amenable for inclusion in a long-term waste repository at the cessation of ISR mining. Importantly, the composition of the neutralised barren lixiviant produced via HT precipitation is similar to that of existing groundwater allowing for the possibility of direct aquifer re-injection after remediation. A potential exists to apply this HT-based remediation technology to conventional or ISR U mines (or mines exploiting other commodities) and allows for the prospect of a fully integrated ISR mining, processing and lixiviant remediation strategy consistent with stringent environmental and mine closure standards

  13. Natural and Synthetic Barriers to Immobilize Radionuclides

    International Nuclear Information System (INIS)

    Um, W.

    2011-01-01

    The experiments of weathering of glass waste form and the reacted sediments with simulated glass leachates show that radionuclide sequestration can be significantly enhanced by promoting the formation of secondary precipitates. In addition, synthetic phosphate-bearing nanoporous material exhibits high stability at temperature and has a very high K d value for U(VI) removal. Both natural and synthetic barrier materials can be used as additional efficient adsorbents for retarding transport of radionuclides for various contaminated waste streams and waste forms present at U. S. Department of Energy clean-up sites and the proposed geologic radioactive waste disposal facility. In the radioactive waste repository facility, natural or synthetic materials are planned to be used as a barrier material to immobilize and retard radionuclide release. The getter material can be used to selectively scavenge the radionuclide of interest from a liquid waste stream and subsequently incorporate the loaded getters in a cementitious or various monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides from monolithic waste forms. Also, the getter material is to reduce the release of radionuclides form monolithic waste forms by being emplaced as a backfill barrier material around the wastes or waste form to minimize the potential around the wastes or waste form to minimize the potential hazard of leached radioactive wastes. The barrier material should be highly efficient to sequester radionuclides and possess physical and chemical stability for long-term exposure to severe weathering conditions. Because potential leaching of radionuclides depends on various environmental and weathering conditions of the near-field repository, the barrier materials must be durable and not disintegrate under a range of moisture, temperature, pressure, radiation, Eh, ph. and

  14. Decontamination of radionuclides in food

    Energy Technology Data Exchange (ETDEWEB)

    Ohmomo, Yoichiro [Institute for Environmental Sciences, Aomori (Japan)

    1994-03-01

    The release of radionuclides arising from the Chernobyle accident led to widespread contamination of the northern hemisphere through fallout. This accident provided again an opportunity to investigate how and to what extent the radionuclides contamination in crops and animal derived foods could be reduced. The following topics are included in this paper. (1) How to reduce the transfer of radiostrontium and/or cesium from soil to crops: A pH increase of soil is effective for reducing their plant uptake. (2) How to reduce the transfer of radiocesium to animal derived foods: Ammonium-ferric-cyanoferrate (AFCF) should be the most effective compound for radiocesium excretion in the feces. Experiments with lactating cows and/or poultry gave extremely good results with respect to low radiocesium concentrations in milk, meat and eggs. (3) Removal coefficients of radiostrontium, cesium and iodine from contaminated leaf vegetables and cereals during food processing and culinary preparation: Though different by species, more than 80% of cesium and about 50% of strontium and iodine can be removed during culinary preparation of washing and boiling. (4) Simultaneous decontamination of radiocesium and iodine from drinking water and liquid milk: Metal ferrocyanide-anion exchange resin, specifically Fe ferrocyanide one, was successfully used for a rapid and simple decontamination of radiocesium and iodine in the liquid samples arising from the Chernobyle accident. (5) Removal of radiocesium from meat: The meat structurally contaminated with radiocesium is easily and very successfully decontaminated by pickling in NaCl solution and the decontamination is much speeded up by freezing meat before pickling. (author).

  15. Decontamination of radionuclides in food

    International Nuclear Information System (INIS)

    Ohmomo, Yoichiro

    1994-01-01

    The release of radionuclides arising from the Chernobyle accident led to widespread contamination of the northern hemisphere through fallout. This accident provided again an opportunity to investigate how and to what extent the radionuclides contamination in crops and animal derived foods could be reduced. The following topics are included in this paper. (1) How to reduce the transfer of radiostrontium and/or cesium from soil to crops: A pH increase of soil is effective for reducing their plant uptake. (2) How to reduce the transfer of radiocesium to animal derived foods: Ammonium-ferric-cyanoferrate (AFCF) should be the most effective compound for radiocesium excretion in the feces. Experiments with lactating cows and/or poultry gave extremely good results with respect to low radiocesium concentrations in milk, meat and eggs. (3) Removal coefficients of radiostrontium, cesium and iodine from contaminated leaf vegetables and cereals during food processing and culinary preparation: Though different by species, more than 80% of cesium and about 50% of strontium and iodine can be removed during culinary preparation of washing and boiling. (4) Simultaneous decontamination of radiocesium and iodine from drinking water and liquid milk: Metal ferrocyanide-anion exchange resin, specifically Fe ferrocyanide one, was successfully used for a rapid and simple decontamination of radiocesium and iodine in the liquid samples arising from the Chernobyle accident. (5) Removal of radiocesium from meat: The meat structurally contaminated with radiocesium is easily and very successfully decontaminated by pickling in NaCl solution and the decontamination is much speeded up by freezing meat before pickling. (author)

  16. Protocols of radiocontaminant air monitoring for inhalation exposure estimates

    International Nuclear Information System (INIS)

    Shinn, J.H.

    1995-09-01

    Monitoring the plutonium and americium particle emissions from soils contaminated during atmospheric nuclear testing or due to accidental releases is important for several reasons. First, it is important to quantify the extent of potential human exposure from inhalation of alpha-emitting particles, which is the major exposure pathway from transuranic radionuclides. Second, the information provided by resuspension monitoring is the basis of criteria that determine the target soil concentrations for management and cleanup of contaminated soil sites. There are other radioactive aerosols, such as the fission products (cesium and strontium) and neutron-activation products (europium isotopes), which may be resuspended and therefore necessary to monitor as well. This Standard Protocol (SP) provides the method used for radiocontaminant air monitoring by the Health and Ecological Assessment Division (formerly Environmental Sciences Division), Lawrence Livermore National Laboratory, as developed and tested at Nevada Test Site (NTS) and in the Marshall Islands. The objective of this SP is to document the applications and methods of monitoring of all the relevant variables. This protocol deals only with measuring air concentrations of radionuclides and total suspended particulates (TSP, or open-quotes dustclose quotes). A separate protocol presents the more difficult measurements required to determine transuranic aerosol emission rates, or open-quotes resuspension rateclose quotes

  17. Alpha Emitting Radionuclides and Radiopharmaceuticals for Therapy

    International Nuclear Information System (INIS)

    Chérel, Michel; Barbet, Jacques

    2013-01-01

    Today, cancer treatments mainly rely on surgery or external beam radiation to remove or destroy bulky tumors. Chemotherapy is given when tumours cannot be removed or when dissemination is suspected. However, these approaches cannot permanently treat all cancers and relapse occurs in up to 50% of the patients’ population. Radioimmunotherapy (RIT) and peptide receptor radionuclide therapy (PRRT) are effective against some disseminated and metastatic diseases, although they are rarely curative. Most preclinical and clinical developments in this field have involved electron-emitting radionuclides, particularly iodine-131, yttrium-90 and lutetium-177. The large range of the electrons emitted by these radionuclides reduces their efficacy against very small tumour cell clusters or isolated tumour cells present in residual disease and in many haematological tumours (leukaemia, myeloma). The range of alpha particles in biological tissues is very short, less than 0.1 mm, which makes alpha emitters theoretically ideal for treatment of such isolated tumour cells or micro-clusters of malignant cells. Thus, over the last decade, a growing interest for the use of alpha-emitting radionuclides has emerged. Research on targeted alpha therapy (TAT) began years ago in Nantes through cooperation between Subatech, a nuclear physics laboratory, CRCNA, a cancer research centre with a nuclear oncology team and ITU (Karlsruhe, Germany). CD138 was demonstrated as a potential target antigen for Multiple Myeloma, which is a target of huge clinical interest particularly suited for TAT because of the disseminated nature of the disease consisting primarily of isolated cells and small clusters of tumour cells mainly localized in the bone marrow. Thus anti-CD138 antibodies were labelled with bismuth-213 from actinium-225/bismuth-213 generators provided by ITU and used to target multiple myeloma cells. In vitro studies showed cell cycle arrest, synergism with chemotherapy and very little induction

  18. Analyses of human exposures to alpha-emitting radionuclides from nuclear fuel cycles

    International Nuclear Information System (INIS)

    Cuddihy, R.G.; McClellan, R.O.; Griffith, W.C.; Hoover, M.D.

    1977-01-01

    Human populations may potentially be exposed to alpha-emitting radionuclides released to the environment from a variety of activities associated with nuclear fuel cycles. Generally, the most important exposure pathway is by way of inhalation. This can occur soon after release of these substances or after they have been deposited on ground surfaces and resuspended with soil particles. Estimating the potential magnitude of these exposures is usually done through the use of mathematical models accounting for the dispersion of the released material through the environment and its uptake by people living near the nuclear facilities. Studies described in this paper suggest that these exposures can probably be estimated within a factor of 10 based upon our previous experience with measured human organ levels of other trace metals taken up from the environment. It should also be noted that variability among individuals within the population may result in a few percent accumulating more than 10 times the geometric mean of the internal organ radionuclide burdens

  19. Behaviour of Chernobyl fallout radionuclides deposited on peat and urban surfaces in Finland

    International Nuclear Information System (INIS)

    Reponen, A.

    1992-10-01

    In the thesis the impact of the Chernobyl nuclear reactor accident on Finland was studied in three aspects: (1) the areal distribution of Chernobyl fallout in Finland was determined by measuring peat samples, (2) the behaviour of fallout radionuclides was investigated in the combustion of peat in power plants, and (3) the removal rates of fallout radionuclides on urban surfaces were resolved

  20. Estimation of the skeletal burden of bone-seeking radionuclides from in vivo scintillation measurements of their content in the skull: contribution from radionuclides in the thoracic skeleton to in vivo measurement of activity in the lung

    International Nuclear Information System (INIS)

    Anon.

    1980-01-01

    After the initiation of NaI(Tl), spectrometric methods for detecting photon-emitting radionuclides in man, it became evident that the high background rates in the low energy regions precluded in vivo measurement of many bone-seeking nuclides. To meet these needs a dual crystal, low energy sensitive NaI(Tl)-CsI(Tl) detector system was developed. To date this system, in combination with more routine bioassays, remains the optimum methodology for the determination of internal exposure to low energy, photon-emitting radionuclides. Since most occupational exposures occur by inhalation, internal deposits must be quantitated with these detectors placed over the lung area. Since many of the alpha-emitting nuclides are bone-seekers, the contribution of material which has been transported from the lung and deposited in the skeleton must be accounted for

  1. Operational Testing of a Combined Hardware-Software Strategy for Triage of Radiologically-Contaminated Persons.

    Science.gov (United States)

    Waller, Edward J

    2015-08-01

    After a radiological dispersal device (RDD) event, it is possible for radionuclides to enter the human body through inhalation, ingestion, and skin and wound absorption. The dominant pathway will be through inhalation. From a health physics perspective, it is important to know the magnitude of the intake to perform dosimetric assessments. From a medical perspective, removal of radionuclides leading to dose (hence risk) aversion is of high importance. The efficacy of medical decorporation strategies is extremely dependent upon the time of treatment delivery after intake. The "golden hour," or more realistically 3-4 h, is imperative when attempting to increase removal of radionuclides from extracellular fluids prior to cellular incorporation. To assist medical first response personnel in making timely decisions regarding appropriate treatment delivery modes, a software tool has been developed which compiles existing radionuclide decorporation therapy data and allows a user to perform simple triage leading to potential appropriate decorporation treatment strategies. Three triage algorithms were included: (1) multi-parameter model (MPM), (2) clinical decision guidance (CDG) model, and (3) annual limit on intake (ALI) model. A radiation triage mask (RTM) has simultaneously been developed to provide a simple and rapid hardware solution for first responders to triage internally exposed personnel in the field. The hardware/software strategy was field tested with a military medical unit and was found by end-users to be relatively simple to learn and use.

  2. The computation of ICRP dose coefficients for intakes of radionuclides with PLEIADES: biokinetic aspects.

    Science.gov (United States)

    Fell, T P

    2007-01-01

    The ICRP has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public including children and pregnant or lactating women. The calculation of these coefficients conveniently divides into two distinct parts--the biokinetic and dosimetric. This paper gives a brief summary of the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES.

  3. The computation of ICRP dose coefficients for intakes of radionuclides with PLEIADES: biokinetic aspects

    International Nuclear Information System (INIS)

    Fell, T.P.

    2007-01-01

    The ICRP has published dose coefficients for the ingestion or inhalation of radionuclides in a series of reports covering intakes by workers and members of the public including children and pregnant or lactating women. The calculation of these coefficients conveniently divides into two distinct parts - the biokinetic and dosimetric. This paper gives a brief summary of the methods used to solve the biokinetic problem in the generation of dose coefficients on behalf of the ICRP, as implemented in the Health Protection Agency's internal dosimetry code PLEIADES. (author)

  4. Biosorption of radionuclides by snail shell biomass

    International Nuclear Information System (INIS)

    Dhami, P.S.; Chaudhari, S.D.; Rathinam, M.; Gopalakrishnan, V.; Ramanujam, A.

    2001-01-01

    The sorption of various radionuclides from low acidic and alkaline medium was studied using biomass of snail shell origin. Quantitative removal of plutonium was achieved when an alkaline waste effluents of PUREX origin at pH 9.4 was treated using this biomass. The sorbed activity was recovered by dissolving it in 1.0 M nitric acid. (author)

  5. Transport of radionuclides in the atmosphere during complex meteorological conditions

    International Nuclear Information System (INIS)

    Antic, D.; Telenta, B.

    1991-01-01

    Radionuclides from various sources (nuclear and fossil fuel power plants, nuclear facilities, medical facilities, etc.) are being released to the atmosphere. The meteorological conditions determine the atmospheric turbulence, dispersion, and removal processes of the radionuclides. A two-dimensional version of the cloud model based on the Klemp-Wilhelmson dynamic and Lin et al.'s microphysics and thermodynamics has been adapted and used to simulate the transport of radionuclides emitted from a power plant or other source to the atmosphere. Calculations of the trajectories and radii for a few puffs are included in this paper. These numerical investigations show that the presented model can be used for the transport simulation of radionuclides and for the assessment of the radiological impact of power plants and other sources in safety assessments and comparative studies. Because it can simulate puff trajectories, this model is especially valuable in the presence of complex meteorological conditions

  6. Removal efficiency of radioactive cesium and iodine ions by a flow-type apparatus designed for electrochemically reduced water production.

    Directory of Open Access Journals (Sweden)

    Takeki Hamasaki

    Full Text Available The Fukushima Daiichi Nuclear Power Plant accident on March 11, 2011 attracted people's attention, with anxiety over possible radiation hazards. Immediate and long-term concerns are around protection from external and internal exposure by the liberated radionuclides. In particular, residents living in the affected regions are most concerned about ingesting contaminated foodstuffs, including drinking water. Efficient removal of radionuclides from rainwater and drinking water has been reported using several pot-type filtration devices. A currently used flow-type test apparatus is expected to simultaneously provide radionuclide elimination prior to ingestion and protection from internal exposure by accidental ingestion of radionuclides through the use of a micro-carbon carboxymethyl cartridge unit and an electrochemically reduced water production unit, respectively. However, the removability of radionuclides from contaminated tap water has not been tested to date. Thus, the current research was undertaken to assess the capability of the apparatus to remove radionuclides from artificially contaminated tap water. The results presented here demonstrate that the apparatus can reduce radioactivity levels to below the detection limit in applied tap water containing either 300 Bq/kg of 137Cs or 150 Bq/kg of 125I. The apparatus had a removal efficiency of over 90% for all concentration ranges of radio-cesium and -iodine tested. The results showing efficient radionuclide removability, together with previous studies on molecular hydrogen and platinum nanoparticles as reactive oxygen species scavengers, strongly suggest that the test apparatus has the potential to offer maximum safety against radionuclide-contaminated foodstuffs, including drinking water.

  7. Toxicity of inhaled 91YCl3 in Beagle dogs. XII

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Rebar, A.H.; Boecker, B.B.; Jones, R.K.; McClellan, R.O.; Pickrell, J.A.

    1978-01-01

    Studies on the metabolism, dosimetry and effects of inhaled 91 YCl 3 in Beagle dogs are being continued to provide information that will aid in assessing the biological consequences of nuclear accidents in which 91 Y or other radionuclides that produce a similar radiation dose pattern may be released. Forty-two dogs with 91 Y initial body burdens from 64 to 1300 μCi/kg body weight was placed in four groups with mean lung burdens of 310, 180, 75 and 40 μCi/kg body weight. These dogs and 12 control dogs are being maintained for lifetime observation. An additional group of four dogs with a mean initial 91 Y body burden of 180 μCi/kg body weight was placed in a sacrifice study. Twenty-six of the exposed dogs and four of the control dogs have died. Eleven dogs within the highest activity level groups died or were euthanized at 12 to 33 days after inhalation of 91 Y with changes related to severe bone marrow damage and associated pancytopenia. Two dogs died approximately one year after 91 Y inhalation with convulsive seizures that were presumed to be unrelated to the 91 Y exposure. Nine 91 Y-exposed dogs died or were euthanized due to neoplasms 2012 to 4115 days after exposure. Three dogs had nasal squamous cell carcinomas, one had a bronchioloalveolar carcinoma, one a mast cell sarcoma, one a mammary adenocarcinoma, one a malignant lymphoma, one a melanosarcoma in the mouth and one heart base tumor. Two dogs died of renal failure 2663 and 4086 days after exposure. One dog died with autoimmune hemolytic anemia 3888 days after exposure and one died with congestive heart failure 4042 days after inhalation exposure. One control dog died of empyema, another control dog died with a mammary adenocarcinoma, one died with congestive heart failure and one with malabsorption syndrome. Serial observations are continuing on all surviving dogs

  8. Nasal Filters For Relief From Atopic Dermatitis Caused by Inhalants

    Directory of Open Access Journals (Sweden)

    J S Pasricha

    1989-01-01

    Full Text Available Nasal filter is a simple device consisting of a net mounted in a frame made to fit inside the nostrils. These filters thus are not visible from outside. If a person uses the nasal filters the .u particulate material from the air that the person breathes gets removed and in case the person is allergic to an inhalant antigen, he stops having the allergic symptoms. We tried nasal filters on two females patients aged 32 and 7 years respectively, having topics dermatitis the age of I year, caused by an inhalant (indicated by seasonal aggravations, and spontaneous recovery during brief visits to other towns. Unrig a follow-up of 2 1/2 and 2 years respectively, both the patients experienced almost 80-90% relief from the dermatitis and required only animal treatment.

  9. Activation of Alveolar Macrophages after Plutonium Oxide Inhalation in Rats: Involvement in the Early Inflammatory Response

    Energy Technology Data Exchange (ETDEWEB)

    Van der Meeren, A.; Tourdes, F.; Gremy, O.; Grillon, G.; Abram, M.C.; Poncy, J.L.; Griffiths, N. [CEA, DSV, DRR, SRCA, Centre DAM Ile de France, F-91297 Bruyeres Le Chatel, Arpajon (France)

    2008-07-01

    Alveolar macrophages play an important role in the distribution, clearance and inflammatory reactions after particle inhalation, which may influence long-term events such as fibrosis and tumorigenesis. The objectives of the present study were to investigate the early inflammatory events after plutonium oxide inhalation in rats and involvement of alveolar macrophages. Lung changes were studied from 3 days to 3 months after inhalation of PuO{sub 2} or different isotopic compositions (70% or 97% {sup 239}Pu) and initial lung deposits (range 2.1 to 43.4 kBq/rat). Analyses of bronchoalveolar lavages showed early increases in the numbers of granulocytes, lymphocytes and multi-nucleated macrophages. The activation of macrophages was evaluated ex vivo by measurement of inflammatory mediator levels in culture supernatants. TNF-alpha and chemokine MCP-1, MIP-2 and CINC-1 production was elevated from 7 days after inhalation and remained so up to 3 months. In contrast, IL-1 beta, IL-6 and IL-10 production was unchanged. At 6 weeks, pulmonary macrophage numbers and activation state were increased as observed from an immunohistochemistry study of lung sections with anti-ED1. Similarly, histological analyses of lung sections also showed evidence of inflammatory responses. In conclusion, our results indicate early inflammatory changes in the lungs of PuO{sub 2}-contaminated animals and the involvement of macrophages in this process. A dose-effect relationship was observed between the amount of radionuclide inhaled or retained at the time of analysis and inflammatory mediator production by alveolar macrophages 14 days after exposure. For similar initial lung deposits, the inflammatory manifestation appears higher for 97% {sup 239}Pu than for 70% {sup 239}Pu. (authors)

  10. Innovative methods to stabilize liquid membranes for removal of radionuclides from groundwater

    Energy Technology Data Exchange (ETDEWEB)

    Lokhandwala, K. [Membrane Technology and Research, Inc., Menlo Park, CA (United States)

    1997-10-01

    In this Phase I Small Business Innovation Research program, Membrane Technology Research, Inc., is developing a stable liquid membrane for extracting uranium and other radionuclides from groundwater. The improved membrane can also be applied to separation of other metal ions from aqueous streams in industrial operations.

  11. Ciclesonide Oral Inhalation

    Science.gov (United States)

    ... use ciclesonide inhalation.Ciclesonide inhalation helps to prevent asthma attacks (sudden episodes of shortness of breath, wheezing, and coughing) but will not stop an asthma attack that has already started. Do not use ciclesonide ...

  12. Flunisolide Oral Inhalation

    Science.gov (United States)

    ... use flunisolide inhalation.Flunisolide inhalation helps to prevent asthma attacks (sudden episodes of shortness of breath, wheezing, and coughing) but will not stop an asthma attack that has already started. Do not use flunisolide ...

  13. Toxicity of inhaled 91YCl3 in beagle dogs. XI

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Rebar, A.H.; Benjamin, S.A.; Boecker, B.B.; Jones, R.K.; McClellan, R.O.; Pickrell, J.A.

    1977-01-01

    Studies on the metabolism, dosimetry and effects of inhaled 91 YCl 3 in Beagle dogs are being continued to provide information that will aid in assessing the biological consequences of nuclear accidents in which 91 Y or other radionuclides that produce a similar radiation dose pattern may be released. Forty-two dogs with 91 Y initial body burdens from 64 to 1300 μCi/kg body weight were placed in four groups with mean lung burdens of 310, 180, 75 and 40 μCi/kg body weight. These dogs and 12 control dogs are being maintained for lifetime observation. An additional group of four dogs with a mean initial 91 Y body burden of 180 μCi/kg body weight were placed in a sacrifice study. Twenty-one of the exposed dogs have died and two of the control dogs have died. Eleven dogs within the highest activity level groups died or were euthanized at 12 to 33 days after inhalation of 91 Y with changes related to severe bone marrow damage and associated pancytopenia. Two dogs died approximately one year after 91 Y inhalation with convulsive seizures that were presumed to be unrelated to the 91 Y exposure. Seven 91 Y-exposed dogs died or were euthanized due to neoplasms 2000 to 3341 days after exposure. Three dogs had nasal squamous cell carcinomas, one had a bronchioloalveolar carcinoma, one, a mast cell sarcoma, one a mammary adenocarcinoma and one with a malignant lymphoma. One dog died of renal failure 2660 days after exposure, one control dog died of empyema and another control dog died with a mammary adenocarcinoma. Serial observations are continuing on all surviving dogs

  14. Development and testing of inorganic sorbents made by the internal gelation process for radionuclide and heavy metal separations

    International Nuclear Information System (INIS)

    Egan, B.Z.; Collins, J.L.; Anderson, K.K.; Chase, C.W.

    1995-01-01

    The objectives of this task are to develop, prepare, and test microspheres and granular forms of inorganic ion exchangers to remove radionuclides and heavy metals from waste streams occurring at various sites. Several inorganic materials, such as hexacyanoferrates, titanates, phosphates, and oxides have high selectivities and efficiencies for separating and removing radionuclides such as uranium, technetium, cesium, and strontium, and metals such as cobalt, silver, zinc, and zirconium from aqueous waste streams. However, these sorbents frequently exist only as powders and consequently are not readily adaptable to continuous processing such as column chromatography. Making these inorganic ion exchangers as microspheres or granular forms improves the flow dynamics for column operations and expands their practical applications. Microspheres of several materials have been prepared at ORNL, and the effectiveness of zirconium monohydrogen phosphate and hydrous titanium oxide microspheres for removing radionuclides from hot cell waste solutions has been demonstrated

  15. Toxicity of inhaled 238PuO2 I

    International Nuclear Information System (INIS)

    Diel, J.H.; Mewhinney, J.A.

    1980-01-01

    The deposition, retention, translocation and microscopic distribution of inhaled 238 PuO 2 particles were studied to better define the organs at risk and uniformity of dose and cell types or structures at risk in the lung. Beagle dogs were exposed once by inhalation to an aerosol of 238 PuO 2 with particle aerodynamic diameters of 0.7, 1.4, or 2.7 μm (+-10%). Initial burdens averaged about 700 nCi, a level not expected to induce life-shortening effects in Beagle dogs. Animals were sacrificed at times from 4 hours to 2 years after exposure. Whole body retention of plutonium and its distribution among organs in the sacrificed animals was determined by radiochemical analysis for plutonium content of excreta and tissue samples. The distribution of particles in lung was determined using autoradiographs of lung tissue sections and computer-assisted data collection and analysis. Soon after exposure, PuO 2 was relatively insoluble in lung with individual particles being randomly distributed throughout the lung. A distinct change in the rate of dissolution from lung occurred at about 100 days after exposure resulting in decreased pulmonary retention and increased uptake by liver and skeleton. Particle breakup was observed in autoradiographs for time periods in excess of 128 days after exposure. Broken up particles dissolved rapidly leaving little residue in the lung. The remaining particles were randomly distributed in the lung. These results are discussed in relation to current radiation protection guides for plutonium radionuclides. (author)

  16. Comparison of the COMRADEX-IV and AIRDOS-EPA methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere

    International Nuclear Information System (INIS)

    Miller, C.W.; Hoffman, F.O.; Dunning, D.E. Jr.

    1981-01-01

    This report presents a comparison between two computerized methodologies for estimating the radiation dose to man from radionuclide releases to the atmosphere. The COMRADEX-IV code was designed to provide a means of assessing potential radiological consequences from postulated power reactor accidents. The AIRDOS-EPA code was developed primarily to assess routine radionuclide releases from nuclear facilities. Although a number of different calculations are performed by these codes, three calculations are in common - atmospheric dispersion, estimation of internal dose from inhalation, and estimation of external dose from immersion in air containing gamma emitting radionuclides. The models used in these calculations were examined and found, in general, to be the same. Most differences in the doses calculated by the two codes are due to differences in values chosen for input parameters and not due to model differences. A sample problem is presented for illustration

  17. An interspecies comparison of the biological effects of an inhaled, relatively insoluble beta emitter

    International Nuclear Information System (INIS)

    Griffith, W.C.; Lundgren, D.L.; Hahn, F.F.; Boecker, B.B.; McClellan, R.O.

    1986-01-01

    Mice, rats, Syrian hamsters, and beagle dogs were exposed by inhalation to graded levels of 144 Ce in relatively insoluble forms to demonstrate species similarities and differences regarding patterns of deposition, fate, dosimetry, and dose-response relationships. All animals were serially evaluated to determine lung burdens, held for life-span observation, necropsied at death, and examined histopathologically to characterize the lesions present and to determine the cause of death. The primary malignant lung tumors observed in rodents were predominantly squamous-cell carcinomas and adenocarcinomas, whereas those in dogs at earlier times were primarily hemangiosarcomas and those in dogs that died at later times were pulmonary carcinomas. The relationship between the incidence of lung cancer and absorbed beta dose to the lung differed among species. The results of modeling these data provide a better understanding of how the choice of species can influence the outcome of a life-span study. The data are used to estimate the risk of lung cancer in man from an inhaled beta-emitting radionuclide. 26 refs., 5 figs., 6 tabs

  18. Interaction between water, sediments and radionuclides

    International Nuclear Information System (INIS)

    Snodgrass, W.J.; McKee, P.; Garnett, J.; Stieff, L.

    1988-08-01

    A model-based measurements program was carried out to evaluate the primary mechanisms controlling transport of uranium 238 and thorium 232 decay chain radionuclides in Quirke Lake, a water body draining much of the uranium mining and milling district near Elliot Lake, Ontario. This program included studies of radionuclide accumulation in sediments, particle settling and lake mass-balance studies. Also, sediment studies were undertaken to evaluate chemical fractionation, mineralogical associations, and sediment-water adsorption and release. A limnocorral experiment was conducted in an isolated portion of a lake to measure radium 226 removal from the water column and diffusion from the sediments back to the water. Modelling studies were made to assess the data. Substantial agreement was obtained using the model originally developed for the AECB between model predictions and observations for Quirke Lake and for the limnocorrals. Further work is required to complete the studies undertaken in this project to assess the significance of the efflux of radionuclides from the sediments. These studies include a laboratory program to measure kinetics of adsorption, sediment-water modelling studies of the results and a field measurement program to develop a mass-balance analysis for thorium. (numerous refs)

  19. Summary Report for the Development of Materials for Volatile Radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Strachan, Denis M.; Chun, Jaehun; Henager, Charles H.; Matyas, Josef; Riley, Brian J.; Ryan, Joseph V.; Thallapally, Praveen K.

    2010-11-22

    The materials development summarized here is in support of the Waste Forms campaign, Volatile Radionuclide task. Specifically, materials are being developed for the removal and immobilization of iodine and krypton, specifically 129I and 85Kr. During FY 2010, aerogel materials were investigated for removal and immobilization of 129I. Two aerogel formulations were investigated, one based on silica aerogels and the second on chalcogenides. For 85Kr, metal organic framework (MOF) structures were investigated.

  20. Summary Report for the Development of Materials for Volatile Radionuclides

    International Nuclear Information System (INIS)

    Strachan, Denis M.; Chun, Jaehun; Henager, Charles H.; Matyas, Josef; Riley, Brian J.; Ryan, Joseph V.; Thallapally, Praveen K.

    2010-01-01

    The materials development summarized here is in support of the Waste Forms campaign, Volatile Radionuclide task. Specifically, materials are being developed for the removal and immobilization of iodine and krypton, specifically 129I and 85Kr. During FY 2010, aerogel materials were investigated for removal and immobilization of 129I. Two aerogel formulations were investigated, one based on silica aerogels and the second on chalcogenides. For 85Kr, metal organic framework (MOF) structures were investigated.

  1. Hot demonstration of proposed commercial nuclide removal technology

    Energy Technology Data Exchange (ETDEWEB)

    Lee, D.D.; Travis, J.R.; Gibson, M.R. [Oak Ridge National Lab., TN (United States)

    1997-10-01

    Cesium, strontium, and technetium radionuclides are a small fraction of the mainly sodium and potassium salts in storage tank supernatants at the Hanford, Oak Ridge, Savannah River, and Idaho sites that DOE must remediate. Radionuclide removal technologies supplied by the ESP-CP have been previously proposed and tested in small batch and column tests using simulated and a few actual supernatants. They must now be tested and the most appropriate ones selected using a flow system of a scale suitable to obtain engineering data that can be applied to the design of pilot-scale equipment. This task involves operation of an experimental unit designed and constructed to test radionuclide removal technologies during continuous operation on actual supernatants. The equipment diagram, consists of the tanks, pumps, tubing and fittings, filters, and intrumentation for testing radionuclide removal technologies in a continuous-flow system in an Oak Ridge National Laboratory (ORNL) hot cell. The task provides a test bed for investigating new technologies, such as 3M`s SLIG 644 WWL WEB and AEA Technology`s EIX electrochemical elution system, and complements ESP`s comprehensive supernatant task (TTPOR06C341) by using larger engineering-scale, continuous equipment to verify and expand that task`s batch studies. This task complements the Tanks Focus Area`s (TFA`s) Cesium Removal Demonstration (CsRD) at ORNL by providing sorbent selection information, evaluating and testing proposed sorbents, and providing operational experience and characteristics using the sorbent and supernatant to be used in the demonstration, followed by evaluating and comparing small-scale to demonstration-scale performance. The authors cooperate closely with other ESP-CP tasks and the TFA to ultimately transfer the technologies being developed to the end user.

  2. Solid phase microextraction sampling of high explosive residues in the presence of radionuclides and radionuclide surrogate metals

    International Nuclear Information System (INIS)

    Duff, M.C.; Crump, S.L.; Ray, R.J.; Beals, D.; Cotham, W.E.; Mount, K.; Koons, R.D.; Leggitt, J.

    2008-01-01

    The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating high explosive (HE) evidence while maintaining evidentiary value. One experimental method for the isolation of HE residue involves using solid phase microextraction (SPME) fibers to remove residue of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most metals. However, no studies have measured the affinity of radionuclides for SPME fibers. The focus of this research was to examine the affinity of dissolved radionuclide ( 239/240 Pu, 238 U, 237 Np, 85 Sr, 133 Ba, 137 Cs, 60 Co and 226 Ra) and stable radionuclide surrogate metals (Sr, Co, Ir, Re, Ni, Ba, Cs, Nb, Ru, and Nd) for SPME fibers at the exposure conditions that favor the uptake of HE residues. Our results from radiochemical and mass spectrometric analyses indicate these metals have little measurable affinity for these SPME fibers during conditions that are conducive to HE residue uptake with subsequent analysis by liquid or gas phase chromatography with mass spectrometric detection. (author)

  3. Activity concentrations of radionuclides in energy production from peat, wood chips and straw

    Science.gov (United States)

    Hedvall, Robert Hans

    1997-11-01

    In this thesis quantitative analyses of radionuclide concentrations in bioenergy fuels such as peat, wood chips and straw are presented. For comparison a brief description is included of radionuclide concentrations and radiation doses from other sources of power and also from some industrial applications. Radiation is a natural phenomenon and radionuclides occur naturally. The first man-made spread of concentrated radioactivity occurred some 100,000 years ago when the first fireplace was lit, with fallout as a later consequence. Radioactive potassium is found in most materials and is the most easily detected nuclide in fuels. Its activity concentration in Bq kg-1 normally dominates over the concentration of other natural radionuclides. The radiation dose from potassium in the emission is nevertheless negligible. The most important radionuclides in the dose to humans are the U- and Th-isotopes and also 210Pb and 210Po. Of fission products in fallout from the atmospheric nuclear tests and after the Chernobyl accident, 137Cs was shown to be the most common nuclide. Compared to natural nuclides, the contribution from emission of 137Cs was shown to be the most common nuclide. Compared to natural nuclides, the contribution from emission of 137Cs is less than a few percent of the total dose to the population. A total dose of approximately a few μSv from inhalation only can be calculated from the emission of a district heating plant in Sweden. This dose can be compared with the annual dose limit to the public from nuclear industry, which is 0.1 mSv and the global collective effective dose of 5 person Sv a-1.

  4. On the optimization of empirical data concerning radionuclides in water of Lake Juodis

    International Nuclear Information System (INIS)

    Tarasiuk, N.; Koviazina, E.; Shliahtich, E.

    2004-01-01

    Quality of site-dependent water sampling for radionuclide analysis assessing their removal from the complicated aquatic system of eutrophic Lake Juodis is analyzed comparing time courses of site-specific data on standard variables (pH, temperature, redox potential, oxygen concentration, conductivity) in 2003-2004. Compared data were measured simultaneously: a) in the open bottom terrace of the lake adjoining its outflow; b) before the beaver dam bounding the lake rush grown area and c) at the site of the outflowing brook usually used for water sampling for radionuclide analysis. The rush grown area adjoining the outflowing brook is a natural filter for plutonium transport from the lake during warm season as well as for radiocesium activity fraction associated with the suspended matter. Using information on site-specific variations of vertical profiles of standard variables measured in the shallow bottom terrace of the lake, seasonal peculiarities of vertical radionuclide transport in the water column and their release from the sediments are discussed. In winter beaver activities in the lake as well as formation of the anaerobic zone in the rush grown area are considered as supplementary mechanisms facilitating vertical transport of radionuclides in the temperature stratificated water column and their removal from similar lakes. (author)

  5. Inhalant allergies in children.

    Science.gov (United States)

    Mims, James W; Veling, Maria C

    2011-06-01

    Children with chronic or recurrent upper respiratory inflammatory disease (rhinitis) should be considered for inhalant allergies. Risk factors for inhalant allergies in children include a first-degree relative with allergies, food allergy in infancy, and atopic dermatitis. Although inhalant allergies are rare in infancy, inhalant allergies are common in older children and impair quality of life and productivity. Differentiating between viral and allergic rhinitis can be challenging in children, but the child's age, history, and risk factors can provide helpful information. Allergic rhinitis is a risk factor for asthma, and if one is present, medical consideration of the other is warranted. Copyright © 2011 Elsevier Inc. All rights reserved.

  6. Inhalant Abuse and Dextromethorphan.

    Science.gov (United States)

    Storck, Michael; Black, Laura; Liddell, Morgan

    2016-07-01

    Inhalant abuse is the intentional inhalation of a volatile substance for the purpose of achieving an altered mental state. As an important, yet underrecognized form of substance abuse, inhalant abuse crosses all demographic, ethnic, and socioeconomic boundaries, causing significant morbidity and mortality in school-aged and older children. This review presents current perspectives on epidemiology, detection, and clinical challenges of inhalant abuse and offers advice regarding the medical and mental health providers' roles in the prevention and management of this substance abuse problem. Also discussed is the misuse of a specific "over-the-counter" dissociative, dextromethorphan. Copyright © 2016 Elsevier Inc. All rights reserved.

  7. Inhaled Drug Delivery: A Practical Guide to Prescribing Inhaler Devices

    Directory of Open Access Journals (Sweden)

    Pierre Ernst

    1998-01-01

    Full Text Available Direct delivery of medication to the target organ results in a high ratio of local to systemic bioavailability and has made aerosol delivery of respiratory medication the route of choice for the treatment of obstructive lung diseases. The most commonly prescribed device is the pressurized metered dose inhaler (pMDI; its major drawback is the requirement that inspiration and actuation of the device be well coordinated. Other requirements for effective drug delivery include an optimal inspiratory flow, a full inspiration from functional residual capacity and a breath hold of at least 6 s. Available pMDIs are to be gradually phased out due to their use of atmospheric ozone-depleting chlorofluorocarbons (CFCs as propellants. Newer pMDI devices using non-CFC propellants are available; preliminary experience suggests these devices greatly increase systemic bioavailability of inhaled corticosteroids. The newer multidose dry powder inhalation devices (DPIs are breath actuated, thus facilitating coordination with inspiration, and contain fewer ingredients. Furthermore, drug delivery is adequate even at low inspired flows, making their use appropriate in almost all situations. Equivalence of dosing among different devices for inhaled corticosteroids will remain imprecise, requiring the physician to adjust the dose of medication to the lowest dose that provides adequate control of asthma. Asthma education will be needed to instruct patients on the effective use of the numerous inhalation devices available.

  8. Comparative analysis of radionuclide inhalation and perfusion lung imaging with X ray pulmonary angiography for the diagnosis of pulmonary embolism

    International Nuclear Information System (INIS)

    Zhang Yanyan; Chen Man; Shao Maogang; Zhang Songlin; Mao Jieming; Guo Jingxuan

    1993-01-01

    The result of radionuclide lung imaging was compared in 18 patients of pulmonary embolism (PE) and 2 normal persons. The discovered perfusion defects correlated well with the location of angiographic obstruction. The positive angiographic and radionuclide finding was in 141 and 104 emboli arteries respectively. The sensitivity of total emboli pulmonary segments of lung imaging was 73.8%, the specificity was 82.7 and the accuracy was 79%. The techniques correlated quite well (r = 0.83, P<0.001)

  9. Assessment of inhalation risk due to radioactivity released from coal-based thermal power plant

    International Nuclear Information System (INIS)

    Sahu, S.K.; Pandit, G.G.; Shukla, V.K.; Puranik, V.D.; Kushwaha, H.S.

    2006-01-01

    In India, the coal based thermal power plants have been the major source of power generation in the past and would continue for decades to come. As the coal contains naturally occurring primordial radionuclides the burning of pulverized coal to produce energy for generation of electricity in thermal power plants will result in the emission of a variety of natural radioactive elements into the environment in the vicinity of thermal power plants. In this paper we have used two different methods for characterization of uncertainty in inhalation risk to the general public around 10 Kms radius in the neighborhood of a coal-fired thermal power plant. (author)

  10. Evaluation of a novel educational strategy, including inhaler-based reminder labels, to improve asthma inhaler technique.

    Science.gov (United States)

    Basheti, Iman A; Armour, Carol L; Bosnic-Anticevich, Sinthia Z; Reddel, Helen K

    2008-07-01

    To evaluate the feasibility, acceptability and effectiveness of a brief intervention about inhaler technique, delivered by community pharmacists to asthma patients. Thirty-one pharmacists received brief workshop education (Active: n=16, CONTROL: n=15). Active Group pharmacists were trained to assess and teach dry powder inhaler technique, using patient-centered educational tools including novel Inhaler Technique Labels. Interventions were delivered to patients at four visits over 6 months. At baseline, patients (Active: 53, CONTROL: 44) demonstrated poor inhaler technique (mean+/-S.D. score out of 9, 5.7+/-1.6). At 6 months, improvement in inhaler technique score was significantly greater in Active cf. CONTROL patients (2.8+/-1.6 cf. 0.9+/-1.4, p<0.001), and asthma severity was significantly improved (p=0.015). Qualitative responses from patients and pharmacists indicated a high level of satisfaction with the intervention and educational tools, both for their effectiveness and for their impact on the patient-pharmacist relationship. A simple feasible intervention in community pharmacies, incorporating daily reminders via Inhaler Technique Labels on inhalers, can lead to improvement in inhaler technique and asthma outcomes. Brief training modules and simple educational tools, such as Inhaler Technique Labels, can provide a low-cost and sustainable way of changing patient behavior in asthma, using community pharmacists as educators.

  11. Radionuclide toxicity

    International Nuclear Information System (INIS)

    Galle, P.

    1982-01-01

    The aim of this symposium was to review the radionuclide toxicity problems. Five topics were discussed: (1) natural and artificial radionuclides (origin, presence or emission in the environment, human irradiation); (2) environmental behaviour of radionuclides and transfer to man; (3) metabolism and toxicity of radionuclides (radioiodine, strontium, rare gas released from nuclear power plants, ruthenium-activation metals, rare earths, tritium, carbon 14, plutonium, americium, curium and einsteinium, neptunium, californium, uranium) cancerogenous effects of radon 222 and of its danghter products; (4) comparison of the hazards of various types of energy; (5) human epidemiology of radionuclide toxicity (bone cancer induction by radium, lung cancer induction by radon daughter products, liver cancer and leukaemia following the use of Thorotrast, thyroid cancer; other site of cancer induction by radionuclides) [fr

  12. Inhalant Dependence and its Medical Consequences

    Directory of Open Access Journals (Sweden)

    Mehmet Hamid Boztaş

    2010-12-01

    Full Text Available The term of inhalants is used for matters easily vapors. Inhalants are preferred for rapid, positive reinforcement and mild high effects. Products including inhalants are cheap, accessible, legal substances and are prevalently used in community. The prevalence of inhalant use in secondary schools in Turkey is about 5.1%. Inhalant substance dependence is generally observed within 14-15 age group. Age at first use could be as low as 5 to 6 years of age. Substance dependence is more probable in adults working in substance existing places. Inhalant usage is common in disadvantaged groups, children living in street, people with history of crimes, prison, depression, suicide, antisocial attitudes and conflict of family, history of abuse, violence and any other drug dependence and isolated populations. Inhalants are absorbed from lungs, after performing their quick and short effect metabolized by cytochrom P450 enzyme system except inhalant nitrites group which has a depressing effect like alcohol. In chronic use general atrophy, ventricular dilatation and wide sulcus were shown in cerebrum, cerebellum and pons by monitoring brain. Defects are mostly in periventricular, subcortical regions and in white matter. Demyelinization, hyperintensity, callosal slimming and wearing off in white and gray matter margins was also found. Ravages of brain shown by brain monitorisation are more and serious in inhalant dependence than in other dependences. It is important to decrease use of inhalants. Different approaches should be used for subcultures and groups in prevention. Prohibiting all the matters including inhalant is not practical as there are too many substances including inhalants. Etiquettes showing harmful materials can be used but this approach can also lead the children and adolescents recognize these substances easily.. Despite determintal effects of inhalant dependence, there are not yet sufficient number of studies conducted on prevention and

  13. Mapping of Natural Radionuclides using Noise Adjusted Singular Value Decomposition, NASVD

    DEFF Research Database (Denmark)

    Aage, Helle Karina

    2006-01-01

    Mapping of natural radionuclides from airborne gamma spectrometry suffer from random ”noise” in the spectra due to short measurement times. This is partly compensated for by using large volume detectors to improve the counting statistics. One method of further improving the quality of the measured...... spectra is to remove from the spectra a large fraction of this random noise using a special variant of Singular Value Decomposition: Noise Adjusted Singular Value Decomposition. In 1997-1999 the natural radionuclides on the Danish Island of Bornholm were mapped using a combination of the standard 3...

  14. Analysis of uncertainties in CRAC2 calculations: the inhalation pathway

    International Nuclear Information System (INIS)

    Killough, G.G.; Dunning, D.E. Jr.

    1984-01-01

    CRAC2 is a computer code for estimating the health effects and economic costs that might result from a release of radioactivity from a nuclear reactor to the environment. This paper describes tests of sensitivity of the predicted health effects to uncertainties in parameters associated with inhalation of the released radionuclides. These parameters are the particle size of the carrier aerosol and, for each element in the release, the clearance parameters for the lung model on which the code's dose conversion factors for inhalation are based. CRAC2 uses hourly meteorological data and a straight-line Gaussian plume model to predict the transport of airborne radioactivity; it includes models for plume depletion and population evacuation, and data for the distributions of population and land use. The code can compute results for single weather sequences, or it can perform random sampling of weather sequences from the meteorological data file and compute results for each weather sequence in the sample. For the work described in this paper, we concentrated on three fixed weather sequences that represent a range of conditions. For each fixed weather sequence, we applied random sampling to joint distributions of the inhalation parameters in order to estimate the sensitivity of the predicted health effects. All sampling runs produced coefficients of variation that were less than 50%, but some differences of means between weather sequences were substantial, as were some differences between means and the corresponding CRAC2 results without random sampling. Early injuries showed differences of as much as 1 to 2 orders of magnitude, while the differences in early fatalities were less than a factor of 2. Latent cancer fatalities varied by less than 10%. 19 references, 6 figures, 3 tables

  15. Estimation of risk for lung cancer induced by inhaled alpha-emitting radionuclides at very low doses

    International Nuclear Information System (INIS)

    Mahaffey, J.A.; Sanders, C.L.

    1979-01-01

    Results of statistical analyses of data from experiments in which rats were exposed to transuranics by inhalation imply that tumor incidence extrapolated to lower doses is not dependent on the chemical form of the transuranic. Using many questionable assumptions and several alternative models, most of the analyses predicted that irradiation at the current occupational exposure limit of 15 rem/year would increase the tumor incidence in rats to about three times the spontaneous incidence--the spontaneous incidence being defined by a single observed tumor

  16. Natural uranium-series radionuclide inventories in coastal and oceanic waters of the south-western Pacific - insights into trace metal flux and removal pathway analysis

    International Nuclear Information System (INIS)

    Szymczak, R.; Jeffree, R.A.; Peck, G.A.

    2003-01-01

    Participate scavenging of trace metals plays a major role in determining their ecosystem flux and incident dissolved concentrations. Differences in the half-lives and biogeochemical behaviour of natural uranium series radioisotope pairs (eg. 238 U/ 234 Th, 210 Pb/ 210 Po) allow their application as oceanic process tracers. Coincidental measurements of dissolved and particulate trace element concentrations and inventories of radionuclides in the Noumea coral lagoon and adjacent offshore waters were used to quantify water column flux rates and provide insights on removal pathway analysis. Understanding prevailing pathways and respective flux rates of pollutants in specific coastal and oceanic systems will assist to establish the fate and consequence of pollutants and allow sustainable management strategies to be developed. Both natural and pollutant chemical species introduced to the marine environment may either remain benign in solution or undergo physiological uptake by biota, but most often associate with colloids and fine particles, which subsequent undergo aggregation, sedimentation and removal to the sea floor

  17. Methods of separating short half-life radionuclides from a mixture of radionuclides

    International Nuclear Information System (INIS)

    Bray, L.A.; Ryan, J.L.

    1998-01-01

    The present invention is a method of obtaining a radionuclide product selected from the group consisting of 223 Ra and 225 Ac, from a radionuclide ''cow'' of 227 Ac or 229 Th respectively. The method comprises the steps of (a) permitting ingrowth of at least one radionuclide daughter from said radionuclide ''cow'' forming an ingrown mixture; (b) insuring that the ingrown mixture is a nitric acid ingrown mixture; (c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the ''cow'' from at least one radionuclide daughter; (d) insuring that the at least one radionuclide daughter contains the radionuclide product; (e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and (f) recycling the at least one radionuclide daughter by adding it to the ''cow''. In one embodiment the radionuclide ''cow'' is the 227 Ac, the at least one daughter radionuclide is a 227 Th and the product radionuclide is the 223 Ra and the first nitrate form ion exchange column passes the 227 Ac and retains the 227 Th. In another embodiment the radionuclide ''cow'' is the 229 Th, the at least one daughter radionuclide is a 225 Ra and said product radionuclide is the 225 Ac and the 225 Ac and nitrate form ion exchange column retains the 229 Th and passes the 225 Ra/Ac. 8 figs

  18. Impact assessment of radionuclides released to environment from the European Spallation Source

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, S.; Andersson, K. [Technical University of Denmark (Denmark); Ene, D. [European Spallation Soure AB - ESS, Lund (Sweden)

    2014-07-01

    The European Spallation Source (ESS) is a large science and technology infrastructure project currently under construction in Lund, Sweden, with operation planned by 2019. The facility design and construction includes a linear proton accelerator, a heavy-metal target station, neutron instruments, laboratories, and a data management and software development centre. During operation the ESS will produce a wide range of radionuclides via spallation and activation processes. Radiological assessments are needed to ensure that operational discharges and releases from potential incidents/accidents are within acceptable limits. The spectrum of radionuclides produced at ESS is quite different from that produced in nuclear power plants and assessment work has therefore been challenged by lack of information on less well-known radionuclides. Traditional assessment methodologies have been applied focusing on releases to air and public sewer systems and calculating radiation doses to representative persons living in and near Lund close to the ESS site. Exposure pathways considered include external radiation from radionuclides in air, external radiation from radionuclides deposited on ground and skin, inhalation of radionuclides and ingestion of locally produced contaminated food. Atmospheric dispersion has been simulated with the Gaussian plume model which is considered adequate within a few kilometres. Effects of release height have been investigated and site specific values of other parameters such as wind speed, wind direction, rain fall etc. have been used. Contamination of food has been calculated from the (ECOSYS) food dose model used in the RODOS and ARGOS decision support systems. The food dose model does not contain specific data for a number of ESS relevant radionuclides, e.g. {sup 7}Be, {sup 32}P and {sup 35}S. The data required include mobility of these isotopes, soil-to-plant concentration ratios and equilibrium transfer factors of daily intake by ingestion of meat

  19. Comparative effects of inhaled relatively insoluble forms of 90Y, 144Ce, and 90Sr on canine peripheral lymphocyte function

    International Nuclear Information System (INIS)

    Benjamin, S.A.; Jones, R.K.; Snipes, M.B.; Lustgarten, C.S.

    1976-01-01

    Dogs that have inhaled relatively insoluble forms of either alpha- or beta-emitting radionuclides manifest a peripheral lymphopenia, the development and course of which depends on both total dose and dose rate. The remaining peripheral lymphocytes in dogs exposed to longer lived beta-emitting radionuclides showed a depressed function as measured by the ability to respond to plant mitogens in vitro. This experiment was designed to evaluate the effect of dose rate on peripheral lymphocyte function by exposing dogs to aerosols of radionuclides with varied effective half-lives in the lung: 90 Y (2.6 days), 144 Ce (170 days), and 90 Sr (650 days). Three groups of four adult beagle dogs each were exposed by inhalation to 90 Y, 144 Ce, or 90 Sr in fused-clay particles. Two controls were matched with each group. Initial lung burdens and initial dose rates to the lung were 520 to 610 μCi/kg of body weight and 2200 to 2600 rads/day in the 90 Y group, 33 to 60 μCi/kg and 200 to 350 rads/day in the 144 Ce group, and 25 to 32 μCi/kg and 130 to 170 rads/day in the 90 Sr group. Hematologic parameters and lymphocyte function as measured by the ability of lymphocytes to respond to plant mitogen stimulation were evaluated on a weekly or biweekly basis for 8 weeks after exposure and on a monthly basis thereafter. The 90 Y-exposed dogs showed a marked lymphopenia within 1 week with a return to control levels by 20 weeks after exposure. The remaining peripheral lymphocytes, however, showed no functional changes in these dogs. Animals exposed to 144 Ce or 90 Sr developed a progressive and persisent lymphopenia and showed functional depression of the remaining lymphocytes as well. The relationships among dose pattern, lymphopenia, and lymphocyte-function depression are discussed

  20. Effect of Some Therapeutic Agents on the Radionuclides Excretion from Internally Contaminated Rats

    International Nuclear Information System (INIS)

    Aziz, M.; Mangood, Sh.A.; Sohsah, M.A.

    2009-01-01

    The present work was oriented to investigate the effectiveness of Prussian blue (PB), vermiculite and diethylenetriaminepentaacetic acid (CaDTPA) as therapeutic agents for the elimination of either 134 Cs or 60 Co from contaminated rats after intake of one of the isotopes. The study was performed by using 48 adult rats divided into 8 identical groups each of six rats having approximately the same body weight. The groups included a reference group, without isotope or therapeutic agent administration, four groups given one of the isotopes and four groups given the isotopes and treated with different therapeutic regimes. The isotope content of the treated and untreated contaminated rats were followed by daily whole body radiometric counting for three weeks. On plotting log % radionuclide retained as a function of time, elapsed between radionuclide administration and radiometric counting, straight lines were obtained. The results indicate that excretion can mostly be represented by two stages; the first is fast followed by a second slow stage. The % radionuclide excreted, the corresponding rate constant and the biological half-life of each stage was estimated. It was found that the application of PB + vermiculite is more efficient, to remove 134 Cs, from contaminated rats, than PB only and CaDTPA is more efficient to remove 60Co. Therefore, it is recommended to use the three therapeutic agents to remove both isotopes when taken simultaneously

  1. Methods of separating short half-life radionuclides from a mixture of radionuclides

    Science.gov (United States)

    Bray, Lane A.; Ryan, Jack L.

    1998-01-01

    The present invention is a method of obtaining a radionuclide product selected from the group consisting of .sup.223 Ra and .sup.225 Ac, from a radionuclide "cow" of .sup.227 Ac or .sup.229 Th respectively. The method comprises the steps of a) permitting ingrowth of at least one radionuclide daughter from said radionuclide "cow" forming an ingrown mixture; b) insuring that the ingrown mixture is a nitric acid ingrown mixture; c) passing the nitric acid ingrown mixture through a first nitrate form ion exchange column which permits separating the "cow" from at least one radionuclide daughter; d) insuring that the at least one radionuclide daughter contains the radionuclide product; e) passing the at least one radionuclide daughter through a second ion exchange column and separating the at least one radionuclide daughter from the radionuclide product and f) recycling the at least one radionuclide daughter by adding it to the "cow". In one embodiment the radionuclide "cow" is the .sup.227 Ac, the at least one daughter radionuclide is a .sup.227 Th and the product radionuclide is the .sup.223 Ra and the first nitrate form ion exchange column passes the .sup.227 Ac and retains the .sup.227 Th. In another embodiment the radionuclide "cow"is the .sup.229 Th, the at least one daughter radionuclide is a .sup.225 Ra and said product radionuclide is the .sup.225 Ac and the .sup.225 Ac and nitrate form ion exchange column retains the .sup.229 Th and passes the .sup.225 Ra/Ac.

  2. Contribution of maternal radionuclide burdens to prenatal radiation doses: Relationships between annual limits on intake and prenatal doses

    International Nuclear Information System (INIS)

    Sikov, M.R.; Hui, T.E.

    1993-10-01

    This addendum describes approaches for calculating and expressing radiation doses to the embryo/fetus from maternal intakes of radionuclides at levels corresponding to fractions or multiples of the Annual Limits on Intake (ALI). Information, concerning metabolic or dosimetric characteristics and the placental transfer of selected, occupationally significant radionuclides was presented in NUREG/CR-5631, Revision 1. That information was used to estimate levels of radioactivity in the embryo/fetus as a function of stage of pregnancy and time after entry. Extension of MIRD methodology to accommodate gestational-stage-dependent characteristics allowed dose calculations for the simplified situation based on introduction of 1 μCi into the woman's transfer compartment (blood). The expanded scenarios in this addendum include repeated or chronic ingestion or inhalation intakes by a woman during pregnancy and body burdens at the beginning of pregnancy. Tables present dose equivalent to the embryo/fetus relative to intakes of these radionuclides in various chemical or physical forms and from preexisting maternal burdens corresponding to ALI; complementary intake values (fraction of an ALI and μCi) that yield a dose equivalent of 0.05 rem are included. Similar tables give these measures of dose equivalency to the uterus from intakes of radionuclides for use as surrogates for embryo/fetus dose when biokinetic information is not available

  3. Decontamination of radionuclides on construction materials

    International Nuclear Information System (INIS)

    Samuleev, P.V.; Andrews, W.S.; Creber, K.A.M.; Velicogna, D.

    2013-01-01

    A wide variety of materials can become contaminated by radionuclides, either from a terrorist attack or an industrial or nuclear accident. The final disposition of these materials depends, in large part, on the effectiveness of decontamination measures. This study reports on investigations into the decontamination of a selection of building materials. The aim has been to find an effective, easy-to-use and inexpensive decontamination system for radionuclides of cesium and cobalt, considering both the chemical and physical nature of these potential contaminants. The basic method investigated was surface washing, due to its ease and simplicity. In the present study, a basic decontamination formulation was modified by adding isotope-specific sequestering agents, to enhance the removal of cesium(I) and cobalt(II) from such construction materials as concrete, marble, aluminum and painted steel. Spiking solutions contained 134 Cs or 60 Co, which were prepared by neutron activation in the SLOWPOKE-2 nuclear reactor facility at the Royal Military College of Canada. Gamma spectroscopy was used to determine the decontamination efficiency. The results showed that the addition of sequestering agents generally improved the radiological decontamination. Although the washing of both cesium and cobalt from non-porous materials, such as aluminum and painted steel, achieved a 90-95 % removal, the decontamination of concrete and marble was more challenging, due to the porous nature of the materials. Nevertheless, the removal efficiency from 6-year-old concrete increased from 10 % to approximately 50 % for cobalt(II), and from 18 to 55 % for cesium(I), with the use of isotope binding agents, as opposed to a simple water wash. (author)

  4. Effects of combined exposure of F344 rats to inhaled Plutonium-239 dioxide and a chemical carcinogen (NNK)

    Energy Technology Data Exchange (ETDEWEB)

    Lundgren, D.L.; Carlton, W.W. [Purdue Univ., Lafayette, IN (United States); Griffith, W.C. [and others

    1995-12-01

    Workers in nuclear weapons facilities have a significant potential for exposure to chemical carcinogens and to radiation from external sources or from internally deposited radionuclides such as {sup 239}Pu. Although the carcinogenic effects of inhaled {sup 239}Pu and many chemicals have been studied individually, very little information is available on their combined effects. One chemical carcinogen that workers could be exposed to via tobacco smoke is the tobacco-specific nitrosamine 4-(N-methyl-n-nitrosamino)-1-(3-pyridyl)-1(3-pyridyl)-1-butanone (NNK), a product of tobacco curing and the pyrolysis of nicotine in tobacco. NNK causes lung tumors in rats, regardless of the route of administration and to a lesser extent liver, nasal, and pancreatic tumors. From the results presented, it can be concluded that exposure to a chemical carcinogen (NNK) in combination with {alpha}-particle radiation from inhaled {sup 239}PuO{sub 2} acts in, at best, an additive manner in inducing lung cancer in rats.

  5. Effects of indoor residence on radiation doses from routine releases of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Kocher, D.C.

    1980-01-01

    Dose reduction factors from indoor residence during routine releases of radionuclides to the atmosphere were studied using models that are suitable for application to arbitrary source terms. Dose reduction factors for internal exposure to inhaled radionuclides account for air ventilation and deposition on inside building surfaces. Estimated internal dose reduction factors are approx. 0.2 to 0.8 for particulates and 0.07 to 0.4 for radioiodine. Dose reduction factors for external photon exposure from airborne and surface-deposited sources are based on the point-kernel integration method. Values for source terms from a fuel reprocessing plant and a hypothetical reactor accident are within a factor of 2 of the value 0.5 adopted by the US Nuclear Regulatory Commission (NRC) for population dose assessments. For the release at Three Mile Island nuclear station, however, the external dose reduction factor may be an order of magnitude less than the value adopted by the NRC

  6. Allowable residual contamination levels of radionuclides in soil from pathway analysis

    International Nuclear Information System (INIS)

    Nyquist, J.E.; Baes, C.F. III

    1987-01-01

    The Remedial Action Program (RAP) at Oak Ridge National Laboratory will include well drilling, facility upgrades, and other waste management operations likely to involve soils contaminated with radionuclides. A preliminary protocol and generalized criteria for handling contaminated soils is needed to coordinate and plan RAP activities, but there exists only limited information on contaminate nature and distribution at ORNL RAP sites. Furthermore, projections of long-term decommissioning and closure options for these sites are preliminary. They have adapted a pathway analysis model, DECOM, to quantify risks to human health from radionuclides in soil and used it to outline preliminary criteria for determining the fate of contaminated soil produced during RAP activities. They assumed that the site could be available for unrestricted use immediately upon decontamination. The pathways considered are consumption of food grown on the contaminated soil, including direct ingestion of soil from poorly washed vegetables, direct radiation from the ground surface, inhalation of resuspended radioactive soil, and drinking water from a well drilled through or near the contaminated soil. We will discuss the assumptions and simplifications implicit in DECOM, the site-specific data required, and the results of initial calculations for the Oak Ridge Reservation

  7. Toxicity of 144Ce fused clay particles inhaled by immature beagle dogs. III

    International Nuclear Information System (INIS)

    Boecker, B.B.; McClellan, R.O.; Hahn, F.F.; Hobbs, C.H.; Mauderly, J.L.

    1974-01-01

    The metabolism, dosimetry, and biological effects of 144 Ce fused clay particles inhaled by immature Beagle dogs (approximately 3 months of age at exposure) are being investigated for comparison with studies of dogs exposed at 12 to 14 months of age and 8 to 10.5 years of age. These studies will assess possible age-related differences in the biological behavior and effects of inhaled radionuclides, differences that may be of significance in predicting the response of accidentally-exposed human populations that include individuals of different ages. Eighteen immature dogs have been entered into a radiation dose pattern study to be serially sacrificed at different intervals after inhalation exposure. During the first 2 months post-exposure, lung clearance and uptake by the tracheobronchial lymph nodes appeared to be greater in the immature dogs than in young adult dogs. Also, skeletal uptake was greater than hepatic uptake in the immature dogs. Three blocks of longevity animals, 10 per block, with graded initial lung burdens ranging from 0.004 to 120 μCi 144 Ce/kg body weight and 1 control, are currently on experiment. Three dogs with initial lung burdens of 73 to 120 μCi 144 Ce/kg body weight died at 66 to 121 days after exposure with pulmonary injury and congestive heart failure. Another dog with an initial lung burden of 70 μCi 144 Ce/kg body weight died at 511 days after exposure with pulmonary injury. Serial observations are continuing on the surviving 26 144 Ce-exposed and 3 control dogs. (U.S.)

  8. The removal of radionuclides from contaminated milk and meat

    International Nuclear Information System (INIS)

    Long, S.C.; Sequeira, S.; Pollard, D.; Fedin, F.A.; Krylova, N.V.

    1996-01-01

    The transfer of radiocesium and radiostrontium from milk to a number of commonly consumed European and Ukrainian cheeses was quantified. The F f 1 for radiocesium in these cheeses was typically between 0.5 and 0.7, while that for radiostrontium ranged from 0.7 to 8.3. Those steps during the cheese making process that resulted in removal of radiocesium were then identified. The production of cheeses by modified technologies succeeded in reducing the radiostrontium transfer by a small amount. Acidification of the milk (to a pH < 5.1) prior to coagulation resulted in a significantly smaller transfer of radiostrontium to the cheese. The coagulation process varied by up to 20% for duplicate experiments. At least 50% of radiocesium may be removed from contaminated meat by soaking in NaCI solution (brine). Greater removal (up to 90%) may be achieved by varying treatment parameters. The losses of vitamins and minerals associated with this treatment were quantified

  9. Know How to Use Your Asthma Inhaler

    Medline Plus

    Full Text Available ... KB] Using a metered dose inhaler (inhaler in mouth) Your browser does not support iframes Using a metered dose inhaler (inhaler in mouth) [PDF – 370 KB] Your browser does not support ...

  10. Past and present levels of some radionuclides in fish from Bikini and Enewetak Atolls.

    Science.gov (United States)

    Noshkin, V E; Robison, W L; Wong, K M; Brunk, J L; Eagle, R J; Jones, H E

    1997-07-01

    Bikini and Enewetak were the sites in the Northern Marshall Islands that were used by the United States as testing grounds for nuclear devices between 1946 and 1958. The testing produced close-in fallout debris that was contaminated with different radionuclides and which entered the aquatic environment. The contaminated lagoon sediments became a reservoir and source term of manmade radionuclides for the resident marine organisms. This report contains a summary of all the available data on the concentrations of 137Cs, 60Co and 207Bi in flesh samples of reef and pelagic fish collected from Bikini and Enewetak Atolls between 1964 and 1995. The selection of these three radionuclides for discussion is based on the fact that these are the only radionuclides that have been routinely detected by gamma spectrometry in flesh samples from all fish for the last 20 y. Flesh from fish is an important source of food in the Marshallese diet. These radionuclides along with the transuranic radionuclides and 90Sr contribute most of the small radiological dose from ingesting marine foods. Some basic relationships among concentrations in different tissues and organs are discussed. The reef fish can be used as indicator species because their body burden is derived from feeding, over a lifetime, within a relatively small contaminated area of the lagoon. Therefore, the emphasis of this report is to use this extensive and unique concentration data base to describe the effective half lives and cycling for the radionuclides in the marine environments during the 31-y period between 1964 and 1995. The results from an analysis of the radionuclide concentrations in the flesh samples indicate the removal rates for the 3 radionuclides are significantly different. 137Cs is removed from the lagoons with an effective half life of 9-12 y. Little 60Co is mobilized to the water column so that it is depleted in both environments, primarily through radioactive decay. The properties of 207Bi are different

  11. 238U-series radionuclides in Finnish groundwater-based drinking water and effective doses

    International Nuclear Information System (INIS)

    Vesterbacka, P.

    2005-09-01

    The thesis deals with the occurrence of 238 U-series radionuclides and particle-bound 210 Pb and 210 Po in Finnish groundwater-based drinking water, methods used for removing 234 U, 238 U, 210 Pb and 210 Po, and the annual effective doses caused by 238 U-series radionuclides in drinking water. In order to reduce radiation exposure and avoid high doses, it is important to examine the activity levels of natural radionuclides in groundwater. In this work, the activity concentrations of radon ( 222 Rn), radium ( 226 Ra), uranium ( 238 U and 234 U), lead ( 210 Pb) and polonium ( 210 Po) were determined from 472 private wells, which were selected randomly from across Finland. On the basis of the results, the activity concentrations in groundwater and the radiation exposure from drinking water of people living outside the public water supply in Finland was specified. The efficiency of 238 U, 234 U, 210 Pb and 210 Po removal from drinking water was examined at ten private homes. In order to obtain accurate results and correct estimates of effective doses, attention was paid to the sampling of 222 Rn and 210 Pb, and the determination of 210 Pb. The results revealed that the median activity concentrations of natural radionuclides were as much as ten times higher in drilled wells than in wells dug in soil. The average activity concentration of 222 Rn in drilled wells was 460 Bq/l and in dug wells 50 Bq/l. The highest activity concentrations were found in Southern Finland. In addition, occasional high activity concentrations were found all over Finland. The average activity concentrations of 234 U and 238 U in drilled wells were 0.35 and 0.26 Bq/l and in dug wells 0.020 and 0.015 Bq/l, respectively. The spatial distribution of 234 U, 238 U, 210 Pb and 210 Po was essentially similar to that of 222 Rn. In contrast to other natural radionuclides, the highest 226 Ra activity concentrations were found in coastal areas, since drilled well water near the sea has a higher salinity

  12. Radionuclide emissions from a coal-fired power plant

    International Nuclear Information System (INIS)

    Amin, Y.M.; Uddin Khandaker, Mayeen; Shyen, A.K.S.; Mahat, R.H.; Nor, R.M.; Bradley, D.A.

    2013-01-01

    Current study concerns measurement of radioactivity levels in areas surrounding a 2420 MW thermal power plant fueled predominantly by bituminous coal. The concentrations of 226 Ra, 232 Th and 40 K in onsite bottom-ash were found to be 139 Bq/kg, 108 Bq/kg and 291 Bq/kg, respectively, the levels for these radiolnuclides in soil decreasing with distance from the power plant. At the plant perimeter the respective radionuclide concentrations were 87 Bq/kg, 74 Bq/kg and 297 Bq/kg. In a nearby town, the corresponding concentrations were 104 Bq/kg, 52 Bq/kg and 358 Bq/kg, suggestive of use of TENORM affected soils. The mean radium equivalent activities (Ra eq ) in soil and ash sample in the town were 205 Bq/kg and 316 Bq/kg, respectively. The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste. For the prevailing levels of exposure and a worst case senario, the predicted committed effective dose due to ingestion and inhalation for intake durations of 1- and 30 years would be 4.2 μSv and 220 μSv, respectively. - Highlights: • Detailed studies on naturally occuring radionuclide emissions due to a 2420 MW coal-fired power plant in Malaysia. • Assessment of radiation exposures to the public around the power plant due to an intake of the radionuclides. • The Kapar plant ash/slag appears to contain a higher level of TENORM than the world average. • The degree of contamination is much higher inside the town where slag has been mixed with topsoil as landfill or as simple domestic waste

  13. Studies of decontamination using easy removable coatings technique

    International Nuclear Information System (INIS)

    Oglaza, J.; Nowak, Z.

    1991-01-01

    The usefulness of removable coatings for decontamination of steel and epoxy-resin painted surfaces was examined. Natural latex, Revultex, butadiene-styrene latex as well as mixtures of latex with complexing agents and surfactants were used as decontaminating coats. The best decontamination was obtained by removable coatings of natural latex with EDTA additive for all surfaces and radionuclides tested. (author). 16 refs, 5 tabs

  14. Radionuclides in peat bogs and energy peat; Turvesoiden ja polttoturpeen radionuklidit

    Energy Technology Data Exchange (ETDEWEB)

    Helariutta, K.; Rantavaara, A. [Radiation and Nuclear Safety Authority, Helsinki (Finland); Lehtovaara, J. [Vapo Oy, Jyvaeskylae (Finland)

    2000-06-01

    The study was aimed at improving the general view on radionuclides contents in energy peat produced in Finland. The annual harvest of fuel peat in 1994 was studied extensively. Also thirteen peat bogs used for peat production and one bog in natural condition were analysed for vertical distributions of several radionuclides. These distributions demonstrate the future change in radioactivity of energy peat. Both natural nuclides emitting gamma radiation ({sup 238}U, {sup 235}U, {sup 232}Th, {sup 226}Ra, {sup 40}K) and radiocaesium ({sup 137}Cs, {sup 134}Cs) origin in fallout from a nuclear power plant accident (1986) and in atmospheric nuclear weapon tests were analysed. The beta and alpha active natural nuclides of lead and polonium ({sup 210}Pb, {sup 210}Po) were determined on a set of peat samples. These nuclides potentially contribute to radiation exposure through inhalation when partially released to atmosphere during combustion of peat. The activity concentrations of natural radionuclides often increased towards the deepest peat bog layers whereas the radioactive caesium deposited from atmosphere was missing in the deep layers. In undisturbed surface layers of a natural bog and peat production bogs the contents of {sup 210}Pb and {sup 210}Po exceeded those of the deeper peat layers. The nuclides of the uranium series in the samples were generally not in radioactive equilibrium, as different environmental processes change their activity ratios in peat. Radiation exposure from handling and utilisation of peat ash was estimated with activity indices derived from the data for energy peat harvested in 1994. Intervention doses were exceeded in a minor selection of samples due to {sup 137}Cs, whereas natural radionuclides contributed very little to the doses. (orig.)

  15. Radionuclide trap

    International Nuclear Information System (INIS)

    McGuire, J.C.

    1978-01-01

    The deposition of radionuclides manganese-54, cobalt-58 and cobalt-60 from liquid sodium coolant is controlled by providing surfaces of nickel or high nickel alloys to extract the radionuclides from the liquid sodium, and by providing surfaces of tungsten, molybdenum or tantalum to prevent or retard radionuclide deposition

  16. Electrostatic Properties of Particles for Inhalation

    OpenAIRE

    Rowland, Martin

    2015-01-01

    Dry powder inhalers (DPIs) and pressurised metered dose inhalers (pMDIs) aredevices used to deliver therapeutic agents to the lungs. Typically, inhaled activepharmaceutical ingredients (APIs) are electrically resistive materials and are prone toaccumulating electrostatic charge. The build-up of charge on inhaled therapeutics hastraditionally been viewed as a nuisance as it may result in problems such as weighingerrors, agglomeration, adhesion to surfaces and poor flow. Energetic processing st...

  17. Inhaled americium dioxide

    International Nuclear Information System (INIS)

    Park, J.F.

    1982-01-01

    This project includes experiments to determine the effects of Zn-DTPA therapy on the retention, translocation and biological effects of inhaled 241 AmO 2 . Beagle dogs that received inhalation exposure to 241 AmO 2 developed leukopenia, clincial chemistry changes associated with hepatocellular damage, and were euthanized due to respiratory insufficiency caused by radiation pneumonitis 120 to 131 days after pulmonary deposition of 22 to 65 μCi 241 Am. Another group of dogs that received inhalation exposure to 241 AmO 2 and were treated daily with Zn-DTPA had initial pulmonary deposition of 19 to 26 μCi 241 Am. These dogs did not develop respiratory insufficiency, and hematologic and clinical chemistry changes were less severe than in the non-DTPA-treated dogs

  18. Effects of inhaled plutonium nitrate on bone and liver in dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Weller, R.E.; Watson, C.R.; Buschbom, R.L.

    1994-04-01

    The life-span biological effects of inhaled soluble, alpha-emitting radionuclides deposited in the skeleton and liver were studied in 5 groups of 20 beagles exposed to initial lung depositions ranging from 0.48 to 518 Bq/g of lung. Average plutonium amounts in the lungs decreased to approximately 1% of the final body deposition in dogs surviving 5 years or more; more than 90% of the final depositions accumulated in the liver and skeleton. The liver-to-skeletal ratio of deposited plutonium was 0.83. The incidence of bone tumors, primarily osteogenic sarcomas causing early mortality, at final group average skeletal depositions of 15.8, 2.1, and 0.5 Bq/g was, respectively, 85%, 50%, and 5%; there were no bone tumors in exposure groups with mean average depositions lower than 0.5 Bq/g. Elevated serum liver enzyme levels were observed in exposure groups down to 1.3 Bq/g. The incidence of liver tumors at final group average liver depositions of 6.9, 1.3, 0.2, and 0.1 Bq/g, was, respectively, 25%, 15%, 15%, and 15%; one hepatoma occurred among 40 control dogs. The risk of the liver cancer produced by inhaled plutonium nitrate was difficult to assess due to the competing risks of life shortening from lung and bone tumors

  19. Evaluation and selection of aqueous-based technology for partitioning radionuclides from ICPP calcine

    International Nuclear Information System (INIS)

    Olson, A.L.; Schulz, W.W.; Burchfield, L.A.; Carlson, C.D.; Swanson, J.L.; Thompson, M.C.

    1993-02-01

    Early in 1993 Westinghouse Idaho Nuclear Company (WINCO) chartered a Panel of Nuclear Separations Experts. The purpose of this Panel was to assist WINCO scientists and engineers in selecting, evaluating, and ranking candidate aqueous-based processes and technologies for potential use in partitioning selected radionuclides from nitric acid solutions of retrieved Idaho Chemical Processing Plant (ICPP) calcine. Radionuclides of interest are all transuranium elements, 90 Sr, 99 Tc, 129 I, and 137 Cs. The six man Panel met for 4 days (February 16--19, 1993) on the campus of the Idaho State University in Pocatello, Idaho. Principal topics addressed included: Available radionuclide removal technology; applicability of separations technology and processes to ICPP calcine; and potential integrated radionuclide partitioning schemes. This report, prepared from contributions from all Panel members, presents a comprehensive account of the proceedings and significant findings of the February, 1993 meeting in Pocatello

  20. Removal of inhaled 241Am oxide particles from beagle dogs by combined treatment with lung lavage and a chelating agent

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Mo, T.; Slauson, D.O.

    1978-01-01

    This experiment was performed to evaluate combined therapy of lung lavage and chelation treatments to remove inhaled particles of 241 Am oxide. Twenty-four Beagle dogs were divided into four groups of 6 dogs each. Each group was exposed to an aerosol of different-sized particles of 241 Am oxide: monodisperse particles with AD of 0.75, 1.5 or 3.0 μm; polydisperse particles with AMAD = 1.5 μm. Three dogs in each group were treated with 5 lung lavages of the right lung (day 2, 7, 14, 28 and 42), and 5 lavages of the left lung (days 2, 10, 21, 35, and 49). In addition, each of the treated dogs was given 22 μmoles of trisodium calcium diethylenetriaminepentaacetate (Na 3 Ca DTPA) by intravenous injection 18 times from day 1 to 52 after exposure. The remaining 3 dogs in each group were untreated control dogs. All of the dogs were sacrificed 64 days after exposure and tissues, excreta, and lavage fluids were analyzed for 241 Am activity. Tissue distribution of 241 Am activity at sacrifice varied with aerosol particle size. Less 241 Am activity was found in the lungs of the dogs exposed to 0.75 and 1.5 μm AD aerosols groups than in those exposed to 3.0 μm particles. Lung lavage removed from 24 to 58% of the initial lung burden (ILB). Particle size did not affect the usefulness of lung lavage but it did influence the effectiveness of Na 3 Ca DTPA treatment. Na 3 Ca DTPA enhanced urinary excretion of 241 Am; dogs exposed to 0.75 μm particles excreted 31% of the ILB, and those exposed to 3.0 μm particles excreted only 10%. This experiment showed the effectiveness of combined treatment with lung lavage and chelation therapy for the removal of 241 Am oxide in the first 64 days after exposure. (author)

  1. Radiation, radionuclides and bacteria: An in-perspective review.

    Science.gov (United States)

    Shukla, Arpit; Parmar, Paritosh; Saraf, Meenu

    2017-12-01

    There has been a significant surge in consumption of radionuclides for various academic and commercial purposes. Correspondingly, there has been a considerable amount of generation of radioactive waste. Bacteria and archaea, being earliest inhabitants on earth serve as model microorganisms on earth. These microbes have consistently proven their mettle by surviving extreme environments, even extreme ionizing radiations. Their ability to accept and undergo stable genetic mutations have led to development of recombinant mutants that are been exploited for remediation of various pollutants such as; heavy metals, hydrocarbons and even radioactive waste (radwaste). Thus, microbes have repeatedly presented themselves to be prime candidates suitable for remediation of radwaste. It is interesting to study the behind-the-scenes interactions these microbes possess when observed in presence of radionuclides. The emphasis is on the indigenous bacteria isolated from radionuclide containing environments as well as the five fundamental interaction mechanisms that have been studied extensively, namely; bioaccumulation, biotransformation, biosorption, biosolubilisation and bioprecipitation. Application of microbes exhibiting such mechanisms in remediation of radioactive waste depends largely on the individual capability of the species. Challenges pertaining to its potential bioremediation activity is also been briefly discussed. This review provides an insight into the various mechanisms bacteria uses to tolerate, survive and carry out processes that could potentially lead the eco-friendly approach for removal of radionuclides. Copyright © 2017 Elsevier Ltd. All rights reserved.

  2. Radionuclide cisternography

    International Nuclear Information System (INIS)

    Song, H.H.

    1980-01-01

    The purpose of this thesis is to show that radionuclide cisternography makes an essential contribution to the investigation of cerebrospinal fluid (CSF) dynamics, especially for the investigation of hydrocephalus. The technical details of radionuclide cisternography are discussed, followed by a description of the normal and abnormal radionuclide cisternograms. The dynamics of CFS by means of radionuclide cisternography were examined in 188 patients in whom some kind of hydrocephalus was suspected. This study included findings of anomalies associated with hydrocephalus in a number of cases, such as nasal liquorrhea, hygromas, leptomeningeal or porencephalic cysts. The investigation substantiates the value of radionuclide cisternography in the diagnosis of disturbances of CSF flow. The retrograde flow of radiopharmaceutical into the ventricular system (ventricular reflux) is an abnormal phenomenon indicating the presence of communicating hydrocephalus. (Auth.)

  3. Suffocation caused by plastic wrap covering the face combined with nitrous oxide inhalation.

    Science.gov (United States)

    Leth, Peter Mygind; Astrup, Birgitte Schmidt

    2017-09-01

    Suicide using a combination of a plastic bag over the head and inhalation of a non-irritating gas, such as helium, argon or nitrogen, has been reported in the literature. Here an unusual suicide method in a 17-year old man by suffocation from covering the face with household plastic wrap, combined with nitrous oxide inhalation, is presented. The case was reviewed based on police, autopsy and hospital reports. A PubMed search for scientific literature related to nitrous oxide abuse and suicide by suffocation was performed and our findings discussed in relation to the scientific literature found. The deceased was a 17-year old man who was found with the nose and mouth closed with a piece of kitchen plastic wrap. The plastic wrap had been removed prior to autopsy. Autopsy findings were suggestive of asphyxia, but were otherwise negative. Nitrous oxide was detected in the brain and lung tissue with headspace-gas chromatography-mass spectrometry (headspace-GCMS). The cause of death was assumed to be suffocation caused by plastic wrap covering the face, combined with nitrous oxide inhalation. Suicide was suspected because of a history of depression for several months. Nitrous oxide, also known as laughing gas, has a euphoric effect and is used as a recreational inhalant drug that can be purchased legally. Deaths caused by recreational nitrous oxide abuse are rare but may occur if used in combination with a plastic bag over the head. This is the first report of suicide by suffocation by external obstruction combined with nitrous oxide inhalation.

  4. Microorganisms as potential vectors of the migration of radionuclides?

    International Nuclear Information System (INIS)

    Yves, A.

    1998-01-01

    The aims of our work are the study of the sorption of radionuclides by bacteria as the first step in the microorganism-metal interaction. The latter involves the fixation of ions on a surface layer and it results in the immobilization of the metal, thus possibly being the primary step of bioaccumulation. After a rapid presentation of the direct and indirect mechanisms of the interactions, we shall present our experiments of radionuclide biosorption by bacteria. A salient feature of biosorption is the selectivity of the adsorption of some radionuclides from a composed solution. For example, Andres et al. (1993, 1995) have shown that Mycobacterium smegmatis, from a composed solution containing uranium, thorium, lanthanum, europium and ytterbium, selectively adsorbs thorium ions. The sequence of preferential fixation is: Th 4+ > UO 2 2+ > La 3+ = Eu 3+ = Yb 3+ . This selectivity is a function of the cell wall organization and of the speciation of the metal in the solution. Yet, each species of bacteria has characteristic and specific cell wall layer composition and organization. Moreover, the culture and the environmental conditions change the surface layer properties. Another parameter in the migration of radionuclides is the transfer from the soil to the microorganisms. In column experiments, Gd, and likely the rare earths, in general, adsorbed on sand can be removed with a suspension of bacteria (Thouand and Andres 1997). These examples will be discussed and serve as a basis to illustrate the diversity of the interactions between microorganisms and radionuclides

  5. Inhalants

    Science.gov (United States)

    ... Alcohol Club Drugs Cocaine Fentanyl Hallucinogens Inhalants Heroin Marijuana MDMA (Ecstasy/Molly) Methamphetamine Opioids Over-the-Counter Medicines Prescription Medicines Steroids (Anabolic) Synthetic Cannabinoids (K2/Spice) Synthetic Cathinones (Bath Salts) Tobacco/ ...

  6. Proposed development of a radionuclide washoff model for the German Reactor Safety Study

    International Nuclear Information System (INIS)

    Helton, J.C.

    1982-11-01

    This report presents a brief overview of the possible development of a model for the attenuation of radionuclide concentrations in urban environments due to rainfall/runoff relationships. The following sequence of actions is suggested: (1) preliminary review, (2) exploratory modeling, (3) detailed literature review, (4) development of mathematical model, (5) development of computer model, and (6) model review including verification and sensitivity analysis. To facilitate the initiation of the indicated efforts, an introduction to the relevant literature is provided. Further, the following topics are also briefly discussed: (1) radionuclide transport and removal in the terrestrial environment, (2) need for a description of the chemical and physical forms of the radionuclides released in a reactor accident, and (3) potential importance of surface-water contamination. (orig./HP) [de

  7. Decontamination of spent ion-exchangers contaminated with cesium radionuclides using resorcinol-formaldehyde resins.

    Science.gov (United States)

    Palamarchuk, Marina; Egorin, Andrey; Tokar, Eduard; Tutov, Mikhail; Marinin, Dmitry; Avramenko, Valentin

    2017-01-05

    The origin of the emergence of radioactive contamination not removable in the process of acid-base regeneration of ion-exchange resins used in treatment of technological media and liquid radioactive waste streams has been determined. It has been shown that a majority of cesium radionuclides not removable by regeneration are bound to inorganic deposits on the surface and inside the ion-exchange resin beads. The nature of the above inorganic inclusions has been investigated by means of the methods of electron microscopy, IR spectrometry and X-ray diffraction. The method of decontamination of spent ion-exchange resins and zeolites contaminated with cesium radionuclides employing selective resorcinol-formaldehyde resins has been suggested. Good prospects of such an approach in deep decontamination of spent ion exchangers have been demonstrated. Copyright © 2016 Elsevier B.V. All rights reserved.

  8. Activity measurement of 33P and 32P radionuclide mixture

    International Nuclear Information System (INIS)

    Hanker, I.; Kansky, Z.

    1984-01-01

    The possibilities are briefly summed up of measuring mixtures of 33 P and 32 P with special regard to the method of simultaneous determination of both radionuclides in a liquid scintillator. This method was experimentally tested for special detection sensitivity and intended special applications in plant physiology and biochemistry using a dioxane scintillator (SLD-31, Spolana Neratovice, CSSR) and a Packard Tri-Carb 300 C, USA. The method gave erroneous results. The main cause of the errors in measurements of the 33 P and 32 P mixture in the SLD-31 was the adsorption of radionuclides on the inner wall of glass tubes. This phenomenon is not accompanied by changes in the quenching index. However, the effectiveness of measurement dropped and the relative contribution of the spectra of the two radionuclides changed with the time following sample preparation. The said effects were removed by adding 0.4% silicon dioxide (Cab-O-Sil M5, Serva) to the liquid scintillator. (author)

  9. A biokinetic model of inhaled Cm compounds in dogs: Application to human exposure data

    International Nuclear Information System (INIS)

    Guilmette, R.A.; Mewhinney, J.A.

    1989-01-01

    Curium isotopes are major by-products in irradiated nuclear reactor fuel and comprise a significant fraction of the alpha-emitting radionuclide inventory. Although little use is currently being made of purified Cm sources, such usage is possible if reprocessing of spent fuel becomes feasible. Because little information is available on the biokinetics and dosimetry of inhaled Cm compounds, a study was conducted in which adult beagle dogs received a single inhalation exposure to either a monodisperse aerosol of 244Cm2O3 (1.4 micron activity median aerodynamic diameter [AMAD]; sigma g = 1.16) or a polydisperse aerosol of 244Cm (NO3)3 (1.1 micron AMAD; sigma g = 1.74). At times ranging from 4 h to 2 y after exposure, animals were sacrificed and their tissues analyzed for Cm content. The data describing the uptake and retention of 244Cm in the different organs and tissues and the measured rates of excretion of these dogs formed the basis on which a biokinetic model of Cm metabolism was constructed. This Cm model was based on a previously published model of the biokinetics of 241Am that was shown to be applicable to data from human cases of inhalation exposure to 241Am aerosols. This Cm model was found to be adequate to describe the biological distribution of Cm in dogs and was also applied to the sparse data from humans. Reasonable agreement was found between the model predictions for lung retention of Cm and for urinary excretion patterns in humans

  10. Toxicity of 144Ce inhaled in a relatively insoluble form by Beagle dogs. XI

    International Nuclear Information System (INIS)

    Hahn, F.F.; Hanika-Rebar, C.; Boecker, B.B.; Mauderly, J.L.; McClellan, R.O.; Pickrell, J.A.

    1978-01-01

    The metabolism, dosimetry and effects of 144 Ce inhaled in fused aluminosilicate particles are being investigated in the Beagle dog to assess the biological consequences of release of 144 Ce in a relatively insoluble form such as might occur in certain types of nuclear accidents. The toxicity of inhaled 144 Ce is also of general interest since it is representative of intermediate-lived beta-emitting radionuclides. Two major studies with young adult dogs (12 to 14 months of age at exposure) are involved: (1) a metabolism and dosimetry study in which 24 dogs were serially sacrificed over an extended period of time, and (2) a longevity study with two series of dogs. Series I contains 15 dogs exposed to aerosols of 144 Ce in fused aluminosilicate particles to yield initial lung burdens of 11 to 210 μCi/kg body weight and three control dogs exposed to nonradioactive fused aluminosilicate particles. Series II contains 96 dogs exposed to aerosols of 144 Ce in fused aluminosilicate particles to yield initial lung burdens of 0.0024 to 66 μCi/kg body weight and 12 control dogs exposed to nonradioactive, fused aluminosilicate particles. To date, 51 dogs have died or were euthanized at 143 to 3280 days after inhalation of 144 Ce. The prominent findings were radiation pneumonitis in 17 dogs that died or were euthanized at 750 days or later. The cumulative radiation dose to the lung at time of death has ranged from 550 to 140,000 rads. Serial observations are continuing on the 60 survivors and 15 controls

  11. The variation of organ doses with the particle size and chemical form of an inhaled radioactive aerosol

    International Nuclear Information System (INIS)

    Hunt, B.W.; Adams, N.; Reissland, J.A.

    1979-04-01

    In this report, radiation doses to organs are calculated as a function of the particle size of the inhaled radioactive material. Aerosols with an Activity Median Aerodynamic Diameter (AMAD) from 0.1 μm to 20 μm are considered and doses accumulated by various organs in periods ranging from 1 day to 70 years are given for 65 radionuclides. A computer program is used which calculates the transformations taking place in each organ per curie of inhaled nuclide from the basic radioactivity and metabolic data. The program also calculates the resulting doses both for the organ in which the transformations occur and from penetrating radiation emitted as a result of transformations in other organs. The effects of particle size and chemical form of the nuclides on the doses received by organs are discussed. Tables of doses accumulated by 10 specific organs and other organs together with effective whole body doses are given for particle sizes 0.1 μm, 1 μm and 10 μm (AMAD). (author)

  12. Marine sediments as a sink, and contaminated sediments as a diffuse source of radionuclides

    International Nuclear Information System (INIS)

    Salbu, B.; Borretzen, P.

    1997-01-01

    Full text: Marine sediments may act as a sink for radionuclides originating from atmospheric fallout (e.g. Chernobyl accident), for radionuclides in discharges from nuclear installations (e.g. Sellafield, UK) for river transported radionuclides, and radionuclides released from nuclear waste dumped at sea (e.g. fjords at Novaya Zemlya). In order to assess short and long term consequences of radionuclides entering the marine ecosystem, the role of sediments as a relatively permanent sink and the potential for contaminated sediments to act as a diffuse source should be focused. The retention of radionuclides in sediments will depend on the source term, i.e. the physico-chemical forms of radionuclides entering the system and on interactions with various sediment components. Radionuclides associated with particles or aggregating polymers are removed from the water phase by sedimentation, while sorption to surface sediment layers is of relevance for ionic radionuclide species including negatively charged colloids. With time, transformation processes will influence the mobility of radionuclides in sediments. The diffusion into mineral lattices will increase fixation, while the influence of for instance red/ox conditions and bio-erosion may mobilize radionuclides originally fixed in radioactive particles. Thus, information of radionuclides species, surface interactions, transformation processes and kinetics is essential for reducing the uncertainties in marine transfer models. Dynamic model experiments where chemically well defined tracers are added to a sea water-marine sediment system are useful for providing information on time dependent interactions and distribution coefficients. When combined with sequential extraction techniques, information on mobility and rate of fixation is subsequently attained. In the present work experimental results from the Irish Sea and the Kara Sea will be discussed

  13. Uptake of Radionuclide Metals by SPME Fibers

    International Nuclear Information System (INIS)

    Duff, M; S Crump, S; Robert Ray, R; Keisha Martin, K; Donna Beals, D

    2006-08-01

    The Federal Bureau of Investigation (FBI) Laboratory currently does not have on site facilities for handling radioactive evidentiary materials and there are no established FBI methods or procedures for decontaminating high explosive (HE) and fire debris (FD) evidence while maintaining evidentiary value. One experimental method for the isolation of HE and FD residue involves using solid phase microextraction or SPME fibers to remove residue of interest. Due to their high affinity for organics, SPME fibers should have little affinity for most metals. However, no studies have measured the affinity of radionuclides for SPME fibers. The focus of this research was to examine the affinity of dissolved radionuclide ( 239/240 Pu, 238 U, 237 Np, 85 Sr, 133 Ba, 137 Cs, 60 Co and 226 Ra) and stable radionuclide surrogate metals (Sr, Co, Ir, Re, Ni, Ba, Cs, Nb, Zr, Ru, and Nd) for SPME fibers at the exposure conditions that favor the uptake of HE and FD residues. Our results from radiochemical and mass spectrometric analyses indicate these metals have little measurable affinity for these SPME fibers during conditions that are conducive to HE and FD residue uptake with subsequent analysis by liquid or gas phase chromatography with mass spectrometric detection

  14. Radionuclide and heavy metal biosorption by Pseudomonas biomass

    International Nuclear Information System (INIS)

    Sar, Pinaki; D'Souza, S.F.; Kazy, Sufia K.; Singh, S.P.

    2001-01-01

    Biosorptive metal (nickel and copper) and radionuclide (uranium) uptake capacity of two Pseudomonas strains was investigated in order to develop biotechnological strategies for toxic metals remediation. Lyophilized Pseudomonas biomass showed a very high uranium loading of 541 mg g -1 dry wt. Compared to this, the other bacterial strain of Pseudomonas aeruginosa used for nickel and copper removal yielded a maximum value of 265 mg g -1 and 137 mg g -1 respectively. Cation binding by both the biomass was fast saturating, pH -dependent process with optimum pH for U, Cu and Ni was pH 5.0, 7.0 and 8.0, respectively. In bimetallic combination, U sorption was inhibited only by Fe 3+ , Al 3+ and Cu 2+ suggesting a selective cation binding by the Pseudomonas biomass. In case of Ni and Cu, presence of Na, K or Ca increased the metal binding while Cd and Pb was antagonistic. Mineral acids could recover more than 75% (on average) of sorbed Ni or Cu. Noticeably, uranium and copper desorption was specifically high (88-90%) with sodium carbonate while calcium carbonate showed a good result for nickel. The overall data are in favour of deployment of the test biomass as efficient metal/radionuclide removal/recovery system. (author)

  15. Removal of radon by aeration testing of various aeration techniques for small water works. For European Commission under Contract No FI4PCT960054 TENAWA project

    CERN Document Server

    Salonen, L; Mehtonen, J; Mjoenes, L; Raff, O; Turunen, H

    2002-01-01

    Capability of various aeration techniques to remove radon from water in small waterworks was studied as a part of project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water), which was carried out during 1997-1999 on a cost-shared basis (contract No. F14PCT960054) with The European Commission (CEC) under the supervision of the Directorate-General XII Radiation Protection Research Unit. In TENAWA project both laboratory and field experiments were performed in order to find reliable methods and equipment for removing natural radionuclides from ground water originating either from private wells or small waterworks. Because such techniques are more often needed in private households than at waterworks, the main emphasis of the research was aimed to solve the water treatment problems related to the private water supplies, especially bedrock wells. Radon was the most important radionuclide to be removed from water at waterworks whereas the removal of other radionuclides ( sup 2 sup 3 sup 4...

  16. Naturally occurring radionuclides in drinking water before and after radon removal

    International Nuclear Information System (INIS)

    Swedjemark, G.A.; Linden, A.

    1998-06-01

    Radon removal can, with a good effect, be used to remove radon from well water. The short-lived radon progeny have been investigated in the raw and cleaned water from six private wells where radon removal based on aeration and recirculation of the water have been installed. The results from this pilot study indicate that the short-lived radon progeny in some cases follow the water to the tap for consumption to such an extent that the problem should be considered. The extent of the study is not sufficient for general conclusions. However, it is important to stress that the effective dose from the short-lived progeny is always lower than it would have been from the radon, when no radon is removed

  17. Respiratory tract carcinogenesis induced by radionuclides in the Syrian hamister

    International Nuclear Information System (INIS)

    Smith, D.M.; Thomas, R.G.; Anderson, E.C.

    1979-01-01

    Syrian hamsters were exposed to lung irradiation by various modalities that differed in degree of localization and the fraction of lung exposed. The animals were given alpha emitters under several exposure conditions: intratracheal (IT) instillation of 210 Po and 239 PuO 2 -ZrO 2 microspheres; inhalation (INH) of 238 239 PuO 2 -ZrO 2 particles; and/or intravenous (IV) injection of 238 239 PuO 2 -ZrO 2 microspheres. Beta-emitting 147 Pm was also administered; the radionuclide was incorporated into 10 μm diameter ZrO 2 microspheres and deposited in the lungs via the jugular vein. These microspheres lodge quantitatively in the pulmonary capillary bed for the duration of the animal's life span. Total IV Pu microsphere lung burdens have ranged from 0.14 nCi to 484 nCi and the number of spheres from 1500 to 880 000. Pu burdens from inhalation have ranged from 8 nCi to 101 nCi, IT Po burdens from 25 to 122 nCi, and Pm-laden microsphere burdens from 427 to 15 750 nCi. Intratracheal instillation of 210 Po solution gave nearly uniform alpha irradiation of the entire lung, intravenous injection of large numbers of ZrO 2 microspheres laden with 147 Pm gave whole lung exposures to low LET radiation, and IV injection of Pu-microspheres provided a gradation of focal alpha exposures. The Po and Pm exposures were highly tumorigenic, whereas the Pu microspheres produced tumors only when a large fraction of the lung was exposed to large radiation doses. However, Pu-ZrO 2 administered via inhalation was very carcinogenic and resulted in tumor incidences of 50% in some experiments. The IT instillation of Fe 2 O 3 following IV or IT Pu-ZrO 2 microsphere administration dramatically enhanced lung tumor induction

  18. Influence of inhaled Ca-DTPA on the long-term effects of inhaled Pu nitrate

    International Nuclear Information System (INIS)

    Ballou, J.E.; Dagle, G.E.; McDonald, K.E.; Buschbom, R.L.

    1975-01-01

    Inhaled Ca-DTPA administered to rats in 6 weekly, one-hour treatments of 3 mg/rat did not affect weight gain or life-span compared to Pu burdened animals (78 nCi ILB) or nontreated controls. In addition, the drug did not appear to promote the development of malignant lung tumors and bone tumors in Pu burdened rats although one rat exposed only to Ca-DTPA aerosols did develop a malignant lung tumor. This single lung tumor can not be considered significant although the normal incidence of this lesion is quite low. Inhaled Ca-DTPA therapy administered 20 days after Pu inhalation showed little effect in reducing the lung burden of plutonium. Skeletal deposition was decreased possibly because Ca-DTPA was administered during a time of active translocation of the inhaled Pu when Pu may have been available for chelation in the blood. Inhaled Ca-DTPA therapy did not appear to be beneficial in reducing the number of malignant lung tumors or bone tumors in plutonium burdened rats but on the other hand the chelate did not appear to promote these lesions. (U.S.)

  19. Propose of a model for dose and hazard calculation due the Rn-222, Rn-220 and its short half-life daugthers inhalation

    International Nuclear Information System (INIS)

    Mauricio, C.L.P.

    1982-01-01

    The compartimental dosimetric model is used to simulate, by computer, the interactions of the inhalated radon atom radiations and its short half-life daugthers with cells. The metabolic trajectory of these radionuclides is described by differential equations of continuous medium dynamics, where the elements transform by radioactive decay. This work permits to determine the individual retenction function, beeing useful in radioprotection routines or emergence situations. The results of internal dosimetry are consistent with the new I.C.R.P. - 32 international recommendations. (L.C.) [pt

  20. Inhalation of 210Po and 210Pb from cigarette smoking in Poland

    International Nuclear Information System (INIS)

    Skwarzec, B.; Ulatowski, J.; Struminska, D.I.; Borylo, A.

    2001-01-01

    The carcinogenic effect of 210 Po and 210 Pb with respect to lung cancer is an important problem in many countries with very high cigarette consumption. Poland has one of the highest consumptions of cigarettes in the world. The results of 210 Po determination on the 14 most frequently smoked brands of cigarettes which constitute over 70% of the total cigarette consumption in Poland are presented and discussed. Moreover, the polonium content in cigarette smoke was estimated on the basis of its activity in fresh tobaccos, ash, fresh filters and post-smoking filters. The annual effective doses were calculated on the basis of 210 Po and 210 Pb inhalation with the cigarette smoke. The results of this work indicate that Polish smokers who smoke one pack (20 cigarettes) per day inhale from 20 to 215 mBq of 210 Po and 210 Pb each. The mean values of the annual effective dose for smokers were estimated to be 35 and 70 μSv from 210 Po and 210 Pb, respectively. For persons who smoke two packs of cigarettes with higher radionuclide concentrations, the effective dose is much higher (471 μSv yr -1 ) in comparison with the intake in diet. Therefore, cigarettes and the absorption through the respiratory system are the main sources and the principal pathway of 210 Po and 210 Pb intake of smokers in Poland

  1. Sudden death caused by 1,1-difluoroethane inhalation.

    Science.gov (United States)

    Xiong, Zhenggang; Avella, Joseph; Wetli, Charles V

    2004-05-01

    A 20-year-old man was found dead on the floor next to a computer, with a nearly full can of "CRC Duster" dust remover located next to the deceased on the floor, and an empty can of the same product on the computer desk. Toxicologic evaluation using either gas chromatography/mass spectrometry (GC/MS) or gas chromatography/flame ionization detector (GC/FID) method identified the active ingredient 1,1-difluoroethane (Freon 152a) in all tissues analyzed. Tissue distribution studies revealed highest concentration in central blood, lung, and liver. It is believed that the 1,1-difluoroethane inhalation was the cause of death.

  2. Derived intervention levels for radionuclides in food

    International Nuclear Information System (INIS)

    1988-01-01

    After the nuclear accident at Chernobyl in 1986, many countries were affected by widespread radioactive contamination. It became clear that the available guidance on dealing with the consequences of a nuclear accident was inappropriate for the long term and for areas far removed from the accident site. A particular concern was the safety of radioactively contaminated food and drinking-water in the ''far field'' region. The present guidelines, based on health protection principles, have been prepared by the World Health Organization in response to this concern. For various food categories, recommendations are made on levels of contamination by radionuclides at which corrective action might be justified to reduce the health risk to the population. The guidelines are based on accepted radiation dose criteria, on food consumption data from different parts of the world, and on dosimetric information for the relevant radionuclides. They are intended to assist in national decision-making in the event of another major nuclear accident. Refs, 1 fig., 14 tabs

  3. Speciation analysis of radionuclides

    International Nuclear Information System (INIS)

    Salbu, B.

    2010-01-01

    Full text: Naturally occurring and artificially produced radionuclides in the environment can be present in different physico-chemical forms (i. e. radionuclide species) varying in size (nominal molecular mass), charge properties and valence, oxidation state, structure and morphology, density, complexing ability etc. Low molecular mass (LMM) species are believed to be mobile and potentially bioavailable, while high molecular mass (HMM) species such as colloids, polymers, pseudocolloids and particles are considered inert. Due to time dependent transformation processes such as mobilization of radionuclide species from solid phases or interactions of mobile and reactive radionuclide species with components in soils and sediments, however, the original distribution of radionuclides deposited in ecosystems will change over time and influence the ecosystem behaviour. To assess the environmental impact from radionuclide contamination, information on radionuclide species deposited, interactions within affected ecosystems and the time-dependent distribution of radionuclide species influencing mobility and biological uptake is essential. The development of speciation techniques to characterize radionuclide species in waters, soils and sediments should therefore be essential for improving the prediction power of impact and risk assessment models. The present paper reviews fractionation techniques which should be utilised for radionuclide speciation purposes. (author)

  4. Simulation of deposition and activity distribution of radionuclides in human airways

    International Nuclear Information System (INIS)

    Farkas, A.; Balashazy, I.; Szoke, I.; Hofmann, W.; Golser, R.

    2002-01-01

    The aim of our research activities is the modelling of the biological processes related to the development of lung cancer at the large central-airways observed in the case of uranium miners caused by the inhalation of radionuclides (especially alpha-emitting radon decay products). Statistical data show that at the uranium miners the lung cancer has developed mainly in the 3-4.-5. airway generations and especially in the right upper lobe. Therefore, it is rather important to study the physical and biological effects in this section of the human airways to find relations between the radiation dose and the adverse health effects. These results may provide useful information about the validity or invalidity of the currently used LNT (Linear-No-Threshold) dose-effect hypothesis at low doses

  5. Inhalation Injury: State of the Science 2016.

    Science.gov (United States)

    Foster, Kevin N; Holmes, James H

    This article summarizes research conducted over the last decade in the field of inhalation injury in thermally injured patients. This includes brief summaries of the findings of the 2006 State of the Science meeting with regard to inhalation injury, and of the subsequent 2007 Inhalation Injury Consensus Conference. The reviewed studies are categorized in to five general areas: diagnosis and grading; mechanical ventilation; systemic and inhalation therapy; mechanistic alterations; and outcomes.

  6. Precipitation scavenging of 7Be and 137Cs radionuclides in air

    International Nuclear Information System (INIS)

    Ioannidou, A.; Papastefanou, C.

    2006-01-01

    Atmospheric depositional fluxes of the naturally occurring 7 Be of cosmogenic origin and 137 Cs from fallout of the Chernobyl accident were measured over a 6-year period (January 1987-December 1992) at Thessaloniki, Greece (40 o 38'N, 22 o 58'E). Total precipitation accumulation during 1987-1992 varied between 33.7 cm and 65.2 cm, reflecting a relatively dry (precipitation-free) climate. The activity concentrations of 7 Be and 137 Cs in rainwater depended on the precipitation rate, being higher for low precipitation rates and lesser for high precipitation rates. 137 Cs was removed by rain and snow more efficiently than 7 Be. Snowfall was more efficient than rainfall in removing the radionuclides from the atmosphere. The annual bulk depositional fluxes of 7 Be varied between 477 and 1133 Bq m -2 y -1 and this variability was attributed to the amount of precipitation and the variations of the atmospheric concentrations of 7 Be. The annual bulk depositional fluxes of 137 Cs showed a significant decrease over time from 1987 to 1992, resulting in a removal half-life of 1.33 years. The presence of 137 Cs in air, and therefore in rainwater and snow, long after the Chernobyl accident (26 April 1986) was mainly due to the resuspension process. The normalized depositional fluxes of both radionuclides showed maximal values during the spring season where the maximum amount of precipitation occurred. The relatively high positive correlation between 7 Be and 137 Cs normalized depositional fluxes indicates that the scavenging process of local precipitation controlled the fluxes of both radionuclides. The dry depositional flux of 7 Be was less than 9.37% of total (wet and dry) depositional flux. The fraction of dry-to-total depositional flux of 137 Cs was much higher than that of 7 Be, due to the resuspended soil

  7. Quantitative radionuclide angiocardiography

    International Nuclear Information System (INIS)

    Scholz, P.M.; Rerych, S.K.; Moran, J.F.; Newman, G.E.; Douglas, J.M.; Sabiston, D.C. Jr.; Jones, R.H.

    1980-01-01

    This study introduces a new method for calculating actual left ventricular volumes and cardiac output from data recorded during a single transit of a radionuclide bolus through the heart, and describes in detail current radionuclide angiocardiography methodology. A group of 64 healthy adults with a wide age range were studied to define the normal range of hemodynamic parameters determined by the technique. Radionuclide angiocardiograms were performed in patients undergoing cardiac catherization to validate the measurements. In 33 patients studied by both techniques on the same day, a close correlation was documented for measurement of ejection fraction and end-diastolic volume. To validate the method of volumetric cardiac output calcuation, 33 simultaneous radionuclide and indocyanine green dye determinations of cardiac output were performed in 18 normal young adults. These independent comparisons of radionuclide measurements with two separate methods document that initial transit radionuclide angiocardiography accurately assesses left ventricular function

  8. Know How to Use Your Asthma Inhaler

    Medline Plus

    Full Text Available ... Controlling Tools for Control Triggers Indoors In the Workplace Outdoors Management Asthma Action Plan Flu Shots Inhalers ... inhaler with a spacer Your browser does not support iframes Using a metered dose inhaler with a ...

  9. MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) code description and User's Manual

    International Nuclear Information System (INIS)

    Avci, H.I.; Raghuram, S.; Baybutt, P.

    1985-04-01

    A new computer code called MATADOR (Methods for the Analysis of Transport And Deposition Of Radionuclides) has been developed to replace the CORRAL-2 computer code which was written for the Reactor Safety Study (WASH-1400). This report is a User's Manual for MATADOR. MATADOR is intended for use in system risk studies to analyze radionuclide transport and deposition in reactor containments. The principal output of the code is information on the timing and magnitude of radionuclide releases to the environment as a result of severely degraded core accidents. MATADOR considers the transport of radionuclides through the containment and their removal by natural deposition and by engineered safety systems such as sprays. It is capable of analyzing the behavior of radionuclides existing either as vapors or aerosols in the containment. The code requires input data on the source terms into the containment, the geometry of the containment, and thermal-hydraulic conditions in the containment

  10. Radionuclide concentrations in ground-level air from 1984 to mid 1986 in North Germany and North Norway; influence of the Chernobyl accident

    International Nuclear Information System (INIS)

    Kolb, W.

    1986-09-01

    The activity concentration of various fission products and some other radionuclides (e.g. Be-7, Na-22, K-40 and Pb-210) contained in surface air were determined by gamma-ray spectroscopy. The mean monthly activity concentrations of up to 30 radionuclides measured from 1984 to mid 1986 in Brunswick, Berlin and Skibotn (North Norway) are tabulated. Early in 1984 the ground level air at all three stations still contained some fission and activation products resulting from the latest nuclear test carried out at a high altitude by the People's Republic of China. By the end of 1984 only Cs-137 was still detectable with activity concentrations of less than 1 μBq/m 3 . The occasional appearance of some activation products in 1984 and 1985 is commented on and compared with similar findings of several Scandinavian institutes. Fresh fission products from the Chernobyl accident arrived in late April 1986 in Brunswick, Berlin and Skibotn. The mean Cs-137 concentration in May estimated for Brunswick was 28 mBq/m 3 (i.e. 15 times higher than the hitherto recorded maximum in June 1964). It had decreased by July 1986 down to 0.13 mBq/m 3 . The effective dose equivalent due to inhalation of fission products is estimated for all three sites and compared with the Pb-210 inhalation dose. (orig.) [de

  11. Toxicological perspectives of inhaled therapeutics and nanoparticles.

    Science.gov (United States)

    Hayes, Amanda J; Bakand, Shahnaz

    2014-07-01

    The human respiratory system is an important route for the entry of inhaled therapeutics into the body to treat diseases. Inhaled materials may consist of gases, vapours, aerosols and particulates. In all cases, assessing the toxicological effect of inhaled therapeutics has many challenges. This article provides an overview of in vivo and in vitro models for testing the toxicity of inhaled therapeutics and nanoparticles implemented in drug delivery. Traditionally, inhalation toxicity has been performed on test animals to identify the median lethal concentration of airborne materials. Later maximum tolerable concentration denoted by LC0 has been introduced as a more ethically acceptable end point. More recently, in vitro methods have been developed, allowing the direct exposure of airborne material to cultured human target cells on permeable porous membranes at the air-liquid interface. Modifications of current inhalation therapies, new pulmonary medications for respiratory diseases and implementation of the respiratory tract for systemic drug delivery are providing new challenges when conducting well-designed inhalation toxicology studies. In particular, the area of nanoparticles and nanocarriers is of critical toxicological concern. There is a need to develop toxicological test models, which characterise the toxic response and cellular interaction between inhaled particles and the respiratory system.

  12. Radioactive gas inhalator

    International Nuclear Information System (INIS)

    LeMon, D.E.

    1975-01-01

    An ''inhalator'', or more particularly an apparatus for permitting a patient to inhale a radioactive gas in order to provide a diagnostic test of the patient's lung area, is described. The disclosed apparatus provides a simple, trouble-free mechanism for achieving this result; and, furthermore, provides an improved testing method. Moreover, the disclosed apparatus has the capability of gradually introducing the test condition in a manner that makes it easy for the patient to become acclimated to it. (U.S.)

  13. Estimates of internal dose equivalent to 22 target organs for radionuclides occurring in routine releases from nuclear fuel-cycle facilities. Vol. 1

    International Nuclear Information System (INIS)

    Killough, G.G.; Dunning, D.E. Jr.; Bernard, S.R.; Pleasant, J.C.

    1978-01-01

    This report is the first of a two-volume tabulation of internal radiation dose conversion factors for man for radionuclides of interest in environmental assessments of light-water-reactor fuel cycles. This volume treats 68 radionuclides, all of mass number less than 150. Intake by inhalation and ingestion is considered. In the former case, the ICRP Task Group Lung Model has been used to simulate the behavior of particulate matter in the respiratory tract. Results corresponding to activity median aerodynamic diameters (AMAD) of 0.3, 1.0, and 5.0 μm are given. The GI tract has been represented by a four-segment catenary model with exponential transfer of radioactivity from one segment to the next. Retention of radionuclides in other organs was characterized by linear combinations of decaying exponential functions. Dose equivalent per microcurie intake of each parent nuclide is given for 22 target organs with contributions from specified source organs plus surplus activity in the rest of the body. Cross irradiation due to penetrating radiations has also been considered in the calculations

  14. Know How to Use Your Asthma Inhaler

    Medline Plus

    Full Text Available ... metered dose inhaler with a spacer [ PDF – 377 KB] Your browser does not support iframes Cómo usar ... inhalador de dosis fija con espaciador [PDF – 343 KB] Using a metered dose inhaler (inhaler in mouth) ...

  15. Inhaled plutonium nitrate in dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Cannon, W.C.; Ragan, H.A.; Watson, C.R.; Stevens, D.L.; Cross, F.T.; Dionne, P.J.; Harrington, T.P.

    1978-01-01

    Beagle dogs given a single inhalation exposure to 239 Pu(NO 3 ) 4 are being observed for life-span dose-effect relationships. Lymphopenia occurred at the two highest dosage levels as early as 1 mo following exposure and was associated with neutropenia and reduction in numbers of circulatory monocytes by 4 mo postexposure. Radiation pneumonitis developed in one dog at the highest dosage level at 14 mo postexposure. More rapid translocation to skeleton and liver occurred following inhalation of 238 Pu(NO 3 ) 4 than after 239 Pu(NO 3 ) 4 inhalation

  16. Teaching inhaler use in chronic obstructive pulmonary disease patients.

    Science.gov (United States)

    Lareau, Suzanne C; Hodder, Richard

    2012-02-01

    To review barriers to the successful use of inhalers in patients with chronic obstructive pulmonary disease (COPD), and the role of the nurse practitioner (NP) in facilitating optimum inhaler use. Review of the national and international scientific literature. Pharmacologic treatment of COPD patients comprises mainly inhaled medications. Incorrect use of inhalers is very common in these individuals. Some of the consequences of poor inhaler technique include reduced therapeutic dosing, medication adherence, and disease stability, which can lead to increased morbidity, decreased quality of life, and a high burden on the healthcare system. Knowledgeable evaluation and frequent reassessment of inhaler use coupled with education of patients, caregivers, and healthcare professionals can significantly improve the benefits COPD patients derive from inhaled therapy. Patient education is vital for correct use of inhalers and to ensure the effectiveness of inhaled medications. The NP has a critical role in assessing potential barriers to successful learning by the patient and improving inhaler technique and medication management. The NP can also facilitate success with inhaled medications by providing up-to-date inhaler education for other healthcare team members, who may then act as patient educators. ©2011 The Author(s) Journal compilation ©2011 American Academy of Nurse Practitioners.

  17. Calculated radiation doses from radionuclides brought to the surface if future drilling intercepts the WIPP repository and pressurized brine

    International Nuclear Information System (INIS)

    Channell, J.K.

    1982-01-01

    This report describes a scenario in which an exploratory borehole connects an underlying brine reservoir with the repository and results in saturation of the waste storage area. A subsequent borehole brings portions of this radionuclide contaminated brine to the surface. Radiation odses are calculated for time periods of 125, 400, and 1000 years after repository closing for the following: (1) external radiation doses for workers at the borehole location; (2) inhalation doses for workers at the borehole location; (3) external and inhalation doses for a resident located 360 meters downwind; (4) ingestion doses for the downwind resident from locally grown produce, milk, and meat; and (5) population doses from inhalation within a 50-mile radius. The probability of the various calculated doses occurring was estimated. Probability was included in the report because of a belief that probability considerations are useful in evaluating the acceptability of unlikely events and to encourage others to provide a more detailed evaluation using more sophisticated methodology. Since the probabilities presented in this report were calculated using a simple methodology, with some parameter values chosen arbitrarily, they should be considered as approximate examples, not accurate numbers. The reasonableness of the scenario and the significance of the results are also discussed

  18. Factors that elevate the internal radionuclide and chemical retention, dose and health risks to infants and children in a radiological-nuclear emergency

    International Nuclear Information System (INIS)

    Richardson, R. B.

    2009-01-01

    The factors that influence the dose and risk to vulnerable population groups from exposure and internal uptake of chemicals are examined and, in particular, the radionuclides released in chemical, biological, radiological, nuclear and explosive events. The paper seeks to identify the areas that would benefit from further research. The intake and body burdens of carbon and calcium were assessed as surrogates for contaminants that either act like or bind to hydrocarbons (e.g. tritium and 14 C) or bone-seeking radionuclides (e.g. 90 Sr and 239 Pu). The shortest turnover times for such materials in the whole body were evaluated for the newborn: 11 d and 0.5 y for carbon and calcium, respectively. However, their biokinetic behaviour is complicated by a particularly high percentage of the gut-absorbed dietary intake of carbon (∼16%) and calcium (∼100%) that is incorporated into the soft tissue and skeleton of the growing neonate. The International Commission on Radiological Protection dose coefficients (Sv Bq -1 ) were examined for 14 radionuclides, including 9 of concern because of their potential use in radiological dispersal devices. The dose coefficients for a 3-month-old are greater than those for adults (2-56 times more for ingestion and 2-12 times for inhalation). The age-dependent dose and exposure assessment of contaminant intakes would improve by accounting for gender and growth where it is currently neglected. Health risk is evaluated as the product of the exposure and hazard factors, the latter being about 10-fold greater in infants than in adults. The exposure factor is also approximately 10-fold higher for ingestion by infants than by adults, and unity for inhalation varying with the contaminant. Qualitative and quantitative physiological and epidemiological evidence supports infants being more vulnerable to cancer and neurological deficit than older children). (authors)

  19. Use of nitrite inhalants ("poppers") among American youth.

    Science.gov (United States)

    Wu, Li-Tzy; Schlenger, William E; Ringwalt, Chris L

    2005-07-01

    We examined the patterns and correlates of nitrite inhalant use among adolescents aged 12 to 17 years. Study data were drawn from the 2000 and 2001 National Household Surveys on Drug Abuse. Logistic regression was used to identify the characteristics associated with nitrite inhalant use. Among adolescents aged 12 to 17 years, 1.5% reported any lifetime use of nitrite inhalants. The prevalence of lifetime nitrite inhalant use increased to 12% and 14% among adolescents who were dependent on alcohol and any drug in the past year, respectively. Many nitrite inhalant users used at least three other types of inhalants (68%) and also met the criteria for alcohol (33%) and drug (35%) abuse or dependence. Increased odds of nitrite inhalant use were associated with residing in nonmetropolitan areas, recent utilization of mental health services, delinquent behaviors, past year alcohol and drug abuse and dependence, and multi-drug use. Adolescents who had used nitrite inhalants at least once in their lifetime tend to engage in delinquent activities and report co-occurring multiple drug abuse and mental health problems in the past year.

  20. Age dependent systemic exposure to inhaled salbutamol

    DEFF Research Database (Denmark)

    Bønnelykke, Klaus; Jespersen, Jakob Jessing; Bisgaard, Hans

    2007-01-01

    AIMS: To determine the effect of age on systemic exposure to inhaled salbutamol in children. METHODS: Fifty-eight asthmatic children, aged 3-16 years, inhaled 400 microg of salbutamol from a pressurized metered dose inhaler with spacer. The 20 min serum profile was analyzed. RESULTS: Prescribing...

  1. Atmospheric radionuclides from Fukushima Dai-ichi nuclear accident detected in Lanzhou, China

    Institute of Scientific and Technical Information of China (English)

    邬家龙王赟; 孙卫; 罗伟立; 王延俊; 张飙

    2015-01-01

    After the Fukushima Dai-ichi nuclear power plant accident on March 11, 2011, the radioactivity released from the accident was transported around the globe by atmospheric processes. The radioactivity monitoring program on atmospheric particulate in Lanzhou, China was activated by GSCDC to detect the input radionu-clides through atmospheric transport. Several artificial radionuclides were detected and measured in aerosol samples from March 26 to May 2, 2011. The peaked activity concentrations (in mBq/m3) were: 1.194 (131I), 0.231 (137Cs), 0.173 (134Cs) and 0.008 (136Cs), detected on April 6, 2011. The average activity ratio of 131I/137Cs and 134Cs/137Cs in air were 13.5 and 0.78. The significant increase of 137Cs activity concentration, one order of magnitude higher than pre-Fukushima accident levels, in ground level aerosol was observed in 2013, as its re-suspension from soil. The back-trajectory analysis simulated by NOAA-ARL HYSPLIT shows a direct transfer of the air masses released from Fukushima to Lanzhou across the Pacific Ocean, North America and Europe at the height close to 9000 m AGL. The value of effective dose for inhalation is close to one millionth of the annual limit for the general public.

  2. Radiation exposure parameters resulting from the radionuclides in soil collected from Manavalakurichi

    International Nuclear Information System (INIS)

    Jose, Reeba Maria; Ben Byju, S.; Arunima, S.; Jojo, P.J.

    2014-01-01

    Naturally occurring radioactive materials (NORMS) are and have always been a part of our environment. Exposure to ionizing radiation film natural sources is a continuous and unavoidable feature of life on earth. Human beings are exposed outdoors to the natural terrestrial radiation that originates predominantly from the upper 30 cm of the soil. Only radionuclides with half-lives comparable with the age of the earth or their corresponding decay products existing in terrestrial material such as 232 Th, 238 U and 40 K are of great interest. The radiological implication of these radionuclides is due to the gamma ray exposure of the body and irradiation of lung tissue from inhalation of radon and its daughters. Therefore the assessment of gamma radiation dose from natural source is of particular importance as natural radiation is the largest contributor to the external dose of the world population. The natural environmental radioactivity and the external exposure due to gamma radiation depend primarily on the geology and geographical condition and appear at different levels in the soils of each region in the world. A systematic radiological survey has been carried out in the region of high level natural radioactive area in South West India to assess the natural gamma radiation level

  3. Effect of novel inhaler technique reminder labels on the retention of inhaler technique skills in asthma: a single-blind randomized controlled trial.

    Science.gov (United States)

    Basheti, Iman A; Obeidat, Nathir M; Reddel, Helen K

    2017-02-09

    Inhaler technique can be corrected with training, but skills drop off quickly without repeated training. The aim of our study was to explore the effect of novel inhaler technique labels on the retention of correct inhaler technique. In this single-blind randomized parallel-group active-controlled study, clinical pharmacists enrolled asthma patients using controller medication by Accuhaler [Diskus] or Turbuhaler. Inhaler technique was assessed using published checklists (score 0-9). Symptom control was assessed by asthma control test. Patients were randomized into active (ACCa; THa) and control (ACCc; THc) groups. All patients received a "Show-and-Tell" inhaler technique counseling service. Active patients also received inhaler labels highlighting their initial errors. Baseline data were available for 95 patients, 68% females, mean age 44.9 (SD 15.2) years. Mean inhaler scores were ACCa:5.3 ± 1.0; THa:4.7 ± 0.9, ACCc:5.5 ± 1.1; THc:4.2 ± 1.0. Asthma was poorly controlled (mean ACT scores ACCa:13.9 ± 4.3; THa:12.1 ± 3.9; ACCc:12.7 ± 3.3; THc:14.3 ± 3.7). After training, all patients had correct technique (score 9/9). After 3 months, there was significantly less decline in inhaler technique scores for active than control groups (mean difference: Accuhaler -1.04 (95% confidence interval -1.92, -0.16, P = 0.022); Turbuhaler -1.61 (-2.63, -0.59, P = 0.003). Symptom control improved significantly, with no significant difference between active and control patients, but active patients used less reliever medication (active 2.19 (SD 1.78) vs. control 3.42 (1.83) puffs/day, P = 0.002). After inhaler training, novel inhaler technique labels improve retention of correct inhaler technique skills with dry powder inhalers. Inhaler technique labels represent a simple, scalable intervention that has the potential to extend the benefit of inhaler training on asthma outcomes. REMINDER LABELS IMPROVE INHALER TECHNIQUE: Personalized

  4. Radionuclide fixation mechanisms in rocks

    International Nuclear Information System (INIS)

    Nakashima, S.

    1991-01-01

    In the safety evaluation of the radioactive waste disposal in geological environment, the mass balance equation for radionuclide migration is given. The sorption of radionuclides by geological formations is conventionally represented by the retardation of the radionuclides as compared with water movement. In order to quantify the sorption of radionuclides by rocks and sediments, the distribution ratio is used. In order to study quantitatively the long term behavior of waste radionuclides in geological environment, besides the distribution ratio concept in short term, slower radionuclide retention reaction involving mineral transformation should be considered. The development of microspectroscopic method for long term reaction path modeling, the behavior of iron during granite and water interaction, the reduction precipitation of radionuclides, radionuclide migration pathways, and the representative scheme of radionuclide migration and fixation in rocks are discussed. (K.I.)

  5. Effects on elevating cancer risk in population exposed to natural radionuclide 226Ra if parent radionuclide 238U is entered the body by inhalation or ingestion

    International Nuclear Information System (INIS)

    Zupunski, Lj.; Trobok, M.; Gordanic, V.; Spasic-Jokic, V.; Sovilj, P.

    2009-01-01

    People have always been exposed to ionizing radiation originating from natural radionuclides including 238 U, 40 K, 232 Th that exist in earths crust. Although received doses are small, due to the fact that threshold does not exist, there is a certain risk of developing cancer. Purpose of this study was to measure 238 U concentrations in soil of Bela Crkva territory. Based on these measurements, risks of developing cancers are calculated using Monte Carlo method.(author) [sr

  6. Hot Spot Removal System: System description

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-09-01

    Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System`s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section.

  7. Hot Spot Removal System: System description

    International Nuclear Information System (INIS)

    1997-09-01

    Hazardous wastes contaminated with radionuclides, chemicals, and explosives exist across the Department of Energy complex and need to be remediated due to environmental concerns. Currently, an opportunity is being developed to dramatically reduce remediation costs and to assist in the acceleration of schedules associated with these wastes by deploying a Hot Spot Removal System. Removing the hot spot from the waste site will remove risk driver(s) and enable another, more cost effective process/option/remedial alternative (i.e., capping) to be applied to the remainder of the site. The Hot Spot Removal System consists of a suite of technologies that will be utilized to locate and remove source terms. Components of the system can also be used in a variety of other cleanup activities. This Hot Spot Removal System Description document presents technologies that were considered for possible inclusion in the Hot Spot Removal System, technologies made available to the Hot Spot Removal System, industrial interest in the Hot Spot Removal System''s subsystems, the schedule required for the Hot Spot Removal System, the evaluation of the relevant technologies, and the recommendations for equipment and technologies as stated in the Plan section

  8. Filters for water purification from radionuclides

    International Nuclear Information System (INIS)

    Mironov, V.V.; Khaydarov, R.R.; Khaydarov, R.A.; Gapurova, O.U.

    2006-01-01

    Full text: At present purification of waste water and drinking water from radionuclides, heavy metal ions, and organic contaminants is one of the most important problems. One of widely used methods for solving this problem is the ion exchange method based on using of different types of resins and fibroid sorbents. This paper deals with new chemically modified polyester fibroid filters having satisfactory adsorption characteristics. The process of the filter production includes their treatment by acrylonitrilic emulsion for improving mechanical characteristics. An advantage of the fibroid ion-exchange sorbents over resin is in their high sorption rate, effective regeneration and small value of pressure drop of the sorbent layer for purified water. The specific surface of the fibroid sorbents is (2 - 3). 10 4 m 2 / kg, i.e. about 10 2 times greater than that of the resin (10 2 m 2 / kg). Owing to that fact the rate of the sorption process on the developed fibroid sorbents is much greater than that on the resin. The developed cation- and anion-exchange filters can be used for removing metal ions (Zn, Ni, Cu, Sb, Co, Cd, Cr, etc.) and organic compounds (M- 32 P, M- 131 I, M- 99 Mo+ 99m Tc, etc.) from water. Capacity of the cation-exchange sorbents is 0.25 meq/g (Cu 2+ ) and that of the anion - exchange is 0.45 meq/g (Cr 6+ ). The cation- and anion-exchange filters are also selective for removing radionuclides 134 , 137 Cs, 90 Sr, 60 Co and 129 I in presence of Na + , K + , Ca 2+ , Mg 2+ , Cl - ions in water at concentrations up to 500 mg/L. New developed ion-exchange sorbents have been used in drinking water filters and mini-systems for removing organic and inorganic contaminants, in the equipment for waste water purification from oil products (at atomic power stations, car-washing stations, etc), from heavy metal ions (in electronic industry, match fabrics, leather processing plants etc). (author)

  9. Radon removal from different types of groundwater applying granular activated carbon filtration

    International Nuclear Information System (INIS)

    Turtiainen, T.; Salonen, L.; Myllymaeki, P.

    2000-01-01

    Granular activated carbon (CAC) filters were installed in 12 private homes or vacation homes for removing unacceptably high concentrations of radon from household water. Radon removal efficiency was nearly 100% in most locations, although different water types were encountered. Other radionuclides such as uranium, radium, lead and polonium were removed less efficiently. Treated water quality remained good and no significant external radiation dose was caused to the residents. (author)

  10. E-cigarette versus nicotine inhaler: comparing the perceptions and experiences of inhaled nicotine devices.

    Science.gov (United States)

    Steinberg, Michael B; Zimmermann, Mia Hanos; Delnevo, Cristine D; Lewis, M Jane; Shukla, Parth; Coups, Elliot J; Foulds, Jonathan

    2014-11-01

    Novel nicotine delivery products, such as electronic cigarettes (e-cigarettes), have dramatically grown in popularity despite limited data on safety and benefit. In contrast, the similar U.S. Food and Drug Administration (FDA)-approved nicotine inhaler is rarely utilized by smokers. Understanding this paradox could be helpful to determine the potential for e-cigarettes as an alternative to tobacco smoking. To compare the e-cigarette with the nicotine inhaler in terms of perceived benefits, harms, appeal, and role in assisting with smoking cessation. A cross-over trial was conducted from 2012 to 2013 PARTICIPANTS/INTERVENTIONS: Forty-one current smokers age 18 and older used the e-cigarette and nicotine inhaler each for 3 days, in random order, with a washout period in between. Thirty-eight participants provided data on product use, perceptions, and experiences. The Modified Cigarette Evaluation Questionnaire (mCEQ) measured satisfaction, reward, and aversion. Subjects were also asked about each product's helpfulness, similarity to cigarettes, acceptability, image, and effectiveness in quitting smoking. Cigarette use was also recorded during the product-use periods. The e-cigarette had a higher total satisfaction score (13.9 vs. 6.8 [p e-cigarette received higher ratings for helpfulness, acceptability, and "coolness." More subjects would use the e-cigarette to make a quit attempt (76 %) than the inhaler (24 %) (p e-cigarette vs. 10 % (4/38) using the inhaler (p = 0.18). The e-cigarette was more acceptable, provided more satisfaction, and had higher perceived benefit than the inhaler during this trial. E-cigarettes have the potential to be important nicotine delivery products owing to their high acceptance and perceived benefit, but more data are needed to evaluate their actual efficacy and safety. Providers should be aware of these issues, as patients will increasingly inquire about them.

  11. Suffocation caused by plastic wrap covering the face combined with nitrous oxide inhalation

    DEFF Research Database (Denmark)

    Leth, Peter Mygind; Astrup, Birgitte Schmidt

    2017-01-01

    Suicide using a combination of a plastic bag over the head and inhalation of a non-irritating gas, such as helium, argon or nitrogen, has been reported in the literature. Here an unusual suicide method in a 17-year old man by suffocation from covering the face with household plastic wrap, combined....... The deceased was a 17-year old man who was found with the nose and mouth closed with a piece of kitchen plastic wrap. The plastic wrap had been removed prior to autopsy. Autopsy findings were suggestive of asphyxia, but were otherwise negative. Nitrous oxide was detected in the brain and lung tissue...... with headspace-gas chromatography-mass spectrometry (headspace-GCMS). The cause of death was assumed to be suffocation caused by plastic wrap covering the face, combined with nitrous oxide inhalation. Suicide was suspected because of a history of depression for several months. Nitrous oxide, also known...

  12. The sources and fate of radionuclides emitted to the atmosphere

    International Nuclear Information System (INIS)

    Sandalls, J.

    2001-01-01

    The thesis represents an account of the sources and fate of radionuclides entering the atmosphere, and indicates where the candidate, through his own work, has contributed to the overall picture. The sources of the natural and man-made radionuclides found in the atmosphere are identified. New data on emissions from UK coal-fired power stations and UK steel works are reported. Radionuclides produced in nuclear fission and released to the atmosphere in the detonation of nuclear weapons, in nuclear accidents, and through routine discharges from nuclear sites have added to the atmospheric burden of radioactive materials; both acute and chronic low-level emissions are discussed. The various natural processes which remove radionuclides from the atmosphere are described. Soon after release, many radioactive materials become attached to the atmospheric aerosol, but others undergo gas-phase reactions. Some gases are sufficiently long-lived in the troposphere as to find their way into the stratosphere where their fate may be determined by the short-wave radiation from the sun. The nature of the particles of fuel emitted to the atmosphere in the explosion and fire at the Chernobyl nuclear power plant in 1986 are discussed, together with the associated environmental problems. The ground is the major sink for radionuclides leaving the atmosphere, and the behaviour of the more radiologically important radionuclides following deposition is described with special reference to: (i) fallout in both the urban and living environments; (ii) the pathways which may lead to contamination of the food chain; (iii) how the fuel particle fallout from Chernobyl was unique in nuclear accidents; (iv) soil-to-plant transfer of radioelements and (v) how radiation exposure of man can be mitigated in both the contaminated urban and rural environments. (author)

  13. Inhaled medication and inhalation devices for lung disease in patients with cystic fibrosis: A European consensus

    DEFF Research Database (Denmark)

    Heijerman, Harry; Westerman, Elsbeth; Conway, Steven

    2009-01-01

    , mucolytics/mucous mobilizers, anti-inflammatory drugs, bronchodilators and combinations of solutions. Additionally, we review the current knowledge on devices for inhalation therapy with regard to optimal particle sizes and characteristics of wet nebulisers, dry powder and metered dose inhalers. Finally, we...... review the current status of inhaled medication in CF, including the mechanisms of action of the various drugs, their modes of administration and indications, their effects on lung function, exacerbation rates, survival and quality of life, as well as side effects. Specifically we address antibiotics...

  14. Airborne radionuclides in the proglacial environment as indicators of sources and transfers of soil material.

    Science.gov (United States)

    Łokas, Edyta; Wachniew, Przemysław; Jodłowski, Paweł; Gąsiorek, Michał

    2017-11-01

    A survey of artificial ( 137 Cs, 238 Pu, 239+240 Pu, 241 Am) and natural ( 226 Ra, 232 Th, 40 K, 210 Pb) radioactive isotopes in proglacial soils of an Arctic glacier have revealed high spatial variability of activity concentrations and inventories of the airborne radionuclides. Soil column 137 Cs inventories range from below the detection limit to nearly 120 kBq m -2 , this value significantly exceeding direct atmospheric deposition. This variability may result from the mixing of materials characterised by different contents of airborne radionuclides. The highest activity concentrations observed in the proglacial soils may result from the deposition of cryoconites, which have been shown to accumulate airborne radionuclides on the surface of glaciers. The role of cryoconites in radionuclide accumulation is supported by the concordant enrichment of the naturally occurring airborne 210 Pb in proglacial soil cores showing elevated levels of artificial radionuclides. The lithogenic radionuclides show less variability than the airborne radionuclides because their activity concentrations are controlled only by the mixing of material derived from the weathering of different parent rocks. Soil properties vary little within and between the profiles and there is no unequivocal relationship between them and the radionuclide contents. The inventories reflect the pathways and time variable inputs of soil material to particular sites of the proglacial zone. Lack of the airborne radionuclides reflects no deposition of material exposed to the atmosphere after the 1950s or its removal by erosion. Inventories above the direct atmospheric deposition indicate secondary deposition of radionuclide-bearing material. Very high inventories indicate sites where transport pathways of cryoconite material terminated. Copyright © 2017 Elsevier Ltd. All rights reserved.

  15. Separation of protactinum, actinium, and other radionuclides from proton irradiated thorium target

    Science.gov (United States)

    Fassbender, Michael E.; Radchenko, Valery

    2018-04-24

    Protactinium, actinium, radium, radiolanthanides and other radionuclide fission products were separated and recovered from a proton-irradiated thorium target. The target was dissolved in concentrated HCl, which formed anionic complexes of protactinium but not with thorium, actinium, radium, or radiolanthanides. Protactinium was separated from soluble thorium by loading a concentrated HCl solution of the target onto a column of strongly basic anion exchanger resin and eluting with concentrated HCl. Actinium, radium and radiolanthanides elute with thorium. The protactinium that is retained on the column, along with other radionuclides, is eluted may subsequently treated to remove radionuclide impurities to afford a fraction of substantially pure protactinium. The eluate with the soluble thorium, actinium, radium and radiolanthanides may be subjected to treatment with citric acid to form anionic thorium, loaded onto a cationic exchanger resin, and eluted. Actinium, radium and radiolanthanides that are retained can be subjected to extraction chromatography to separate the actinium from the radium and from the radio lanthanides.

  16. Inhalants

    Science.gov (United States)

    ... uses inhalants may be unable to learn new things or may have a hard time carrying on simple conversations. If the cerebral ... get drugs on the street, it is really hard to know what you get, Sometimes, ... put in, all sorts of things could happen. And other times, one might get ...

  17. Public Health Goal for Naturally Occurring Radionuclides in Groundwater

    International Nuclear Information System (INIS)

    Kamel, N.H.M.; Omar, H.A.; El-Baset, L.A.

    2008-01-01

    Naturally occurring and man-made radionuclide in groundwater may have a health hazardous to some residents. The objective of this work is to provide criteria for safety of drinking-water with respect to the chemical parameters and the radionuclide content. The annual effective dose for the consumption of drinking water was considered. Ground water samples were selected from different sites in Egypt, that have the most population, it were taken from aquifer regions along Giza sites in Egypt. Chemical analyses for the major anions, cations, and the radiological analyses were tested . Activity concentrations (Bq/l) of the gross alpha and the gross beta activities of our investigated samples were compared with the maximum contaminant level (MCL) of the world health organization (WHO). Some of the water samples were found to have a higher of gross beta and alpha particles than the MCL. Alpha activity were found depending on to the total dissolved solids (TDS) content of the water samples. Gamma activity concentrations were analyzed using low background germanium detector, the higher of activity values was found in some investigated samples is due to increasing of 226 Ra and 228 Ra activities. Tritium activity concentrations also were measured using soft beta liquid scintillation counter, it was found lower than the MCL. Our investigated samples were found to have a higher concentrations of the phosphate, nitrites, iron, and manganese contents than the maximum permissible limit, all the ground water samples were found to have a higher of silica and alumina content. Commercial carbon powder and natural clay materials were tested as ion exchangers for the removal of inorganic contaminants in the ground water samples. Clay materials was found to have a higher selectivity than activated carbon for the removal of radionuclides, phosphates, nitrites, and manganese content at the ground water samples

  18. Inhaled actinides: some safety issues and some research problems

    International Nuclear Information System (INIS)

    Bair, W.J.

    1978-01-01

    The following topics are discussed: limited research funds; risk coefficients for inhaled particles; the hot particle hypothesis; the Gofman-Martell contention; critical tissues for inhaled actinides inhalation hazards associated with future nuclear fuel cycles; and approach to be used by the inhalation panel

  19. Behavior of radionuclides in sanitary landfills.

    Science.gov (United States)

    Chang, K C; Chian, E S; Pohland, F G; Cross, W H; Roland, L; Kahn, B

    1984-01-01

    his study was undertaken to evaluate the possibility of disposing low-level radioactive waste in sanitary landfills with leachate containment to prevent environmental releases. To meet this objective, two simulated landfills, each 200 l. in volume and containing 55 kg of municipal refuse, were operated in the laboratory with simulated rainfall additions for a 9-month period to observe the extent to which radio-cobalt, -cesium, -strontium and tritium were leached into the liquid phase. One of the units was operated with leachate recycle, the other as a single pass control. Liquid samples were analyzed weekly for 3H, 58Co, 85Sr and 134Cs tracers. Weekly analyses were also performed for approximately 30 parameters to define the degree of stabilization of the waste. Major parameters included BOD, COD, pH and concentrations of specific organics, metals and gases. Concentrations of stable cobalt, strontium and cesium were also measured periodically. Soluble radioactivity levels in both systems were reduced by factors of 50 for 58Co, 5 for 85Sr and 7 for 134Cs, taking radioactive decay and dilution into account. Some radionuclide removal from the liquid phase was associated with major chemical changes in the landfills that occurred within 80 days for the control system and within 130 days for the recycle unit. Observed acid, sulfide, and CO2 concentrations suggested mechanisms for removing some of the radionuclides from leachate. Detection of 3H in the off-gas indicated that less than 1% of tritiated waste became airborne. The waste in the leachate recycle unit was more completely stabilized than in the control unit.

  20. The enrichment behavior of natural radionuclides in pulverized oil shale-fired power plants

    International Nuclear Information System (INIS)

    Vaasma, Taavi; Kiisk, Madis; Meriste, Tõnis; Tkaczyk, Alan Henry

    2014-01-01

    The oil shale industry is the largest producer of NORM (Naturally Occurring Radioactive Material) waste in Estonia. Approximately 11–12 million tons of oil shale containing various amounts of natural radionuclides is burned annually in the Narva oil shale-fired power plants, which accounts for approximately 90% of Estonian electricity production. The radionuclide behavior characteristics change during the fuel combustion process, which redistributes the radionuclides between different ash fractions. Out of 24 operational boilers in the power plants, four use circulating fluidized bed (CFB) technology and twenty use pulverized fuel (PF) technology. Over the past decade, the PF boilers have been renovated, with the main objective to increase the efficiency of the filter systems. Between 2009 and 2012, electrostatic precipitators (ESP) in four PF energy blocks were replaced with novel integrated desulphurization technology (NID) for the efficient removal of fly ash and SO 2 from flue gases. Using gamma spectrometry, activity concentrations and enrichment factors for the 238 U ( 238 U, 226 Ra, 210 Pb) and 232 Th ( 232 Th, 228 Ra) family radionuclides as well as 40 K were measured and analyzed in different PF boiler ash fractions. The radionuclide activity concentrations in the ash samples increased from the furnace toward the back end of the flue gas duct. The highest values in different PF boiler ash fractions were in the last field of the ESP and in the NID ash, where radionuclide enrichment factors were up to 4.2 and 3.3, respectively. The acquired and analyzed data on radionuclide activity concentrations in different PF boiler ashes (operating with an ESP and a NID system) compared to CFB boiler ashes provides an indication that changes in the fuel (oil shale) composition and boiler working parameters, as well as technological enhancements in Estonian oil shale fired power plants, have had a combined effect on the distribution patterns of natural radionuclides in

  1. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.; Wollongong Univ.; Tomiyoshi, K.; Sekine, T.

    1997-01-01

    The present status and future directions of research and development on radionuclide generator technology are reported. The recent interest to develop double-neutron capture reactions for production of in vivo generators; neutron rich nuclides for radio-immunotherapeutic pharmaceuticals: and advances with ultra-short lived generators is highlighted. Emphasis is focused on: production of the parent radionuclide; the selection and the evaluation of support materials and eluents with respect to the resultant radiochemical yield of the daughter, and the breakthrough of the radionuclide parent: and, the uses of radionuclide generators in radiopharmaceutical chemistry, biomedical and industrial applications. The 62 Zn → 62 Cu, 66 Ni → 66 Cu, 103m Rh → 103 Rh, 188 W → 188 Re and the 225 Ac → 221 Fr → 213 Bi generators are predicted to be emphasized for future development. Coverage of the 99 Mo → 99m Tc generator was excluded, as it the subject of another review. The literature search ended June, 1996. (orig.)

  2. Effect of age on the metabolism of inhaled beryllium fluoride in rats

    Energy Technology Data Exchange (ETDEWEB)

    Moskalev, Yu.I.; Bugryshev, P.F.; Zaikina, T.I. (Ministry of Health, Moscow (USSR). Inst. of Biophysics)

    1988-01-01

    The studies reported here investigated age-related differences in the distribution of {sup 7}Be following a single inhalation of carrier-free {sup 7}BeF{sub 2} by rats. Age greatly affected the amount of {sup 7}BeF{sub 2} deposited in each region of the respiratory system, the rate of beryllium translocation from the upper respiratory tract and oral cavity to the stomach, its retention in each section of the gastrointestinal tract, the distribution pattern and the routes of removal. (author).

  3. Ease-of-use preference for the ELLIPTA® dry powder inhaler over a commonly used single-dose capsule dry powder inhaler by inhalation device-naïve Japanese volunteers aged 40 years or older

    Directory of Open Access Journals (Sweden)

    Komase Y

    2014-12-01

    Full Text Available Yuko Komase,1 Akimoto Asako,2 Akihiro Kobayashi,3 Raj Sharma4 1Department of Respiratory Internal Medicine, St Marianna University School of Medicine, Yokohama City Seibu Hospital, Yokohama, Kanagawa, Japan; 2MA Respiratory Department, Development and Medical Affairs Unit, GlaxoSmithKline KK, Tokyo, Japan; 3Biomedical Data Sciences Department, GlaxoSmithKline KK, Tokyo, Japan; 4Global Respiratory Franchise Medical Department, GSK, Stockley Park, UK Background: In patients receiving inhaled medication, dissatisfaction with and difficulty in using the inhaler can affect treatment adherence. The incidence of handling errors is typically higher in the elderly than in younger people. The aim of the study was to assess inhaler preference for and handling errors with the ELLIPTA® dry powder inhaler (DPI, (GSK, compared with the established BREEZHALER™, a single-dose capsule DPI (Novartis, in inhalation device-naïve Japanese volunteers aged ≥40 years. Methods: In this open-label, nondrug interventional, crossover DPI preference study comparing the ELLIPTA DPI and BREEZHALER, 150 subjects were randomized to handle the ELLIPTA or BREEZHALER DPIs until the point of inhalation, without receiving verbal or demonstrative instruction (first attempt. Subjects then crossed over to the other inhaler. Preference was assessed using a self-completed questionnaire. Inhaler handling was assessed by a trained assessor using a checklist. Subjects did not inhale any medication in the study, so efficacy and safety were not measured. Results: The ELLIPTA DPI was preferred to the BREEZHALER by 89% of subjects (odds ratio [OR] 70.14, 95% confidence interval [CI] 33.69–146.01; P-value not applicable for this inhaler for ease of use, by 63% of subjects (OR 2.98, CI 1.87–4.77; P<0.0001 for ease of determining the number of doses remaining in the inhaler, by 91% for number of steps required, and by 93% for time needed for handling the inhaler. The BREEZHALER was

  4. Conference report: 1st Medicon Valley Inhalation Symposium.

    Science.gov (United States)

    Lastow, Orest

    2013-02-01

    The 1st Medicon Valley Inhalation Symposium was arranged by the Medicon Valley Inhalation Consortium. It was held at the Medicon Village site, which is the former AstraZeneca site in Lund, Sweden. It was a 1-day symposium focused on inhaled drug delivery and inhalation product development. A total of 90 delegates listened to 15 speakers. The program was organized to follow the value chain of an inhalation product development. The benefits and future opportunities of inhaled drug delivery were discussed together with some new disease areas that can be targeted with inhalation. The pros and cons of the two main formulation types; dry powder and liquid formulations, were discussed by a panel. The different requirements of the drug molecules from a pharmacology, chemical and physical perspective were explained. The modeling of the physics inside an inhaler was demonstrated and the potential strategic benefits of device design were highlighted together with the many challenges of formulation manufacturing. Lung deposition mechanisms and the difficulties of the generic bioequivalence concept were discussed. Using an anatomically correct impactor inlet is a valuable tool in lung deposition predictions and the planning of clinical trials. The management of the biological material generated in clinical studies is key to successful studies.

  5. Disturbance of deposition and removal of plutonium

    International Nuclear Information System (INIS)

    Fukuda, Satoshi

    1992-01-01

    The chelation therapy using DTPA (diethylenetriaminepentaacetic acid) and a new drug, CBMIDA [catechol 3, 6-bis (methyleiminodiacetic acid)] showing more effectiveness on removal of plutonium and lower toxicity than DTPA, is available for occupational exposure but is difficult for public exposure, because there are many reluctant problems on their toxicities, administration routes and times, physical conditions of victims etc. We demonstrated that active amino acid calcium (AAACa), a natural product which mixed oyster shell electrolysate and amino acids of seaweeds, could remove plutonium from bone and liver in rats. The removing methods of radionuclides using the bioavailability of AAACa will be utilized for public exposures and resolve the reluctant problems accompanied with a chelation therapy for occupational exposure. (author)

  6. Workplace Inhalant Abuse in Adult Female: Brief Report

    Directory of Open Access Journals (Sweden)

    Rohit Verma

    2011-01-01

    Full Text Available Inhalant abuse is the purposeful inhalation of intoxicating gases and vapors for the purpose of achieving an altered mental state. With its propensity for being yet an under-recognized form of substance use, being gateway to hard substances, cross-cultural penetration crossing socioeconomic boundaries, and causing significant morbidity and mortality in early ages, the prevention of inhalant misuse is a highly pertinent issue. This clinical report identifies a newer perspective in the emergence of inhalant abuse initiation. We report a case of an adult female with late onset of inhalant dependence developing at workplace and recommend for greater awareness, prevention, and management of this expanding substance abuse problem.

  7. Chemical controls on subsurface radionuclide transport

    International Nuclear Information System (INIS)

    King, K.J.; Killey, R.W.D.

    1990-01-01

    Chemical and biochemical processes can affect the movement of contaminants in groundwater. Materials can be almost completely removed from circulation by processes such as precipitation and coprecipitation. Organic compounds or contaminants that are hazardous may be degraded or formed during groundwater transport. Studies at the Chalk River Laboratories of AECL have focused on radionuclide transport, although other contaminants have been and are being investigated. This paper summarizes findings from research that extends back more than 30 years. Much of the work on reactive contaminant transport has centered on 90 Sr; other contaminants have also been considered, however, and features of their behaviour are also reviewed. (25 refs., 5 figs., 4 tabs.)

  8. Radiation Doses to Members of the U.S. Population from Ubiquitous Radionuclides in the Body: Part 2, Methods and Dose Calculations

    International Nuclear Information System (INIS)

    Watson, David J.; Strom, Daniel J.

    2011-01-01

    This paper is part two of a three-part series investigating annual effective doses to residents of the United States from intakes of ubiquitous radionuclides, including radionuclides occurring naturally, radionuclides whose concentrations are technologically enhanced, and anthropogenic radionuclides. This series of papers explicitly excludes intakes from inhaling 222Rn, 220Rn, and their short-lived decay products; it also excludes intakes of radionuclides in occupational and medical settings. Part one reviewed, summarized, characterized, and grouped all published and some unpublished data for U.S. residents on ubiquitous radionuclide concentrations in tissues and organs. Assumptions about equilibrium with long-lived parents are made for the 28 other radionuclides in these series lacking data. This paper describes the methods developed to group the collected data into source regions described in the Radiation Dose Assessment Resource (RADAR) dosimetric methodology. Methods for converting the various units of data published over 50 years into a standard form are developed and described. Often, meaningful values of uncertainty of measurements were not published so that variability in data sets is confounded with measurement uncertainty. A description of the methods developed to estimate variability is included in this paper. The data described in part one are grouped by gender and age to match the RADAR dosimetric phantoms. Within these phantoms, concentration values are grouped into source tissue regions by radionuclide, and they are imputed for source regions lacking tissue data. Radionuclide concentrations are then imputed for other phantoms source regions with missing concentration values, and the uncertainties of the imputed values are increased. The content concentrations of hollow organs are calculated, and activities are apportioned to the bone source regions using assumptions about each radionuclide's bone-seeking behavior. The data sets are then ready to be

  9. Removal of inhaled 241Am oxide of various particle sizes from beagle dogs by lung lavage and chelation treatment

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Mewhinney, J.A.; Mo, T.; Felicetti, S.A.

    1976-01-01

    The removal of 241 Am oxide aerosols of various particle sizes from the lung was studied in 24 Beagle dogs. There were four groups of dogs with six dogs per group and each group inhaled an aerosol of 241 Am oxide of a different particle size or particle size distribution. The four aerosols had sizes of: 0.75 μm AD, sigma/sub g/ 1.1; 1.5 μm AD, sigma/sub g/ 1.1; 3.0 μm AD, sigma/sub g/ 1.1; or 1.5 μm AMAD and sigma/sub g/ of 1.6. Three of the dogs in each group were treated with 10 lung lavages, the first lavage performed 2 days after exposure and the last lavage on day 49 after exposure. Each of these treated dogs was also given 100 mg diethylenetriaminepentaacetic acid (DTPA) intravenously daily for 4 days after 241 Am exposure and twice per week thereafter to the end of the study. Daily excreta collections were made on each of the dogs until sacrifice at 64 days after exposure. The sacrifice body burden (SBB) was much lower for all of the treated dogs compared to the untreated dogs. The 241 Am activity found in the recovered lavage fluid was two to four times greater than the sacrifice body burden. These results suggest that the treatment procedures were effective in reducing the lung and body burden of 241 Am

  10. Simultaneous treatment of chlorinated organics and removal of metals and radionuclides with bimetals and complexing acids - application to surfactant solutions

    Energy Technology Data Exchange (ETDEWEB)

    Korte, N.E.; Gu, B. [Oak Ridge National Lab., TN (United States)

    1997-10-01

    Currently available methods for separation and treatment of radioactive mixed waste are typically energy-intensive, and often require high temperatures. Passive methods that operate at ambient temperatures are needed. The purpose of this task is to develop bimetallic substrates, using a base metal such as iron and a promoter metal such as palladium (Pd), to provide a passive, low-energy solution to a substantial portion of DOE`s mixed-waste problem. This technology consists of a porous medium that can simultaneously dechlorinate hazardous organics such as TCE and polychlorinated biphenyls (PCBs) at the same time that it removes metallic and hazardous wastes from a solvent/surfactant solution. The porous medium consists of a bimetallic substrate such as palladized iron (Pd/Fe). Palladium is readily chemically plated on iron and preliminary studies suggest that only 0.05 to 0.1% Pd is needed for an efficient reaction. Thus, the cost of the material is reasonable especially is it is long-lived or can be regenerated. Field implementation would consist of the passage of a surfactant-laden, mixed waste through a column or bed of the bimetallic substrate. The organic component of this mixed waste may contain semivolatile compounds such as PCBs or pesticides and herbicides. The bimetal simultaneously removes radionuclides and metals and degrades halogenated hydrocarbons. Virtually any concentration can be treated. Following reaction of the bimetal with the waste stream, the resulting effluent will consist of an uncontaminated aqueous solution of surfactant or solvent that can be reused. The bimetal would then be rinsed with a dilute mineral acid or a mild complexing acid (e.g., oxalic or citric acid) to regenerate the surface and to remove sorbed metals and non-hazardous organic residue. The latter effluent would be low-level radioactive waste in some cases, but it would now be much easier to manage and be of a lower volume than the original mixed waste.

  11. Producing nitric oxide by pulsed electrical discharge in air for portable inhalation therapy.

    Science.gov (United States)

    Yu, Binglan; Muenster, Stefan; Blaesi, Aron H; Bloch, Donald B; Zapol, Warren M

    2015-07-01

    Inhalation of nitric oxide (NO) produces selective pulmonary vasodilation and is an effective therapy for treating pulmonary hypertension in adults and children. In the United States, the average cost of 5 days of inhaled NO for persistent pulmonary hypertension of the newborn is about $14,000. NO therapy involves gas cylinders and distribution, a complex delivery device, gas monitoring and calibration equipment, and a trained respiratory therapy staff. The objective of this study was to develop a lightweight, portable device to serve as a simple and economical method of producing pure NO from air for bedside or portable use. Two NO generators were designed and tested: an offline NO generator and an inline NO generator placed directly within the inspiratory line. Both generators use pulsed electrical discharges to produce therapeutic range NO (5 to 80 parts per million) at gas flow rates of 0.5 to 5 liters/min. NO was produced from air, as well as gas mixtures containing up to 90% O2 and 10% N2. Potentially toxic gases produced in the plasma, including nitrogen dioxide (NO2) and ozone (O3), were removed using a calcium hydroxide scavenger. An iridium spark electrode produced the lowest ratio of NO2/NO. In lambs with acute pulmonary hypertension, breathing electrically generated NO produced pulmonary vasodilation and reduced pulmonary arterial pressure and pulmonary vascular resistance index. In conclusion, electrical plasma NO generation produces therapeutic levels of NO from air. After scavenging to remove NO2 and O3 and filtration to remove particles, electrically produced NO can provide safe and effective treatment of pulmonary hypertension. Copyright © 2015, American Association for the Advancement of Science.

  12. Determination of operating limits for radionuclides for a proposed landfill at Paducah Gaseous Diffusion Plant

    International Nuclear Information System (INIS)

    Wang, J.C.; Lee, D.W.; Ketelle, R.H.; Lee, R.R.; Kocher, D.C.

    1994-01-01

    The operating limits for radionuclides in sanitary and industrial wastes were determined for a proposed landfill at the Paducah Gaseous Diffusion Plant (PGDP), Kentucky. These limits, which may be very small but nonzero, are not mandated by law or regulation but are needed for rational operation. The approach was based on analyses of the potential contamination of groundwater at the plant boundary and the potential exposure to radioactivity of an intruder at the landfill after closure. The groundwater analysis includes (1) a source model describing the disposal of waste and the release of radionuclides from waste to the groundwater, (2) site-specific groundwater flow and contaminant transport calculations, and (3) calculations of operating limits from the dose limit and conversion factors. The intruder analysis includes pathways through ingestion of contaminated vegetables and soil, external exposure to contaminated soil, and inhalation of suspended activity from contaminated soil particles. In both analyses, a limit on annual effective dose equivalent of 4 mrem (0.04 mSv) was adopted. The intended application of the results is to refine the radiological monitoring standards employed by the PGDP Health Physics personnel to determine what constitutes radioactive wastes, with concurrence of the Commonwealth of Kentucky

  13. Environmentally important radionuclides in non-proliferative fuel cycles

    International Nuclear Information System (INIS)

    Kaye, S.V.; Till, J.E.

    1978-01-01

    Increased emphasis in energy research is being given to the development of nonproliferative nuclear fuel cycles and to the assessment of potential release of radionuclides to the environment from these new cycles. Four radionuclides, 14 C, 3 H, 99 Tc, and 232 U, due to lack of adequate knowledge or anticipated increased production in nonproliferative fuel cycles, may require renewed consideration. Our projections indicate that releases of 14 C by the global nuclear industry could exceed the natural production rate of 3.8 x 10 4 Ci/y by the year 2000 and could eventually stabilize at 2.3 times that rate. Tritium may become increasingly important, because recent data from fast reactors (of the nonproliferative type) have confirmed production rates up to 13 times greater than previous estimates. Present radwaste systems do not remove tritium. Recent experiments on the uptake of 99 Tc reveal that soil-to-plant concentration factors for technetium appear to be two to three orders of magnitude greater than the value of 0.25 which has been adopted routinely in radiological assessments. Research is needed to determine reliable 99 Tc soil-to-plant concentration factors because this radionuclide could be released at reprocessing and enrichment facilities. New calculations for certain reactors indicate that 232 U may be formed in concentrations up to 4000 ppm. If accurate, such data will require careful analysis of possible releases of 232 U because of external and food chain exposures. The environmental health aspects of these four radionuclides are discussed, as well as the potential for their release to the environment from nonproliferative fuel cycles. (author)

  14. Radionuclides in terrestrial ecosystems

    International Nuclear Information System (INIS)

    Allen, S.E.; Horrill, A.D.; Howard, B.J.; Lowe, V.P.W.; Parkinson, J.A.

    1983-07-01

    The subject is discussed under the headings: concentration and spatial distribution of radionuclides in grazed and ungrazed saltmarshes; incorporation of radionuclides by sheep grazing on an estuarine saltmarsh; inland transfer of radionuclides by birds feeding in the estuaries and saltmarshes at Ravenglass; radionuclides in contrasting types of coastal pastures and taken up by individual plant species found in west Cumbria; procedures developed and used for the measurement of alpha and gamma emitters in environmental materials. (U.K.)

  15. The measurement of released radionuclides during TIG-Welding and Grinding

    International Nuclear Information System (INIS)

    Reichelt, A.; Lehmann, K.-H.; Reineking, A.; Eder, E.

    2000-01-01

    The radiological relevance of the TIG welding using thoriated tungsten electrodes has recently been proved by means of different studies. As a result of this the TUEV Sueddeutschland and the University of Goettingen have carried out special investigations concerning the release of radionuclides during TIG welding. The main emphasis of these investigations were the representativity of various sampling techniques, the influence of various parameters during welding as well as the determination of activity size distributions related to the aerodynamic diameter of the inhaled aerosols. The properties of the tungsten rods are improved through the addition of radioactive thorium. We investigated the radiation exposure by handling with thoriated tungsten welding rods. We investigated the different exposure pathways and determined the specific activity in dependence to the different types of welding rods. By carrying out surveys with the users, we determined the exposure pathways for the individual exposed persons: TIG - hand-welders', TIG 'machine-welders', labourers, other persons. We measured the activity concentration of the breathing air while welding, at grinding the electrodes and by staying in the rooms where usually it's welded. The size distribution of the aerosol-attached activity was determined with several kinds of impactors. The main emphasis was the comparison of the different sampling systems at the measuring of the activity concentration of the breathing air. Selective sampling by impactors: · Berner-impactor, stationary · Sierra-impactor, stationary · Anderson-Imcaktor, stationary · Marple-impactor, personal sampler Aerosol sampling by air samplers · 5 personal air sampler · 2 stationary sampler, ring face · 2 stationary sampler, open face Rn-220-Measurements · Thoron-monitor Determination of activities on measuring filters · alpha spectrometry · low-level-gamma-spectrometry. For the various exposed persons, at the extern irradiation with gamma

  16. The Advantages of Low-Flow Inhalational Anesthesia

    Directory of Open Access Journals (Sweden)

    P. Torok

    2005-01-01

    Full Text Available The paper deals with the economical and ecological use of inhalation anesthetics in low-flow anesthesia (LFA, 1—0.5 l/ min and high-flow anesthesia (HFA, more than 2—6 l/min. Four hundred and ninety six inhalational anesthesias lasting at least 80 minutes were analyzed in each group under consideration. The concentration of inhalation anesthetics was measures in the atmosphere of an operative theatre if inhalational anesthesia lasted more than 4 hours. There is evidence for the economical and ecological benefits in the use of LFA in terms of the availability of appropriate anesthesiological equipment, monitoring, and a highly skilled anesthesiologist.

  17. Inhalation treatment of primary lung cancer using liposomal curcumin dry powder inhalers

    Directory of Open Access Journals (Sweden)

    Tongtong Zhang

    2018-05-01

    Full Text Available Lung cancer is the leading cause of cancer-related deaths. Traditional chemotherapy causes serious toxicity due to the wide bodily distribution of these drugs. Curcumin is a potential anticancer agent but its low water solubility, poor bioavailability and rapid metabolism significantly limits clinical applications. Here we developed a liposomal curcumin dry powder inhaler (LCD for inhalation treatment of primary lung cancer. LCDs were obtained from curcumin liposomes after freeze-drying. The LCDs had a mass mean aerodynamic diameter of 5.81 μm and a fine particle fraction of 46.71%, suitable for pulmonary delivery. The uptake of curcumin liposomes by human lung cancer A549 cells was markedly greater and faster than that of free curcumin. The high cytotoxicity on A549 cells and the low cytotoxicity of curcumin liposomes on normal human bronchial BEAS-2B epithelial cells yielded a high selection index partly due to increased cell apoptosis. Curcumin powders, LCDs and gemcitabine were directly sprayed into the lungs of rats with lung cancer through the trachea. LCDs showed higher anticancer effects than the other two medications with regard to pathology and the expression of many cancer-related markers including VEGF, malondialdehyde, TNF-α, caspase-3 and BCL-2. LCDs are a promising medication for inhalation treatment of lung cancer with high therapeutic efficiency. Key words: Curcumin, Dry powder inhaler, Liposome, Primary lung cancer, Pulmonary delivery

  18. Radionuclide data

    International Nuclear Information System (INIS)

    Anon.

    1992-01-01

    Chapter 8 presents tables on selected alpha, beta, gamma and x-ray emitters by increasing energy; information on specific activity for selected radionuclides; naturally occurring radionuclides; the natural decay series; and the artificially produced neptunium series. A table of alpha emitters is listed by increasing atomic number and by energy. The table of β emitters presented is useful in identifying β emitters whose energies and possibly half-lives have been determined by standard laboratory techniques. It is also a handy guide to β-emitting isotopes for applications requiring specific half-lives and/or energies. Gamma rays for radionuclides of importance to radiological assessments and radiation protection are listed by increasing energy. The energies and branching ratios are important for radionuclide determinations with gamma spectrometry detectors. This section also presents a table of x-ray energies which are useful for radiochemical analyses. A number of nuclides emit x-rays as part of their decay scheme. These x-rays may be counted with Ar proportional counters, Ge planar or n-type Ge co-axial detectors, or thin crystal NaI(T1) scintillation counters. In both cases, spectral measurements can be made and both qualitative and quantitative information obtained on the sample. Nuclear decay data (energy and probability by radiation type) for more than one hundred radionuclides that are important to health physicists are presented in a schematic manner

  19. Committed dose equivalent per intake of unit activity of radionuclides, for four age-groups, concerning the members of the public for the environmental impact evaluation's of radioactive releases

    International Nuclear Information System (INIS)

    Breuer, F.; Brofferio, C.; Sacripanti, A.

    1983-01-01

    In the present work, with the aim of estimating more realistically the committed dose equivalent for the members of the public in the environmental impact evaluation's of nuclear plants, the authors supply a methodology for calculating the committed dose equivalents for inhalation and ingestion, and the values for fiftheen organs and sixi-three radionuclides, concerning four specific age-groups on the ground of data published by Icrp n.30 part 1, 2, 3

  20. Heavy metals and their radionuclides uptake by Bacillus Licheniformis

    International Nuclear Information System (INIS)

    Ramadan, A.A.; Ahmed, M.M.; Abo-state, M.A.M.; Sarhan, M.; Faroqe, M.

    2007-01-01

    Bacillus licheniformis is a gram positive spore forming bacterium. Different concentrations of cobalt affected the ability of Co uptake and growth of Bacillus licheniformis. As the concentration increased, both the uptake and growth were decreased. Maximum Co uptake was found at ph 7.0, while for growth was ph 8.0. The optimum temperature for uptake and growth was 40 degree C and 20% inoculum size represents the maximum cobalt uptake by Bacillus licheniformis. Also, maximum uptake was recorded after 72 hours, incubation period. As the concentration of cesium was increased till 400 mg/l, the uptake was also increased. The optimum cesium uptake and growth was at ph 8.0. The optimum growth was at 45 degree C while Cs uptake was found at 35 degree C and 15% inoculum size represented the maximum Cs uptake. After 72 hour incubation period, maximum Cs uptake was recorded. Generally, Bacillus licheniformis removed more than 80% of Co and 50% of Cs from the broth medium. Addition of clay to Bacillus licheniformis increased both Co or Cs uptake. Bacillus licheniformis was gamma resistant and 10 KGy reduced the viability by 5.3 log cycles. The irradiated and non-irradiated cultures can grow on 500 or 700 mg Co or Cs. Bacillus licheniformis removed 99.32% of the Co radionuclides and 99.28% of Cs radionuclides

  1. Toxicity of inhaled 144Ce fused clay particles in beagle dogs. VII

    International Nuclear Information System (INIS)

    Hahn, F.F.; Boecker, B.B.; Hobbs, C.H.; Jones, R.K.; Mauderly, J.L.; McClellan, R.O.; Pickrell, J.A.

    1974-01-01

    The metabolism, dosimetry, and effects of inhaled 144 Ce in fused clay particles are being investigated in the Beagle dog to aid in assessing the biological consequences of release of 144 Ce in a relatively insoluble form such as might occur in certain types of nuclear accidents. The toxicity of inhaled 144 Ce fused clay is also of general interest since it is representative of intermediate-lived beta-emitting radionuclides. Two major studies with young adult dogs (12 to 14 months of age at exposure) are involved: (1) a metabolism and dosimetry study in which 24 dogs were serially sacrificed over an extended period of time, and (2) a longevity study with 2 series of dogs; Series I with 15 dogs exposed to aerosols of 144 Ce in fused clay particles to yield initial lung burdens of 11 to 210 μCi/kg body weight and 3 control dogs exposed to nonradioactive fused clay particles and Series II with 96 dogs exposed to aerosols of 144 Ce in fused clay particles to yield initial lung burdens of 0.0024 to 66 μCi/kg body weight and 12 control dogs exposed to nonradioactive fused clay particles. Twenty-eight dogs died or were euthanized at 143 to 2396 days after inhalation of 144 Ce. The prominent findings were radiation pneumonitis in 17 dogs that died or were euthanized at early time periods and neoplastic disease in 10 of the 11 dogs that died or were euthanized at 750 days or later; 5 with hemangiosarcoma of the lung, 1 with both a hemangiosarcoma and a fibrosarcoma of the lung, 1 with both a bronchiolo-alveolar carcinoma and a hemangiosarcoma of lung, 1 with a hemangiosarcoma of lung, bronchiolo-alveolar carcinoma, and a bronchiogenic adenocarcinoma, and 1 each with a hemangiosarcoma of the mediastinum and of the spleen. The cumulative radiation dose to the lung at time of death has ranged from 22,000 to 140,000 rads. Serial observations are continuing on the 83 survivors and 15 controls. (U.S.)

  2. Radioaerosol Inhalation Imaging in Bronchial Asthma

    International Nuclear Information System (INIS)

    Kim, Bum Soo; Park, Young Ha; Park, Jeong Mi; Chung, Myung Hee; Chung, Soo Kyo; Shinn, Kyung Sub; Bahk, Yong Whee

    1991-01-01

    Radioaerosol inhalation imaging (RII) has been used in radionuclide pulmonary studies for the past 20 years. The method is well accepted for assessing regional ventilation because of its usefulness, easy fabrication and simple application system. To evaluate its clinical utility in the study of impaired regional ventilation in bronchial asthma, we obtained and analysed RIIs in 31 patients (16 women and 15 men; age ranging 21-76 years) with typical bronchial asthma at the Department of Radiology, Kangnam St. Mary's Hospital, Catholic University Medical college, from January, 1988 to August, 1989. Scintiscans were obtained with radioaerosol produced by a HARC(Bhabha Atomic Research Center, India) nebulizer with 15 mCi of 99m Tc-phytate. The scanning was performed in anterior, posterior and lateral projections following 5-minute inhalation of radioaerosol on sitting position. The scans were analysed and correlated with the results of pulmonary function study and the findings of chest radiography. Fifteen patients had concomitant lung perfusion image with 99m Tc-MAA. Follow-up scans were obtained in 5 patients after bronchodilator therapy. 1 he patients were divided into (1) attack type (4 patients), (2) resistant type (5 patients), (3) remittent type (10 patients) and (4) bronchitic type (12 patients). Chest radiography showed hyperinflation, altered pulmonary vascularity, thickening of the bronchial wall and accentuation of hasal interstitial markings in 26 of the 31 patients. Chest radiographs were normal in the remaining 5 patients. Regardless of type, the findings of RII were basically the same, and characterized by the deposition of radioaerosol in the central parts or in the main respiratory air ways along with mottled nonsegmental ventilation defects in the periphery. Peripheral parenchymal defects were more extensive than that of expected findings from clinical symptoms, pulmonary function test and chest radiograph. Broomstick sign was present in 1.7 patients

  3. Removal of mercury from water using pottery

    International Nuclear Information System (INIS)

    Helal, A.A.A.

    2006-01-01

    In a previous study, the sorption of radiocobalt by powdered pottery materials was investigated. The use of these materials as immobilization matrix for liquid radioactive waste requires the employment of pottery vessels. Therefore, the present study aims to give detailed investigations of the decontamination of radionuclides and toxic elements using pottery containers. These investigations are equally useful to elucidate how far these vessels can be utilized for water purification through decontamination of toxic and heavy metals. The radionuclide or heavy metal removal capability using pottery pots, as low cost sorbents, has been investigated for both radioactive ( 203 Hg) and stable mercury. The results indicated that Hg 2+ is better removed by pottery from neutral to alkaline solutions. The capacity of the used pottery container (100 ml in volume) for complete removal of mercury was found to reach 3 x 10 -4 mol/l, and the time needed was 8 hours. The sorption process was suggested to occur via adsorption and ion exchange. The effect of presence of humic or fulvic acid, as ligands abundant in water, is also investigated. The results imply that, in absence of humic or fulvic acid the sorption follows the expected behaviour, i.e. sorption sites with similar affinity for mercury. In presence of humic or fulvic acid, additional sorption sites are available by the organic molecule when it is associated to the pottery. (orig.)

  4. Radionuclide contaminant analysis of rodents at a waste burial site, Los Alamos National Laboratory

    International Nuclear Information System (INIS)

    Biggs, J.R.; Bennett, K.D.; Fresquez, P.R.

    1996-01-01

    Small mammals were sampled at two waste burial sites (Sites 1 and 2) at Area G, TA-54, and a control site outside Area G (Site 3) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for americium ( 241 Am), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), total uranium (U), and examined by gamma spectroscopy (including cesium [ 137 Cs]). Significantly higher (parametric t-test at p = 0.05) levels of total U, 241 Am, 238 Pu, and potassium ( 40 K) were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. The results show higher concentrations in pelts compared to carcasses which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had significantly higher (alpha = 0.05, P = 0.0095) total U concentrations in carcasses than Sites 2 and 3. Site 2 had significantly higher (alpha = 0.05, P = 0.0195) 239 Pu concentrations in carcasses than either Site 1 or Site 3

  5. Radionuclide separations and processing for defense water management

    International Nuclear Information System (INIS)

    Fryberger, T.B.

    1993-01-01

    An overview is given of the Department of Energy's Efficient Separations and Processing Integrated Program (ESPIP). This program sponsors research in advanced chemical separations for removal of radionuclides and hazardous components from radioactive defense wastes. Separations processing will reduce the volume of high-level waste that must be disposed of in a deep geological repository and will improve the quality of low-level wastes acceptable for near-surface disposal. DOE defense complex processing needs as well as technologies that are currently under development in the program are discussed

  6. The effect of dose protraction on the incidence of lung carcinomas in beagle dogs with internally deposited β-emitting radionuclides

    International Nuclear Information System (INIS)

    Griffith, W.C.; Boecker, B.B.; Hahn, F.F.; Muggenburg, B.A.; Snipes, M.B.

    1992-01-01

    Studies using Beagle dogs were conducted to understand health effects when lung is the primary organ irradiated after inhaling insoluble radioactive particles containing one of four β-emitting radionuclides, 90 Y, 91 Y, 144 Ce, or 90 Sr. The low-LET β irradiation was delivered over a wide range of total doses and dose rate patterns that protracted the dose to lung from about 1 wk to several years. The tumor incidence rates for lung carcinomas were estimated using a proportional hazard rate model. These studies suggest that dose protraction only affects production of lung carcinomas at doses above 50 Gy

  7. Radionuclide generators

    International Nuclear Information System (INIS)

    Lambrecht, R.M.

    1983-01-01

    The status of radionuclide generators for chemical research and applications related to the life sciences and biomedical research are reviewed. Emphasis is placed upon convenient, efficient and rapid separation of short-lived daughter radionuclides in a chemical form suitable for use without further chemical manipulation. The focus is on the production of the parent, the radiochemistry associated with processing the parent and daughter, the selection and the characteristic separation methods, and yields. Quality control considerations are briefly noted. The scope of this review includes selected references to applications of radionuclide generators in radiopharmaceutical chemistry, and the life sciences, particularly in diagnostic and therapeutic medicine. The 99 Mo-sup(99m)Tc generator was excluded. 202 references are cited. (orig.)

  8. Inhaler devices - from theory to practice

    DEFF Research Database (Denmark)

    Sanchis, Joaquin; Corrigan, Chris; Levy, Mark L

    2013-01-01

    This brief overview of the factors determining lung deposition of aerosols provides background information required by health care providers when instructing patients to use their prescribed inhalers. We discuss differences in the optimal inhalation manoeuvres for each type of aerosol generator a...

  9. Inherently safe aircooling for the storage of self-heating configurations of radionuclides

    International Nuclear Information System (INIS)

    Hame, W.; Klein, D.; Pirk, H.

    1980-01-01

    NUKEM developed a technical concept of a radionuclide storage facility based on aircooling, which provides that - the radionuclides, i.e. spent fuel elements, are tightly canned in steel canisters - the canned elements are put into individual cooling channels, which form the storage rack within the storage cell - the produced heat is removed from the surface of the canisters through free convection. This cooling concept shows the following advantages: - The cooling is inherently safe, as the driving force of the coolant is reliably supplied by the heat production of the system to be cooled. - The system is self-controlled and self-regulated because of the physically based correlation of heat production, heat transfer coefficients and air flow resistances. (orig.) 891 RB/orig. 892 MKO [de

  10. AIRDOS-II computer code for estimating radiation dose to man from airborne radionuclides in areas surrouding nuclear facilities

    International Nuclear Information System (INIS)

    Moore, R.E.

    1977-04-01

    The AIRDOS-II computer code estimates individual and population doses resulting from the simultaneous atmospheric release of as many as 36 radionuclides from a nuclear facility. This report describes the meteorological and environmental models used is the code, their computer implementation, and the applicability of the code to assessments of radiological impact. Atmospheric dispersion and surface deposition of released radionuclides are estimated as a function of direction and distance from a nuclear power plant or fuel-cycle facility, and doses to man through inhalation, air immersion, exposure to contaminated ground, food ingestion, and water immersion are estimated in the surrounding area. Annual doses are estimated for total body, GI tract, bone, thyroid, lungs, muscle, kidneys, liver, spleen, testes, and ovaries. Either the annual population doses (man-rems/year) or the highest annual individual doses in the assessment area (rems/year), whichever are applicable, are summarized in output tables in several ways--by nuclides, modes of exposure, and organs. The location of the highest individual doses for each reference organ estimated for the area is specified in the output data

  11. Evaluation of Inhaled Versus Deposited Dose Using the Exponential Dose-Response Model for Inhalational Anthrax in Nonhuman Primate, Rabbit, and Guinea Pig.

    Science.gov (United States)

    Gutting, Bradford W; Rukhin, Andrey; Mackie, Ryan S; Marchette, David; Thran, Brandolyn

    2015-05-01

    The application of the exponential model is extended by the inclusion of new nonhuman primate (NHP), rabbit, and guinea pig dose-lethality data for inhalation anthrax. Because deposition is a critical step in the initiation of inhalation anthrax, inhaled doses may not provide the most accurate cross-species comparison. For this reason, species-specific deposition factors were derived to translate inhaled dose to deposited dose. Four NHP, three rabbit, and two guinea pig data sets were utilized. Results from species-specific pooling analysis suggested all four NHP data sets could be pooled into a single NHP data set, which was also true for the rabbit and guinea pig data sets. The three species-specific pooled data sets could not be combined into a single generic mammalian data set. For inhaled dose, NHPs were the most sensitive (relative lowest LD50) species and rabbits the least. Improved inhaled LD50 s proposed for use in risk assessment are 50,600, 102,600, and 70,800 inhaled spores for NHP, rabbit, and guinea pig, respectively. Lung deposition factors were estimated for each species using published deposition data from Bacillus spore exposures, particle deposition studies, and computer modeling. Deposition was estimated at 22%, 9%, and 30% of the inhaled dose for NHP, rabbit, and guinea pig, respectively. When the inhaled dose was adjusted to reflect deposited dose, the rabbit animal model appears the most sensitive with the guinea pig the least sensitive species. © 2014 Society for Risk Analysis.

  12. environmental studies for removal of some radioactive elements using zirconium silicate as inorganic ion exchange material

    International Nuclear Information System (INIS)

    El-Aryan, Y.F.A.

    2007-01-01

    inorganic ion exchangers have a good potential than the commonly used organic ones for removal and separation of radionuclides from irradiated nuclear fuel solutions. therefore, the main aim of this work is directed to find the optimum conditions for removal of some radionuclides such as Cs + ,Co 2+ ,and Eu 3+ by the prepared zirconium silicate as cation exchanger. the following items will be involved:-1- preparation of zirconium silicate as a cation exchanger. 2- characterization of the prepared exchanger using IR spectra, X-ray diffraction patterns, DTA and TG analyses. 3-chemical stability, capacity and equilibrium measurements will be determined on the materials using at different conditions (heating temperature and reaction temperature). 4- ion exchange isotherms. 5- breakthrough curves for removal of the investigated metal ions on the prepared exchanger under certain conditions

  13. Radionuclides in radiation-induced bystander effect; may it share in radionuclide therapy?

    Science.gov (United States)

    Widel, M

    2017-01-01

    For many years in radiobiology and radiotherapy predominated the conviction that cellular DNA is the main target for ionizing radiation, however, the view has changed in the past 20 years. Nowadays, it is assumed that not only directed (targeted) radiation effect, but also an indirect (non-targeted) effect may contribute to the result of radiation treatment. Non-targeted effect is relatively well recognized after external beam irradiation in vitro and in vivo, and comprises such phenomena like radiation-induced bystander effect (RIBE), genomic instability, adaptive response and abscopal (out of field) effect. These stress-induced and molecular signaling mediated phenomena appear in non-targeted cells as variety responses resembling that observed in directly hit cells. Bystander effects can be both detrimental and beneficial in dependence on dose, dose-rate, cell type, genetic status and experimental condition. Less is known about radionuclide-induced non-targeted effects in radionuclide therapy, although, based on characteristics of the radionuclide radiation, on experiments in vitro utilizing classical and 3-D cell cultures, and preclinical study on animals it seems obvious that exposure to radionuclide is accompanied by various bystander effects, mostly damaging, less often protective. This review summarizes existing data on radionuclide induced bystander effects comprising radionuclides emitting beta- and alpha-particles and Auger electrons used in tumor radiotherapy and diagnostics. So far, separation of the direct effect of radionuclide decay from crossfire and bystander effects in clinical targeted radionuclide therapy is impossible because of the lack of methods to assess whether, and to what extent bystander effect is involved in human organism. Considerations on this topic are also included.

  14. Identification and analysis of main radionuclides that potentially contribute to the internal dose for workers at radiopharmacy facilities

    International Nuclear Information System (INIS)

    Sanches, Matias Puga

    2004-01-01

    The optimization principle in radiation protection means that there is a reasonable balance between resources used to monitor exposures and the benefits due to the monitoring program. Programs for the monitoring of workers handling radioactive materials are influenced by numerous factors. Estimation of internal doses due to inhalation or ingestion of radioactive materials is often based on measurements of the activity in the tissues of the body and in excreta, following a given intake. In order to enable dose estimations using the biokinetic models recommended by the ICRP and laboratory data, it is proposed to carry out comprehensive study to identify the main radionuclides that potentially contribute to the internal dose of workers at radiopharmacy facilities. The applied methodology for identification of these radionuclides takes into account criteria set out by the ICRP and IAEA. The practical purpose to set up this study was to establish a consistent approach to ensure that the dose assessments are as simple as possible and guarantee the necessary quality standards. The result of this study has indicated the requirement of routine measurements for seven radionuclides over all range of radioactive material compounds, handled at the radiopharmacy plant of IPEN, avoiding unjustifiable work concerning activity levels that are not relevant for the health of the occupationally exposed persons. The main intake pathways, the appropriate monitoring frequencies and derived reference level have also been identified. (author)

  15. Long-term effects of aluminium dust inhalation.

    Science.gov (United States)

    Peters, Susan; Reid, Alison; Fritschi, Lin; de Klerk, Nicholas; Musk, A W Bill

    2013-12-01

    During the 1950s and 1960s, aluminium dust inhalation was used as a potential prophylaxis against silicosis in underground miners, including in Australia. We investigated the association between aluminium dust inhalation and cardiovascular, cerebrovascular and Alzheimer's diseases in a cohort of Australian male underground gold miners. We additionally looked at pneumoconiosis mortality to estimate the effect of the aluminium therapy. SMRs and 95% CI were calculated to compare mortality of the cohort members with that of the Western Australian male population (1961-2009). Internal comparisons on duration of aluminium dust inhalation were examined using Cox regression. Aluminium dust inhalation was reported for 647 out of 1894 underground gold miners. During 42 780 person-years of follow-up, 1577 deaths were observed. An indication of increased mortality of Alzheimer's disease among miners ever exposed to aluminium dust was found (SMR=1.38), although it was not statistically significant (95% CI 0.69 to 2.75). Rates for cardiovascular and cerebrovascular death were above population levels, but were similar for subjects with or without a history of aluminium dust inhalation. HRs suggested an increasing risk of cardiovascular disease with duration of aluminium dust inhalation (HR=1.02, 95% CI 1.00 to 1.04, per year of exposure). No difference in the association between duration of work underground and pneumoconiosis was observed between the groups with or without aluminium dust exposure. No protective effect against silicosis was observed from aluminium dust inhalation. Conversely, exposure to aluminium dust may possibly increase the risk of cardiovascular disease and dementia of the Alzheimer's type.

  16. Assessing inhalation injury in the emergency room

    Directory of Open Access Journals (Sweden)

    Tanizaki S

    2015-07-01

    Full Text Available Shinsuke Tanizaki Department of Emergency Medicine, Fukui Prefectural Hospital, Fukui, Japan Abstract: Respiratory tract injuries caused by inhalation of smoke or chemical products are related to significant morbidity and mortality. While many strategies have been built up to manage cutaneous burn injuries, few logical diagnostic strategies for patients with inhalation injuries exist and almost all treatment is supportive. The goals of initial management are to ensure that the airway allows adequate oxygenation and ventilation and to avoid ventilator-induced lung injury and substances that may complicate subsequent care. Intubation should be considered if any of the following signs exist: respiratory distress, stridor, hypoventilation, use of accessory respiratory muscles, blistering or edema of the oropharynx, or deep burns to the face or neck. Any patients suspected to have inhalation injuries should receive a high concentration of supplemental oxygen to quickly reverse hypoxia and to displace carbon monoxide from protein binding sites. Management of carbon monoxide and cyanide exposure in smoke inhalation patients remains controversial. Absolute indications for hyperbaric oxygen therapy do not exist because there is a low correlation between carboxyhemoglobin levels and the severity of the clinical state. A cyanide antidote should be administered when cyanide poisoning is clinically suspected. Although an ideal approach for respiratory support of patients with inhalation injuries do not exist, it is important that they are supported using techniques that do not further exacerbate respiratory failure. A well-organized strategy for patients with inhalation injury is critical to reduce morbidity and mortality. Keywords: inhalation injury, burn, carbon monoxide poisoning, cyanide poisoning

  17. Inhaled plutonium oxide in dogs

    International Nuclear Information System (INIS)

    Anon.

    1981-01-01

    This project is concerned with long-term experiments to determine the life-span dose-effect relationships of inhaled 239 PuO 2 and 238 PuO 2 in beagles. The data will be used to estimate the health effects of inhaled transuranics. The tissue distribution of plutonium, radiation effects in the lung and hematologic changes in plutonium-exposed beagles with lung tumors were evaluated

  18. 49 CFR 172.555 - POISON INHALATION HAZARD placard.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false POISON INHALATION HAZARD placard. 172.555 Section... REQUIREMENTS, AND SECURITY PLANS Placarding § 172.555 POISON INHALATION HAZARD placard. (a) Except for size and color, the POISON INHALATION HAZARD placard must be as follows: ER22JY97.025 (b) In addition to...

  19. Radioaerosol inhalation lung imaging for the diagnosis of chronic obstructive pulmonary diseases in Thailand. Final report for the period 10 December 1987 - 15 December 1993

    Energy Technology Data Exchange (ETDEWEB)

    Buachum, V [Chulalongkorn Univ., Bangkok (Thailand). Nuclear Medicine Div.

    1993-12-01

    The radionuclide pulmonary function studies such as aerosol inhalation lung imaging, mucociliary clearance and pulmonary epithelial were developed and studied in normal and chronic obstructive pulmonary disease. The results of the aerosol inhalation lung imaging in 71 cases of COPD revealed that the aerosol inhalation lung scan was the most sensitive test for the diagnosis of early COPD as compared to the chest X-ray, vascular perfusion lung scan and spirometric test (% FEVI). The aerosol and perfusion lung scan were also performed in 21 cases of carcinoma of lung who had been treated with external radiation or chemotherapy. The result of study revealed 5 patients died during treatment, 5 patients were slightly improved, no significant change was detected in 10 cases and deterioration was found in one patient. The lung scintigraphy was studied in 15 cases of well differentiated carcinoma of thyroid with pulmonary metastasis who had I-131 treatment. The study showed that the radioactive iodine treatment dose had minimal effect on the post treatment lung imaging study. The perfusion and aerosol study in 15 cases of operated patients revealed no evidence of pulmonary embolism in post operative study. Abnormal vascular disease or pulmonary embolism was observed in one patient preoperatively. 12 refs, 13 figs, 13 tabs.

  20. Radioaerosol inhalation lung imaging for the diagnosis of chronic obstructive pulmonary diseases in Thailand. Final report for the period 10 December 1987 - 15 December 1993

    International Nuclear Information System (INIS)

    Buachum, V.

    1993-12-01

    The radionuclide pulmonary function studies such as aerosol inhalation lung imaging, mucociliary clearance and pulmonary epithelial were developed and studied in normal and chronic obstructive pulmonary disease. The results of the aerosol inhalation lung imaging in 71 cases of COPD revealed that the aerosol inhalation lung scan was the most sensitive test for the diagnosis of early COPD as compared to the chest X-ray, vascular perfusion lung scan and spirometric test (% FEVI). The aerosol and perfusion lung scan were also performed in 21 cases of carcinoma of lung who had been treated with external radiation or chemotherapy. The result of study revealed 5 patients died during treatment, 5 patients were slightly improved, no significant change was detected in 10 cases and deterioration was found in one patient. The lung scintigraphy was studied in 15 cases of well differentiated carcinoma of thyroid with pulmonary metastasis who had I-131 treatment. The study showed that the radioactive iodine treatment dose had minimal effect on the post treatment lung imaging study. The perfusion and aerosol study in 15 cases of operated patients revealed no evidence of pulmonary embolism in post operative study. Abnormal vascular disease or pulmonary embolism was observed in one patient preoperatively. 12 refs, 13 figs, 13 tabs

  1. Dose patterns for 106RuO4 inhaled by Fischer-344 rats and Beagle dogs

    International Nuclear Information System (INIS)

    Runkle, G.E.; Snipes, M.B.

    1978-01-01

    Ruthenium-106 is an abundant fission product radionuclide in the nuclear fuel cycle which has potential for release as ruthenium tetroxide. Ruthenium tetroxide is a vapor, diffuses rapidly through air and porous materials, is chemically reactive and is rapidly reduced by any organic material to the dioxide form. Current ICRP recommendations consider the lung and gastrointestinal tract as critical organs for inhaled particles of radioactive ruthenium. This study was designed to provide additional data needed to adequately assess the risk for humans potentially exposed to 106 Ru encountered in this vapor form. Fischer-344 rats and Beagle dogs were given a nose-only exposure to 106 RuO 4 vapor to determine its distribution and retention patterns. The largest percentage of the initial body burden was found in the nasopharyngeal region of the respiratory tract. Less than 1% of the initial body burden was deposited in the pulmonary region. Most of the 106 Ru was cleared via the feces. A biomathematical simulation model was developed to fit the tissue and excreta data from the rat. This model was used to assess the short-term and long-term risks after inhalation of 106 RuO 4 . The observed deposition, retention and dose patterns for ruthenium tetroxide indicate the nasopharyngeal region should be considered as a critical region when considering the consequences of human exposure to this vapor

  2. Study of the association between exposure to transuranic radionuclides and cancer death

    Science.gov (United States)

    Fallahian, Naz Afarin

    An exploratory epidemiological study has been conducted on 319 deceased nuclear workers, who had recorded intakes and histories of employment for at least one year during the time period from 1943 to 1995, at different facilities including the United States Department of Energy (DOE) sites, and thorium and uranium mining and milling plants. These workers voluntarily agreed to donate their organs or whole body to the United States Transuranium and Uranium Registries (USTUR) for scientific research purposes. The majority of this population was involved in documented radiological incidents during their careers. Many were exposed to transuranic radionuclides primarily via inhalation or puncture wounds. The purpose of this study was to find the level of dose that was received by the USTUR registrants following accidents and subsequent to mitigating actions, and to investigate whether or not there is any association between exposure to these transuranic radionuclides and cancer deaths. The external and internal dose assessments were performed using occupational radiation exposure histories and postmortem concentrations of transuranic radionuclides in critical organs, respectively. Statistical data analyses were performed to identify whether or not the USTUR registrants can be categorized as a 'low-dose' population and to investigate the potential correlation between exposure to transuranic radionuclides and causes of death within this population due to cancers of the lungs and liver as well as cancers of all sites, while controlling for the effects of other confounders. Based on the statistical tests performed, the USTUR registrants can be categorized as a low-dose population in terms of their occupational external exposures. However, when considering their total effective dose equivalents from both external penetrating radiation and internal exposure to transuranic radionuclides, they can not be categorized as a low-dose population with a 95% confidence level (alpha = 0

  3. Novel fungus-Fe{sub 3}O{sub 4} bio-nanocomposites as high performance adsorbents for the removal of radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Ding, Congcong [Institute of Plasma Physics, Chinese Academy of Science, P.O. Box 1126, Hefei 230031 (China); University of Science and Technology of China, Hefei 230000 (China); Cheng, Wencai [Institute of Plasma Physics, Chinese Academy of Science, P.O. Box 1126, Hefei 230031 (China); Sun, Yubing, E-mail: sunyb@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Science, P.O. Box 1126, Hefei 230031 (China); School for Radiological and Interdisciplinary Sciences (RAD-X), Soochow University and Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, 215123 Suzhou (China); School of Environment and Chemical Engineering, North China Electric Power University, Beijing 102206 (China); Wang, Xiangke, E-mail: xkwang@ipp.ac.cn [Institute of Plasma Physics, Chinese Academy of Science, P.O. Box 1126, Hefei 230031 (China); School for Radiological and Interdisciplinary Sciences (RAD-X), Soochow University and Collaborative Innovation Center of Radiation Medicine of Jiangsu Higher Education Institutions, 215123 Suzhou (China); School of Environment and Chemical Engineering, North China Electric Power University, Beijing 102206 (China); Faculty of Engineering, King Abdulaziz University, Jeddah 21589 (Saudi Arabia)

    2015-09-15

    Highlights: • Fungus was used as a template for the assembly of nano-Fe{sub 3}O{sub 4}. • Fungal template directed the nano-Fe{sub 3}O{sub 4} structure from the micro-scale level. • Fungal template enhanced the dispersity and stability of nano-Fe{sub 3}O{sub 4}. • Fungus-Fe{sub 3}O{sub 4} exhibited high sorption capacity for Sr(II), Th(IV) and U(VI). • Fungus-Fe{sub 3}O{sub 4} possessed satisfactory regeneration performance and reusability. - Abstract: The bio-nanocomposites of fungus-Fe{sub 3}O{sub 4} were successfully synthesized using a low-cost self-assembly technique. SEM images showed uniform decoration of nano-Fe{sub 3}O{sub 4} particles on fungus surface. The FTIR analysis indicated that nano-Fe{sub 3}O{sub 4} was combined to the fungus surface by chemical bonds. The sorption ability of fungus-Fe{sub 3}O{sub 4} toward Sr(II), Th(IV) and U(VI) was evaluated by batch techniques. Radionuclide sorption on fungus-Fe{sub 3}O{sub 4} was independent of ionic strength, indicating that inner-sphere surface complexion dominated their sorption. XPS analysis indicated that the inner-sphere radionuclide complexes were formed by mainly bonding with oxygen-containing functional groups (i.e., alcohol, acetal and carboxyl) of fungus-Fe{sub 3}O{sub 4}. The maximum sorption capacities of fungus-Fe{sub 3}O{sub 4} calculated from Langmuir isotherm model were 100.9, 223.9 and 280.8 mg/g for Sr(II) and U(VI) at pH 5.0, and Th(IV) at pH 3.0, respectively, at 303 K. Fungus-Fe{sub 3}O{sub 4} also exhibited excellent regeneration performance for the preconcentration of radionuclides. The calculated thermodynamic parameters showed that the sorption of radionuclides on fungus-Fe{sub 3}O{sub 4} was a spontaneous and endothermic process. The findings herein highlight the novel synthesis method of fungus-Fe{sub 3}O{sub 4} and its high sorption ability for radionuclides.

  4. Characterization of a New High-Dose Dry Powder Inhaler (DPI) Based on a Fluidized Bed Design.

    Science.gov (United States)

    Farkas, Dale R; Hindle, Michael; Longest, P Worth

    2015-11-01

    The objective of this study was to develop a new high-efficiency dry powder inhaler (DPI) that can effectively aerosolize large masses (25-100 mg) of spray dried powder formulations. The DPI was designed to implement a concept similar to a fluidized bed for aerosolization using small mixing balls made of polytetrafluoroethylene along with a larger, hollow dosing sphere filled with the powder. The performance of the fluidized bed DPI was compared, based on emitted dose (ED) and aerosolization efficiency, to other recently developed capsule-based DPIs that were designed to accommodate smaller powder masses (~2-20 mg). The inhalers were tested with spray dried excipient enhanced growth (EEG) formulations that contained an antibiotic (ciprofloxacin) and hygroscopic excipient (mannitol). The new fluidized bed design produced an ED of 71% along with a mass median aerodynamic diameter of 1.53 μm and fine particle fractions <5 and 1 μm of 93 and 36%, respectively, when used to deliver a 100 mg loaded mass of EEG powder with the advantage of not requiring multiple capsules. Surprisingly, performance of the device was further improved by removing the mixing balls from the inhaler and only retaining the dose containment sphere.

  5. Radionuclide cardiography in medical practice

    International Nuclear Information System (INIS)

    Strangfeld, D.; Mohnike, W.; Schmidt, J.; Heine, H.; Correns, H.J.

    1986-01-01

    This publication is a compendium on all aspects of radionuclide diagnostics concerning cardiovascular system diseases. Starting with introductory remarks on the control of cardiovascular diseases the contribution of radionuclide cardiology to functional cardiovascular diagnostics as well as pathophysiological and pathobiochemical aspects of radiocardiography are outlined. Radiopharmaceuticals used in radiocardiography, physical and technical problems in application of radionuclides and their measuring techniques are discussed. In individual chapters radionuclide ventriculography, myocardial scintiscanning, circulatory diagnostics, radionuclide diagnostics of arterial hypertension, of thrombosis and in vitro diagnostics of thrombophilia are treated in the framework of clinical medicine

  6. The risk of liver tumors in dogs and man from radioactive aerosols

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Boecker, B.B.; Hahn, F.F.; Griffith, W.G.; McClellan, R.O.

    1986-01-01

    Life-span studies in progress using beagle dogs that inhaled relatively soluble or relatively insoluble forms of radionuclides will provide information from which we may project the risk to humans for liver cancer from inhaled radioactive material. Twenty-two liver tumors have been observed in dogs exposed to beta-emitting radionuclides, mainly 144 Ce, and one liver tumor in a dog exposed to 238 Pu. Two liver cancers were also observed in control dogs. The risk of liver cancer in dogs that inhaled beta-emitting radionuclides was calculated to be 90 liver cancers per million rads. The risk of liver cancers in dogs in our studies and in studies at the University of Utah, when compared to the incidence of liver tumors in humans exposed to Thorotrast, suggest that the risk of liver cancer from an inhaled beta-emitting radionuclide in people is about 30 liver cancers per million person-rads. 19 refs., 3 tabs

  7. Incorporation of additional radionuclides and the external exposure pathway into the BECAMP [Basic Environmental Compliance and Monitoring Program] radiological assessment model

    International Nuclear Information System (INIS)

    Ng, Yook C.; Rodean, H.C.; Anspaugh, L.R.

    1988-11-01

    The Nevada Applied Ecology Group (NAEG) Model of transport and dose for transuranic radionuclides was modified and expanded for the analysis of radionuclides other than pure alpha-emitters. Doses from internal and external exposures were estimated for the inventories and soil distributions of the individual radionuclides quantified in Areas 2 and 4 of the Nevada Test Site (NTS). We found that the dose equivalents via inhalation to liver, lungs, bone marrow, and bone surface from the plutonium isotopes and 241 Am, those via ingestion to bone marrow and bone surfaces from 90 Sr, and those via ingestion to all the target organs from 137 Cs were the highest from internal exposures. The effective dose equivalents from 137 Cs, 152 Eu, and 154 Eu were the highest from the external exposures. The 60 Co, 152 Eu, 154 Eu, and 155 Eu dose estimates for external exposures greatly exceeded those for internal exposures. The 60 Co, 90 Sr, and 137 Cs dose equivalents from internal exposures were underestimated due to the adoption of some of the foodchain parameter values originally selected for 239 Pu. Nonetheless, the ingestion pathway contributed significantly to the dose estimates for 90 Sr and 137 Cs, but contributed very much less than external exposures to the dose estimates for 60 Co. Therefore, the use of more appropriate values would not alter the identification of important radionuclides, pathways, target organs, and exposure modes in this analysis. 19 refs., 13 figs., 12 tabs

  8. 49 CFR 172.429 - POISON INHALATION HAZARD label.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 2 2010-10-01 2010-10-01 false POISON INHALATION HAZARD label. 172.429 Section... REQUIREMENTS, AND SECURITY PLANS Labeling § 172.429 POISON INHALATION HAZARD label. (a) Except for size and color, the POISON INHALATION HAZARD label must be as follows: ER22JY97.023 (b) In addition to complying...

  9. Methodology of radionuclides dis incorporation in people related to nuclear and radiological accidents

    International Nuclear Information System (INIS)

    Jimenez F, E. A.

    2014-01-01

    In this paper a classification of the radiological and nuclear accidents is presented, describing which the activities are, where they have occurred, their incidence and the learned lessons in these successes. The radiological accidents in which radioactive materials intervene can occur anywhere, and they are related to no controlled dangerous sources (abandoned, lost, stolen, or found sources), improper use of dangerous industrial and medical sources, exposition and contamination of people in general by an unknown origin, serious over expositions, menaces and willful misconduct, emergencies during transportation of radioactive material. A person can receive a dose of radiation from an external source, because of radioactive material placed on skin or on equipment, or because of ingestion or inhalation of radiological particles. The ingestion or the inhalation of radioactive material can cause an internal dose to the whole body or to a specific organ during a period of time. That is why a description of the processes of incorporation, the stages of incorporation and a description of the biokinetic models are also realized to understand the ingestion, transference and the excretion of the radioactive elements. In order to offer help to a victim of internal contamination, the dosimetric and medical diagnosis is very important. The most important techniques of dosimetric diagnosis are the dosimetry in vivo (cytogenetics and the counting in vivo of the whole body) and the bioassays. These techniques allow obtain data such as the radionuclide, the target organ, the absorbed dose, etc. At the same time, the doctor in charge must be attentive to the patients symptoms and their manifestation time, since they are an indicator, first, the patient suffered an irradiation, and second, of the range esteem of the received radiation dose. These are the parameters that are useful as criterion to decide if a person has to receive some treatment and select the methodologies that

  10. The speciation of radionuclides in sediments and soils. Part II. Studies with a sequential organic extraction procedure

    International Nuclear Information System (INIS)

    Voss, H.A.; Williams, G.A.; Cooper, M.B.

    1983-07-01

    A series of chemical extractions with a range of organic solvents has been performed to investigate the speciation of radionuclides in soil and sediment samples from the Mt. Brockman area in the Northern Territory. The major result is that of all the organic solvents used in the extractions, only acetic acid removes large proportions of the radionuclides 210 Pb (ca. 30-70%) and 226 Ra (10-55%) from the soil and sediment samples. The failure of the other organic solvents, and in particular dimethylformamide, to extract appreciable amounts of these radionuclides is taken to indicate that 210 Pb and 226 Ra are not present as discrete metal complexes of organic ligands. The overriding conclusion, that the acidic nature of the solvent is the most important property in releasing the bound radionuclides into solution, suggests that even under mildly acidic conditions encountered in the environment significant amounts of 210 Pb and 226 Ra may be released for transportation

  11. Granulometric determinations and inhalation dose assessment for atmospheric aerosol contaminated by {sup 137}Cs; Determinazioni granulometriche e valutazioni di dose da inalazione per aerosol atmosferico contaminato da {sup 137}CS

    Energy Technology Data Exchange (ETDEWEB)

    Castellani, C.M.; Luciani, A. [ENEA, Centro Ricerche `E. Clementel`, Bologna (Italy). Dip. Ambiente; Oliviero, L.; Donato, R. [ENEA, Centro Ricerche Saluggia, Vercelli (Italy). Dip. Ambiente

    1996-07-01

    During the redevelopment of Brescia freight-yard a measurement campaign of atmospheric aerosol was carried out: in fact a {sup 137}Cs ground contamination, caused by the permanence of wagons carrying iron materials contaminated by this radionuclide, had been found out. During the redevelopment phases of excavation and can filling the workers were exposed to the danger of radioactive aerosol inhalation. The aim of the measurement campaign was to test the aerosol sampling and granulometric analysis methodologies with their sensitivity related to the inhalation dose assessments. The results of both aerosuspended mass and activity, evaluated by means of a portable cascade impactor, are presented. The granulometries have been interpolated with a log normal distribution using an iterative routine minimizing the square deviation between the calculated and experimental data. The results related to the dose assessments are also presented. These evaluations have been carried out using both the granulometric information obtained and the more recent models (ICRP 66) both the total concentration data and the dose coefficients referring to the standard conditions of ICRP 68 and of the Italian law (D.Lgs. 230/95). Furthermore the significance and the reliability of the dose assessments referring to the different methodologies are discussed, also in relation to the possibility of using this sampling methodologies for other radionuclides and different exposure conditions.

  12. Development of long-lived radionuclide partitioning technology

    Energy Technology Data Exchange (ETDEWEB)

    Yoo, Jae Hyung; Lee, Eil Hee; Kim, Kwang Wook; Yang, Han Beom; Chung, Dong Yong; Lim, Jae Kwan; Shin, Young Jun; Kim, Heung Ho; Kown, Sun Gil; Kim, Young Hwan; Hwang, Doo Seung

    1996-07-01

    This study has been focused on the development of unit processes for partitioning in the 1st stage, and experimentally carried out to examine the separation characteristics and operation conditions on the following unit processes. (1) Removal of a small amount of uranium by extraction with TBP, (2) Removal of Zr and Mo and destruction of nitric acid by uranium by denitration with formic acid, (3) Co-precipitation of Am, Np and RE oxalic acid, (4) Dissolution and destruction of oxalate by hydrogen peroxide, (5) Co-extraction of Am, Np and RE by nitric acid, (8) Back-extraction of Np by oxalic acid, (9) Adsorption and elution of Cs and Sr by zeolite, and (10) Advanced separation of radionuclide by electrochemical REDOX method. The results obtained from each unit process will be use as the basic materials for the establishment of optimal partitioning and design of process equipment. (author). 46 refs., 54 tabs., 222 figs.

  13. Radionuclide contaminant analysis of small mammals at Area G, TA-54, 1994

    International Nuclear Information System (INIS)

    Biggs, J.; Bennett, K.; Fresquez, P.

    1995-09-01

    Small mammals were sampled at two waste burial sites (1 and 2) at Area G, TA-54 and a control site outside Area G (Site 3) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for 241 Am, 90 Sr, 238 Pu, 239 Pu, total U, and gamma spectroscopy (including 137 Cs). Significantly higher (parametric t-test at p = 0.05) levels of total U, 241 Am, 238 Pu, 239 Pu, and 40 K were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. The authors results show higher concentrations in pelts compared to carcasses which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had significantly higher (alpha = 0.05, F = 0.0095) total U concentrations in carcasses than Sites 2 and 3. Site 2 had significantly higher (alpha = 0.05, F = 0.0195) 239 Pu concentrations in carcasses than either Site 1 or Site 3. A significant difference in 90 Sr concentration existed between Sites 1 and 2 (alpha = 0.05, F = 0.0681) and concentrations of 40 K at Site 1 were significantly different from Site 3

  14. Radionuclide scanning

    International Nuclear Information System (INIS)

    Shapiro, B.

    1986-01-01

    Radionuclide scanning is the production of images of normal and diseased tissues and organs by means of the gamma-ray emissions from radiopharmaceutical agents having specific distributions in the body. The gamma rays are detected at the body surface by a variety of instruments that convert the invisible rays into visible patterns representing the distribution of the radionuclide in the body. The patterns, or images, obtained can be interpreted to provide or to aid diagnoses, to follow the course of disease, and to monitor the management of various illnesses. Scanning is a sensitive technique, but its specificity may be low when interpreted alone. To be used most successfully, radionuclide scanning must be interpreted in conjunction with other techniques, such as bone radiographs with bone scans, chest radiographs with lung scans, and ultrasonic studies with thyroid scans. Interpretation is also enhanced by providing pertinent clinical information because the distribution of radiopharmaceutical agents can be altered by drugs and by various procedures besides physiologic and pathologic conditions. Discussion of the patient with the radionuclide scanning specialist prior to the study and review of the results with that specialist after the study are beneficial

  15. Inhaled antibiotics for lower airway infections.

    Science.gov (United States)

    Quon, Bradley S; Goss, Christopher H; Ramsey, Bonnie W

    2014-03-01

    Inhaled antibiotics have been used to treat chronic airway infections since the 1940s. The earliest experience with inhaled antibiotics involved aerosolizing antibiotics designed for parenteral administration. These formulations caused significant bronchial irritation due to added preservatives and nonphysiologic chemical composition. A major therapeutic advance took place in 1997, when tobramycin designed for inhalation was approved by the U.S. Food and Drug Administration (FDA) for use in patients with cystic fibrosis (CF) with chronic Pseudomonas aeruginosa infection. Attracted by the clinical benefits observed in CF and the availability of dry powder antibiotic formulations, there has been a growing interest in the use of inhaled antibiotics in other lower respiratory tract infections, such as non-CF bronchiectasis, ventilator-associated pneumonia, chronic obstructive pulmonary disease, mycobacterial disease, and in the post-lung transplant setting over the past decade. Antibiotics currently marketed for inhalation include nebulized and dry powder forms of tobramycin and colistin and nebulized aztreonam. Although both the U.S. Food and Drug Administration and European Medicines Agency have approved their use in CF, they have not been approved in other disease areas due to lack of supportive clinical trial evidence. Injectable formulations of gentamicin, tobramycin, amikacin, ceftazidime, and amphotericin are currently nebulized "off-label" to manage non-CF bronchiectasis, drug-resistant nontuberculous mycobacterial infections, ventilator-associated pneumonia, and post-transplant airway infections. Future inhaled antibiotic trials must focus on disease areas outside of CF with sample sizes large enough to evaluate clinically important endpoints such as exacerbations. Extrapolating from CF, the impact of eradicating organisms such as P. aeruginosa in non-CF bronchiectasis should also be evaluated.

  16. Traces of natural radionuclides in animal food

    Energy Technology Data Exchange (ETDEWEB)

    Merli, Isabella Desan; Guazzelli da Silveira, Marcilei A. [Centro Universitário da FEI, São Bernardo do Campo (Brazil); Medina, Nilberto H. [Instituto de Física da USP, São Paulo (Brazil)

    2014-11-11

    Naturally occurring radioactive materials are present everywhere, e.g., in soil, air, housing materials, food, etc. Therefore, human beings and animals receive internal exposure from radioactive elements inside their bodies through breathing and alimentation. Gamma radiation has enough energy to remove an electron from the atom and compromise the rearrangement of electrons in the search for a more stable configuration which can disturb molecule chemical bonding. Food ingestion is one of the most common forms of radioisotopes absorption. The goal of this work is the measurement of natural gamma radiation rates from natural radioisotopes present in animal food. To determine the concentration of natural radionuclides present in animal food gamma-ray spectrometry was applied. We have prepared animal food samples for poultry, fish, dogs, cats and cattle. The two highest total ingestion effective doses observed refers to a sample of mineral salt cattle, 95.3(15) μSv/year, rabbit chow, with a value of 48(5) μSv/year, and cattle mineral salt, with a value of 69(7) μSv/year, while the annual total dose value from terrestrial intake radionuclide is of the order of 290 μSv/year.

  17. Traces of natural radionuclides in animal food

    Science.gov (United States)

    Merli, Isabella Desan; da Silveira, Marcilei A. Guazzelli; Medina, Nilberto H.

    2014-11-01

    Naturally occurring radioactive materials are present everywhere, e.g., in soil, air, housing materials, food, etc. Therefore, human beings and animals receive internal exposure from radioactive elements inside their bodies through breathing and alimentation. Gamma radiation has enough energy to remove an electron from the atom and compromise the rearrangement of electrons in the search for a more stable configuration which can disturb molecule chemical bonding. Food ingestion is one of the most common forms of radioisotopes absorption. The goal of this work is the measurement of natural gamma radiation rates from natural radioisotopes present in animal food. To determine the concentration of natural radionuclides present in animal food gamma-ray spectrometry was applied. We have prepared animal food samples for poultry, fish, dogs, cats and cattle. The two highest total ingestion effective doses observed refers to a sample of mineral salt cattle, 95.3(15) μSv/year, rabbit chow, with a value of 48(5) μSv/year, and cattle mineral salt, with a value of 69(7) μSv/year, while the annual total dose value from terrestrial intake radionuclide is of the order of 290 μSv/year.

  18. Traces of natural radionuclides in animal food

    International Nuclear Information System (INIS)

    Merli, Isabella Desan; Guazzelli da Silveira, Marcilei A.; Medina, Nilberto H.

    2014-01-01

    Naturally occurring radioactive materials are present everywhere, e.g., in soil, air, housing materials, food, etc. Therefore, human beings and animals receive internal exposure from radioactive elements inside their bodies through breathing and alimentation. Gamma radiation has enough energy to remove an electron from the atom and compromise the rearrangement of electrons in the search for a more stable configuration which can disturb molecule chemical bonding. Food ingestion is one of the most common forms of radioisotopes absorption. The goal of this work is the measurement of natural gamma radiation rates from natural radioisotopes present in animal food. To determine the concentration of natural radionuclides present in animal food gamma-ray spectrometry was applied. We have prepared animal food samples for poultry, fish, dogs, cats and cattle. The two highest total ingestion effective doses observed refers to a sample of mineral salt cattle, 95.3(15) μSv/year, rabbit chow, with a value of 48(5) μSv/year, and cattle mineral salt, with a value of 69(7) μSv/year, while the annual total dose value from terrestrial intake radionuclide is of the order of 290 μSv/year

  19. Personal exposure to inhalable cement dust among construction workers

    International Nuclear Information System (INIS)

    Peters, Susan; Kromhout, Hans; Thomassen, Yngvar; Fechter-Rink, Edeltraud

    2009-01-01

    A case study was carried out in 2006-2007 to assess the actual cement dust exposure among construction workers involved in a full-scale construction project and as a comparison among workers involved in various stages of cement and concrete production. Full-shift personal exposure measurements were performed for several job types. Inhalable dust and cement dust (based on analysis of elemental calcium) concentrations were determined. Inhalable dust exposures at the construction site ranged from 0.05 to 34 mg/m3, with a mean concentration of 1.0 mg/m3. For inhalable cement dust mean exposure was 0.3 mg/m3 (range 0.02-17 mg/m3). Reinforcement and pouring workers had the lowest average concentrations. Inhalable dust levels in the ready-mix and pre-cast concrete plants were, on average, below 0.5 mg/m3 for inhalable dust and below 0.2 mg/m3 for inhalable cement dust. Highest dust concentrations were measured in cement production, particularly during cleaning tasks (inhalable dust GM=55 mg/m3; inhalable cement dust GM=33 mg/m3) at which point the workers wore personal protective equipment. Elemental measurements showed highest but very variable cement percentages in the cement plant and very low percentages of cement during reinforcement work and pouring.

  20. First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations.

    Science.gov (United States)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2014-10-22

    No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric (137)Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12-23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric (137)Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models.

  1. First retrieval of hourly atmospheric radionuclides just after the Fukushima accident by analyzing filter-tapes of operational air pollution monitoring stations

    Science.gov (United States)

    Tsuruta, Haruo; Oura, Yasuji; Ebihara, Mitsuru; Ohara, Toshimasa; Nakajima, Teruyuki

    2014-01-01

    No observed data have been found in the Fukushima Prefecture (FP) for the time-series of atmospheric radionuclides concentrations just after the Fukushima Daiichi Nuclear Power Plant (FD1NPP) accident. Accordingly, current estimates of internal radiation doses from inhalation, and atmospheric radionuclide concentrations by atmospheric transport models are highly uncertain. Here, we present a new method for retrieving the hourly atmospheric 137Cs concentrations by measuring the radioactivity of suspended particulate matter (SPM) collected on filter tapes in SPM monitors which were operated even after the accident. This new dataset focused on the period of March 12–23, 2011 just after the accident, when massive radioactive materials were released from the FD1NPP to the atmosphere. Overall, 40 sites of the more than 400 sites in the air quality monitoring stations in eastern Japan were studied. For the first time, we show the spatio-temporal variation of atmospheric 137Cs concentrations in the FP and the Tokyo Metropolitan Area (TMA) located more than 170 km southwest of the FD1NPP. The comprehensive dataset revealed how the polluted air masses were transported to the FP and TMA, and can be used to re-evaluate internal exposure, time-series radionuclides release rates, and atmospheric transport models. PMID:25335435

  2. Drift-Scale Radionuclide Transport

    International Nuclear Information System (INIS)

    Houseworth, J.

    2004-01-01

    The purpose of this model report is to document the drift scale radionuclide transport model, taking into account the effects of emplacement drifts on flow and transport in the vicinity of the drift, which are not captured in the mountain-scale unsaturated zone (UZ) flow and transport models ''UZ Flow Models and Submodels'' (BSC 2004 [DIRS 169861]), ''Radionuclide Transport Models Under Ambient Conditions'' (BSC 2004 [DIRS 164500]), and ''Particle Tracking Model and Abstraction of Transport Process'' (BSC 2004 [DIRS 170041]). The drift scale radionuclide transport model is intended to be used as an alternative model for comparison with the engineered barrier system (EBS) radionuclide transport model ''EBS Radionuclide Transport Abstraction'' (BSC 2004 [DIRS 169868]). For that purpose, two alternative models have been developed for drift-scale radionuclide transport. One of the alternative models is a dual continuum flow and transport model called the drift shadow model. The effects of variations in the flow field and fracture-matrix interaction in the vicinity of a waste emplacement drift are investigated through sensitivity studies using the drift shadow model (Houseworth et al. 2003 [DIRS 164394]). In this model, the flow is significantly perturbed (reduced) beneath the waste emplacement drifts. However, comparisons of transport in this perturbed flow field with transport in an unperturbed flow field show similar results if the transport is initiated in the rock matrix. This has led to a second alternative model, called the fracture-matrix partitioning model, that focuses on the partitioning of radionuclide transport between the fractures and matrix upon exiting the waste emplacement drift. The fracture-matrix partitioning model computes the partitioning, between fractures and matrix, of diffusive radionuclide transport from the invert (for drifts without seepage) into the rock water. The invert is the structure constructed in a drift to provide the floor of the

  3. Proposal of a new model for dose calculation due to the inhalation of Ru-222, Ru-220 and their sons with brief half-life

    International Nuclear Information System (INIS)

    Mauricio, C.L.P.

    1982-06-01

    The consequences of the radiation interactions upon the human body are studied. In order to simulate by computer the radiation interaction of the atoms of radon and thoron atoms and their Sons with a brief half life inhaled with the cells, the compartimental dosimetric model is used. The metabolic pathway of those radionuclides is described by continuous medium dynamic differential equation. The energy transfer processes are seen in details. The individual retention function is determined by bio-analysis. The results of internal dosimetry are consistents with the new international recommendations from ICRP-32. (L.F.S.) [pt

  4. Evaluation of Inhaler Techniques Among Asthma Patients Seen in ...

    African Journals Online (AJOL)

    hanumantp

    Drug inhalation is an important and a common mode of .... to evaluate the use of inhaler technique among asthma patients in a .... The median duration of the use of the inhalers is 24 ..... Scalabrini A, Cukier A. Incorrect application technique of.

  5. Removal of radon by aeration: testing of various aeration techniques for small water works. For European Commission under Contract No FI4PCT960054 TENAWA project

    International Nuclear Information System (INIS)

    Salonen, L.; Mehtonen, J.; Turunen, H.; Mjoenes, L.; Hagberg, N.; Raff, O.

    2002-12-01

    Capability of various aeration techniques to remove radon from water in small waterworks was studied as a part of project (Treatment Techniques for Removing Natural Radionuclides from Drinking Water), which was carried out during 1997-1999 on a cost-shared basis (contract No. F14PCT960054) with The European Commission (CEC) under the supervision of the Directorate-General XII Radiation Protection Research Unit. In TENAWA project both laboratory and field experiments were performed in order to find reliable methods and equipment for removing natural radionuclides from ground water originating either from private wells or small waterworks. Because such techniques are more often needed in private households than at waterworks, the main emphasis of the research was aimed to solve the water treatment problems related to the private water supplies, especially bedrock wells. Radon was the most important radionuclide to be removed from water at waterworks whereas the removal of other radionuclides ( 234,238 U, 226,228 Ra, 210 Pb and 210 Po) was oft required from radonrich bedrock waters. The currently available methods and equipment were mainly tested during the field and laboratory experiments but the project was also aimed to find new materials, absorbents and membranes applicable for radionuclide removal from various types of ground waters (e.g. soft, hard, acidic). Because iron, manganese or organic occur in waters with radionuclides, their simultaneous removal was also studied. The project was divided into 13 work packages. In this report the results of the work package 2.2 are described. Elevated levels of radon and other natural radionuclides in European ground waters have been observed mainly in wide areas of the crystalline Scandinavian bedrock, especially in the granite rock areas of Finland and Sweden but also in more limited crystalline rock areas of Central and Southern Europe, Ukraine and Scotland. The radon removal efficiencies of different aeration methods

  6. Chapter 2. Radionuclides in the biosphere

    International Nuclear Information System (INIS)

    Toelgyessy, J.; Harangozo, M.

    2000-01-01

    This is a chapter of textbook of radioecology for university students. In this chapter authors deal with role of radionuclides in the biosphere. Chapter consists of next parts: (1) Natural radionuclides in biosphere; (2) Man-made radionuclides in the biosphere; (3) Ecologically important radionuclides; (4) Natural background; (5) Radiotoxicity and (6) Paths of transfer of radionuclides from the source to human

  7. Inhalation exposures during operations in spent fuel bays

    International Nuclear Information System (INIS)

    Dua, S.K.; Maniyan, C.G.; Kotrappa, P.

    1987-01-01

    Radioactive aerosols are generated during operations (transfer, cutting, storage and shipment of fuel) in spent fuel bays. A study has been carried out on the airborne concentration, size distribution and dissolution rate of aerosols to evaluate the inhalation exposure of the workers. Personal air samplers were used for the measurement of concentration of airborne radioactivity and an Andersen impactor for the particle size distribution. The dissolution rates of some of the collected samples in lung serum simulant were followed for a period of about 200 days. Analysis of the samples revealed the presence of 239 Pu, U, 90 Sr and 137 Cs. For all the radionuclides measured ( 239 Pu, U, 90 Sr, 137 Cs) 40% of the activity dissolved rapidly (half-time 1.2d), the remainder with a half-time of 155 d. Calculation of effective dose equivalent for this dissolution half-time and for 6.8μm AMAD aerosols was carried out using the method recommended in ICRP 30 and reported in literature. The annual effective dose equivalent of the workers, if no respirators are worn, worked out to be 8.9 mSv (890 mrem), the contribution from alpha emitters being about 91% of the total. (author)

  8. Health effects of internally deposited radionuclides

    International Nuclear Information System (INIS)

    Raabe, Otto G.

    2008-01-01

    A comparative evaluation has been conducted of the ionizing radiation dose-response relationships in both human and laboratory animal studies involving internal deposition of radionuclides including alpha-emitters 226 Ra, 238 Pu, 239 Pu, and 241 Am and beta-emitters 90 Sr, 90 Y and 144 Ce. Intake routes included inhalation, injection, and ingestion. The preeminent importance of dose rate was revealed in this analysis. The lifetime effects of the ionizing radiation from internal emitters are described by three-dimensional dose rate/ time/response surfaces that compete with other causes of death during an individual's lifetime. Using maximum likelihood survival regression methods, the characteristic logarithmic slope for cancer induction was found to be about negative one-third for alpha-emitters or about negative two-thirds for beta-emitters. The relative biological effectiveness (RBE) of alpha versus beta radiations for cancer induction is a strong function of dose rate, near one at high dose rates and greater than 20 at low dose rates. The cumulative dose required to yield any level of induced-cancer risk is less at lower dose rates than at higher dose rates showing an apparent inverse-dose effect (up to a factor of 10 for high LET alpha radiation and a factor of 2 for low LET beta radiation). The competing risks of death associated with radiation injury, radiation-induced cancer, and natural aging are graphically shown using three-dimensional illustrations. At the higher average dose rates the principal deleterious effects are those associated with radiation-induced injury while at intermediate average dose rates radiation-induced cancer predominates. At the lower average dose rates the long latency time required for radiation-induced cancer may exceed natural life span, yielding an apparent lifespan effective threshold for death associated with radiation-induced cancer for cumulative doses to the target tissue below from 1.1 to 1.4 Gy for alpha-emitters or below

  9. Health effects of internally deposited radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Raabe, Otto G., E-mail: ograabe@ucdavis.edu [California Univ., Davis, CA (United States). Center for Health and the Environment

    2008-07-01

    A comparative evaluation has been conducted of the ionizing radiation dose-response relationships in both human and laboratory animal studies involving internal deposition of radionuclides including alpha-emitters {sup 226}Ra, {sup 238}Pu, {sup 239}Pu, and {sup 241}Am and beta-emitters {sup 90}Sr, {sup 90}Y and {sup 144}Ce. Intake routes included inhalation, injection, and ingestion. The preeminent importance of dose rate was revealed in this analysis. The lifetime effects of the ionizing radiation from internal emitters are described by three-dimensional dose rate/ time/response surfaces that compete with other causes of death during an individual's lifetime. Using maximum likelihood survival regression methods, the characteristic logarithmic slope for cancer induction was found to be about negative one-third for alpha-emitters or about negative two-thirds for beta-emitters. The relative biological effectiveness (RBE) of alpha versus beta radiations for cancer induction is a strong function of dose rate, near one at high dose rates and greater than 20 at low dose rates. The cumulative dose required to yield any level of induced-cancer risk is less at lower dose rates than at higher dose rates showing an apparent inverse-dose effect (up to a factor of 10 for high LET alpha radiation and a factor of 2 for low LET beta radiation). The competing risks of death associated with radiation injury, radiation-induced cancer, and natural aging are graphically shown using three-dimensional illustrations. At the higher average dose rates the principal deleterious effects are those associated with radiation-induced injury while at intermediate average dose rates radiation-induced cancer predominates. At the lower average dose rates the long latency time required for radiation-induced cancer may exceed natural life span, yielding an apparent lifespan effective threshold for death associated with radiation-induced cancer for cumulative doses to the target tissue below from 1.1 to

  10. Processes for Removal and Immobilization of 14C, 129I, and 85Kr

    Energy Technology Data Exchange (ETDEWEB)

    Strachan, Denis M.; Bryan, Samuel A.; Henager, Charles H.; Levitskaia, Tatiana G.; Matyas, Josef; Thallapally, Praveen K.; Scheele, Randall D.; Weber, William J.; Zheng, Feng

    2009-10-05

    This is a white paper covering the results of a literature search and preliminary experiments on materials and methods to remove and immobilize gaseous radionuclided that come from the reprocessing of spent nuclear fuel.

  11. Processes for Removal and Immobilization of 14C, 129I, and 85Kr

    International Nuclear Information System (INIS)

    Strachan, Denis M.; Bryan, Samuel A.; Henager, Charles H.; Levitskaia, Tatiana G.; Matyas, Josef; Thallapally, Praveen K.; Scheele, Randall D.; Weber, William J.; Zheng, Feng

    2009-01-01

    This is a white paper covering the results of a literature search and preliminary experiments on materials and methods to remove and immobilize gaseous radionuclides that come from the reprocessing of spent nuclear fuel.

  12. Inhalation of {sup 210}Po and {sup 210}Pb from cigarette smoking in Poland

    Energy Technology Data Exchange (ETDEWEB)

    Skwarzec, B. E-mail: bosk@chemik.chem.univ.gda.pl; Ulatowski, J.; Struminska, D.I.; Borylo, A

    2001-07-01

    The carcinogenic effect of {sup 210}Po and {sup 210}Pb with respect to lung cancer is an important problem in many countries with very high cigarette consumption. Poland has one of the highest consumptions of cigarettes in the world. The results of {sup 210}Po determination on the 14 most frequently smoked brands of cigarettes which constitute over 70% of the total cigarette consumption in Poland are presented and discussed. Moreover, the polonium content in cigarette smoke was estimated on the basis of its activity in fresh tobaccos, ash, fresh filters and post-smoking filters. The annual effective doses were calculated on the basis of {sup 210}Po and {sup 210}Pb inhalation with the cigarette smoke. The results of this work indicate that Polish smokers who smoke one pack (20 cigarettes) per day inhale from 20 to 215 mBq of {sup 210}Po and {sup 210}Pb each. The mean values of the annual effective dose for smokers were estimated to be 35 and 70 {mu}Sv from {sup 210}Po and {sup 210}Pb, respectively. For persons who smoke two packs of cigarettes with higher radionuclide concentrations, the effective dose is much higher (471 {mu}Sv yr{sup -1}) in comparison with the intake in diet. Therefore, cigarettes and the absorption through the respiratory system are the main sources and the principal pathway of {sup 210}Po and {sup 210}Pb intake of smokers in Poland.

  13. Demonstration of radionuclides removal at the 105-N basin using the 3M system

    International Nuclear Information System (INIS)

    Hobart, S.A.; Hyman, M.

    1996-03-01

    A field demonstration of the Minnesota Mining and Manufacturing Company (3M) innovative Cs- and Sr-removal technology was undertaken to support deactivation of the Hanford Site's N Reactor. The field demonstration and laboratory studies performed by Pacific Northwest National Laboratory are documented in this report. The deactivation of N Reactor includes an aggressive schedule for removing water from the reactor's original fuel storage pool, known as N Basin. The plan for treating N Basin water involves particulate filtration, followed by further treatment at the Hanford Site's Effluent Treatment Facility (ETF) before the water is discharged to a permitted soil column. Prudence calls for developing a backup treatment plan in the event that ETF is not available to support the N Basin critical path schedule. The 3M technique uses membrane filters that are impregnated with chemical species to remove specific ions from water by ion exchange or selective reaction. Sodium titanate is used to remove Sr by ion exchange, and potassium-cobalt hexacyanoferrate (COHEX) is used to remove Cs by formation of cesium-cobalt ferrocyanide. As a result of this field test, the following recommendations are made: 3M technology should not be considered for removing Sr from N Basin water, although the technology merits consideration for Sr removal in waters that have relatively low Cs content; application of 3M technology by recirculation of basin water through 3M adsorption cartridges for removal of Cs-137 should be considered since it efficiently removes Cs and may be cost effective; additional pilot-scale tests should be performed to determine the capacity of COHEX for Cs-137 removal, if full-scale application is desired

  14. Biomass selection for biosorption study of 226 Ra and 137 Cd radionuclides

    International Nuclear Information System (INIS)

    Costa, Wilson Cervi da

    2003-01-01

    The main goal of this work was to verify the potentialities to apply the biosorption technique to synthetic and real solution containing 226 Ra and 137 Cs, utilizing the seaweed Sargassum sp. and the microorganisms Penicillium sp., Saccharomyces cerevisiae and Monoraphidium sp. Indeed, the screening of the most effective biomass to remove the radionuclides was also a central objective. 226 Ra was selected due to its high radiotoxicity and the fact that it can be assimilated and incorporated by living organism through substitution og Mg 2+ and Ca 2+ , two essential nutrients. On the other hand, the selection of 137 Cs, a radionuclide of medium toxicity, was due to its mobility in the environment, which increases the possibility to be assimilated by the organisms as the essential nutrients Na + and K + . (author)

  15. Personal exposure to inhalable cement dust among construction workers.

    Science.gov (United States)

    Peters, Susan; Thomassen, Yngvar; Fechter-Rink, Edeltraud; Kromhout, Hans

    2009-01-01

    Objective- A case study was carried out to assess cement dust exposure and its determinants among construction workers and for comparison among workers in cement and concrete production.Methods- Full-shift personal exposure measurements were performed and samples were analysed for inhalable dust and its cement content. Exposure variability was modelled with linear mixed models.Results- Inhalable dust concentrations at the construction site ranged from 0.05 to 34 mg/m(3), with a mean of 1.0 mg/m(3). Average concentration for inhalable cement dust was 0.3 mg/m(3) (GM; range 0.02-17 mg/m(3)). Levels in the ready-mix and pre-cast concrete plants were on average 0.5 mg/m(3) (GM) for inhalable dust and 0.2 mg/m(3) (GM) for inhalable cement dust. Highest concentrations were measured in cement production, particularly during cleaning tasks (inhalable dust GM = 55 mg/m(3); inhalable cement dust GM = 33 mg/m(3)) at which point the workers wore personal protective equipment. Elemental measurements showed highest but very variable cement percentages in the cement plant and very low percentages during reinforcement work and pouring. Most likely other sources were contributing to dust concentrations, particularly at the construction site. Within job groups, temporal variability in exposure concentrations generally outweighed differences in average concentrations between workers. 'Using a broom', 'outdoor wind speed' and 'presence of rain' were overall the most influential factors affecting inhalable (cement) dust exposure.Conclusion- Job type appeared to be the main predictor of exposure to inhalable (cement) dust at the construction site. Inhalable dust concentrations in cement production plants, especially during cleaning tasks, are usually considerably higher than at the construction site.

  16. Respirable versus inhalable dust sampling

    International Nuclear Information System (INIS)

    Hondros, J.

    1987-01-01

    The ICRP uses a total inhalable dust figure as the basis of calculations on employee lung dose. This paper was written to look at one aspect of the Olympic Dam dust situation, namely, the inhalable versus respirable fraction of the dust cloud. The results of this study will determine whether it is possible to use respirable dust figures, as obtained during routine monitoring to help in the calculations of employee exposure to internal radioactive contaminants

  17. Uranium removal from the water supply

    International Nuclear Information System (INIS)

    Miranzadeh, Mohammad Bagher.

    1996-01-01

    Uranium can be naturally occurring radionuclides that contaminate some potable water supplies. Uranium is found both in surface water and ground water supplies. The United States Environmental Protection Agency recently proposed a maximum contaminant of 20 micro gram/liter for uranium because of concerns about its association with kidney disease and cancer. uranium can be removed from the supply by strong base anion-resin. Exhausted resin is regenerated by sodium chloride solution. (Author)

  18. Economic considerations in the use of inhaled anesthetic agents.

    Science.gov (United States)

    Golembiewski, Julie

    2010-04-15

    To describe the components of and factors contributing to the costs of inhaled anesthesia, basis for quantifying and comparing these costs, and practical strategies for performing pharmacoeconomic analyses and reducing the costs of inhaled anesthetic agents. Inhaled anesthesia can be costly, and some of the variable costs, including fresh gas flow rates and vaporizer settings, are potential targets for cost savings. The use of a low fresh gas flow rate maximizes rebreathing of exhaled anesthetic gas and is less costly than a high flow rate, but it provides less control of the level of anesthesia. The minimum alveolar concentration (MAC) hour is a measure that can be used to compare the cost of inhaled anesthetic agents at various fresh gas flow rates. Anesthesia records provide a sense of patterns of inhaled anesthetic agent use, but the amount of detail can be limited. Cost savings have resulted from efforts to reduce the direct costs of inhaled anesthetic agents, but reductions in indirect costs through shortened times to patient recovery and discharge following the judicious use of these agents are more difficult to demonstrate. The patient case mix, fresh gas flow rates typically used during inhaled anesthesia, availability and location of vaporizers, and anesthesia care provider preferences and practices should be taken into consideration in pharmacoeconomic evaluations and recommendations for controlling the costs of inhaled anesthesia. Understanding factors that contribute to the costs of inhaled anesthesia and considering those factors in pharmacoeconomic analyses and recommendations for use of these agents can result in cost savings.

  19. Geomorphological applications of environmental radionuclides

    International Nuclear Information System (INIS)

    Quine, T.A.; Walling, D.

    1998-01-01

    Geomorphologists have shown increasing interest in environmental radionuclides since pioneering studies by Ritchie and McHenry in the USA and Campbell, Longmore and Loughran in Australia. Environmental radionuclides have attracted this interest because they provide geomorphologists with the means to trace sediment movement within the landscape. They, therefore, facilitate investigation of subjects at the core of geomorphology, namely the rates and patterns of landscape change. Most attention has been focussed on the artificial radionuclide caesium-137 ( 137 Cs) but more recently potential applications of the natural radionuclides lead-210 ( 210 Pb) and beryllium-7( 7 Be) have been investigated (Walling et al., 1995; Wallbrink and Murray, 1996a, 1996b). The origin, characteristics and applications of these radionuclides are summarised. These radionuclides are of value as sediment tracers because of three important characteristics: a strong affinity for sediment; a global distribution and the possibility of measurement at low concentration. Geomorphological applications of environmental radionuclides provide unique access to detailed qualitative data concerning landscape change over a range of timescales

  20. Know How to Use Your Asthma Inhaler

    Medline Plus

    Full Text Available ... for Control Triggers Indoors In the Workplace Outdoors Management Asthma Action Plan Flu Shots Inhalers Data, Statistics, ... How to Use Your Asthma Inhaler Recommend on Facebook Tweet Share Compartir You can control your asthma ...

  1. Foodstuffs, radionuclides, monitoring

    International Nuclear Information System (INIS)

    Denisikov, A.I.

    2000-01-01

    Radionuclide contamination of water and food stuffs as a result of the Chernobyl accident and permissible contents of 90 Sr and 137 Cs are considered in brief. A method of radiation monitoring of food stuffs and water for the radionuclides mentioned is suggested. The method permits employment of the simplest and cheapest radiometric equipment for analysis, whole the high degree of radionuclide concentration using fiber sorbents permits using the instrumentation without expensive shields against external radiation. A description of ion-exchange unit for radiation monitoring of liquid samples of food stuffs or water, is provided [ru

  2. The use of multiple respiratory inhalers requiring different inhalation techniques has an adverse effect on COPD outcomes

    Directory of Open Access Journals (Sweden)

    Bosnic-Anticevich S

    2016-12-01

    Full Text Available Sinthia Bosnic-Anticevich,1 Henry Chrystyn,2 Richard W Costello,3,4 Myrna B Dolovich,5 Monica J Fletcher,6 Federico Lavorini,7 Roberto Rodríguez-Roisin,8 Dermot Ryan,9,10 Simon Wan Yau Ming,2 David B Price2,11 1Woolcock Institute of Medical Research, School of Medical Sciences, University of Sydney and Sydney Local Health District, Sydney, NSW, Australia; 2Observational and Pragmatic Research Institute Pte Ltd, Singapore; 3RCSI Medicine, Royal College of Surgeons, 4RCSI Education & Research Centre, Beaumont Hospital, Beaumont, Dublin, Ireland; 5Department of Medicine, Respirology, McMaster University, ON, Canada; 6Education for Health, Warwick, UK; 7Department of Experimental and Clinical Medicine, University of Florence, Florence, Italy; 8Respiratory Institute, Hospital Clinic, Universitat de Barcelona, Barcelona, Spain; 9Optimum Patient Care, Cambridge, 10Centre for Population Health Sciences, University of Edinburgh, Edinburgh, 11Academic Primary Care, University of Aberdeen, Aberdeen, UK Background: Patients with COPD may be prescribed multiple inhalers as part of their treatment regimen, which require different inhalation techniques. Previous literature has shown that the effectiveness of inhaled treatment can be adversely affected by incorrect inhaler technique. Prescribing a range of device types could worsen this problem, leading to poorer outcomes in COPD patients, but the impact is not yet known. Aims: To compare clinical outcomes of COPD patients who use devices requiring similar inhalation technique with those who use devices with mixed techniques. Methods: A matched cohort design was used, with 2 years of data from the Optimum Patient Care Research Database. Matching variables were established from a baseline year of follow-up data, and two cohorts were formed: a “similar-devices cohort” and a “mixed-devices cohort”. COPD-related events were recorded during an outcome year of follow-up. The primary outcome measure was an

  3. Process for encapsulating radionuclides

    International Nuclear Information System (INIS)

    Brownell, L.E.; Isaacson, R.E.

    1976-01-01

    Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

  4. Inhalation drug delivery devices: technology update

    Directory of Open Access Journals (Sweden)

    Ibrahim M

    2015-02-01

    Full Text Available Mariam Ibrahim, Rahul Verma, Lucila Garcia-ContrerasDepartment of Pharmaceutical Sciences, College of Pharmacy, The University of Oklahoma Health Sciences Center, Oklahoma City, OK, USAAbstract: The pulmonary route of administration has proven to be effective in local and systemic delivery of miscellaneous drugs and biopharmaceuticals to treat pulmonary and non-pulmonary diseases. A successful pulmonary administration requires a harmonic interaction between the drug formulation, the inhaler device, and the patient. However, the biggest single problem that accounts for the lack of desired effect or adverse outcomes is the incorrect use of the device due to lack of training in how to use the device or how to coordinate actuation and aerosol inhalation. This review summarizes the structural and mechanical features of aerosol delivery devices with respect to mechanisms of aerosol generation, their use with different formulations, and their advantages and limitations. A technological update of the current state-of-the-art designs proposed to overcome current challenges of existing devices is also provided.Keywords: pulmonary delivery, asthma, nebulizers, metered dose inhaler, dry powder inhaler

  5. Inhaled ciclesonide versus inhaled budesonide or inhaled beclomethasone or inhaled fluticasone for chronic asthma in adults: a systematic review

    Directory of Open Access Journals (Sweden)

    Halpin David MG

    2006-06-01

    Full Text Available Abstract Background Ciclesonide is a new inhaled corticosteroids licensed for the prophylactic treatment of persistent asthma in adults. Currently beclomethasone dipropionate, budesonide and fluticasone propionate are the most commonly prescribed inhaled corticosteroids for the treatment of asthma but there has been no systematic review comparing the effectiveness and safety ciclesonide to these agents. We therefore aimed to systematically review published randomised controlled trials of the effectiveness and safety of ciclesonide compared to alternative inhaled corticosteroids in people with asthma. Methods We performed literature searches on MEDLINE, EMBASE, PUBMED, the COCHRANE LIBRARY and various Internet evidence sources for randomised controlled trials or systematic reviews comparing ciclesonide to beclomethasone or budesonide or fluticasone in adult humans with persistent asthma. Data was extracted by one reviewer. Results Five studies met the inclusion criteria. Methodological quality was variable. There were no trials comparing ciclesonide to beclomethasone. There was no significant difference between ciclesonide and budesonide or fluticasone on the following outcomes: lung function, symptoms, quality of life, airway responsiveness to a provoking agent or inflammatory markers. However, the trials were very small in size, increasing the possibility of a type II error. One trial demonstrated that the combined deposition of ciclesonide (and its active metabolite in the oropharynx was 47% of that of budesonide while another trial demonstrated that the combined deposition of ciclesonide (and its active metabolite in the oropharynx was 53% of that of fluticasone. One trial demonstrated less suppression of cortisol in overnight urine collection after ciclesonide compared to fluticasone (geometric mean fold difference = 1.5, P Conclusion There is very little evidence comparing CIC to other ICS, restricted to very small, phase II studies of low

  6. Removal of radionuclides from process streams, a series of applications

    International Nuclear Information System (INIS)

    Menetrez, M.Y.

    1987-01-01

    The extensive research performed on metal oxide adsorption, the adsorption phenomena and physical conditions of cationic adsorption on manganese dioxide in solution have demonstrated that above pH 3 cations are adsorbed by an order of affinity, and that the interaction is characterized by the pH dependence of the metal. The relationship of the zero point charge of pH and the solution ionic strength effects on interfacial surface potential and adsorption have been addressed. A system to produce MnO 2 fiber with a heavy MnO 2 loading was designed, constructed, and operated successfully. Extensive testing has been performed on the adsorption of radium, calcium, cadmium, cesium, cobalt, iron, and manganese on MnO 2 fiber. This testing entailed field work utilizing bleed stream tests of MnO 2 fiber cartridges and tests of loose MnO 2 fiber and resin in columns. Radium removal amounted to a level of 36.9 nanocuries per gram MnO 2 , or 2 microcuries on a single 10 inch MnO 2 fiber filter element. Removal of metals from solutions was demonstrated at various rates specific for each metal tested. The order of affinity of those metals tested and the combined effects of electrolytic solutions was compared to previous research. The analysis of radium in water was performed using a highly modified procedure which is included to specify the exact steps of the analytical method followed. This method has introduced innovations in equipment, technique, and the use of reagents. Results of a comparison of MnO 2 fiber to commercial water treatment media for the removal of cobalt and cesium is presented

  7. Ventricular dysfunction in children with obstructive sleep apnea: radionuclide assessment

    International Nuclear Information System (INIS)

    Tal, A.; Leiberman, A.; Margulis, G.; Sofer, S.

    1988-01-01

    Ventricular function was evaluated using radionuclide ventriculography in 27 children with oropharyngeal obstruction and clinical features of obstructive sleep apnea. Their mean age was 3.5 years (9 months to 7.5 years). Conventional clinical assessment did not detect cardiac involvement in 25 of 27 children; however, reduced right ventricular ejection fraction (less than 35%) was found in 10 (37%) patients (mean: 19.5 +/- 2.3% SE, range: 8-28%). In 18 patients wall motion abnormality was detected. In 11 children in whom radionuclide ventriculography was performed before and after adenotonsillectomy, right ventricular ejection fraction rose from 24.4 +/- 3.6% to 46.7 +/- 3.4% (P less than 0.005), and in all cases wall motion showed a definite improvement. In five children, left ventricular ejection fraction rose greater than 10% after removal of oropharyngeal obstruction. It is concluded that right ventricular function may be compromised in children with obstructive sleep apnea secondary to adenotonsillar hypertrophy, even before clinical signs of cardiac involvement are present

  8. Cromolyn Oral Inhalation

    Science.gov (United States)

    ... your doctor.Cromolyn oral inhalation helps to prevent asthma attacks (sudden episodes of shortness of breath, wheezing, and coughing) but will not stop an asthma attack that has already started. Your doctor will prescribe ...

  9. Olodaterol Oral Inhalation

    Science.gov (United States)

    ... in a class of medications called long-acting beta-agonists (LABAs). It works by relaxing and opening ... the inhaler upright with the yellow cap closed. Turn the clear base in the direction of the ...

  10. Ipratropium Oral Inhalation

    Science.gov (United States)

    ... with the clear end pointing upward. Place the metal canister inside the clear end of the inhaler. ... do not discard it in an incinerator or fire.Unneeded medications should be disposed of in special ...

  11. Inhaled Antibiotics in Reanimatology: Problem State and Development Prospects (Review

    Directory of Open Access Journals (Sweden)

    A. N. Kuzovlev

    2017-01-01

    Full Text Available Nosocomial pneumonia is the second most common nosocomial infection in critical care units and most common in ALV patients (9—27%. The purpose of this literature review is to discuss the latest domestic and foreign body of evidence concerning the use of inhaled antibiotics в critical care. Search for domestic publications (literature reviews, observation studies, double blind randomized studies was carried out in elibrary.ru database, for foreign — in PubMed. Database for the period of yrs. 2005—2017. The following search enquiries were used: «inhaled antibiotics», «nosocomial pneumonia», «inhaled tobramycin», «inhaled colistin». The analysis includes 67 publications of yrs. 2007—2017 and 1 publication of yr. 2000. The literature review includes drug descriptions, contemporary capabilities of inhaled antibiotic therapy for nosocomial pneumonia, the advantages and drawbacks of this method of treatment. Special attention is focused on the use of inhaled aminoglycosides and inhaled colistin during nosocomial pneumonia in critical care units.

  12. Radionuclide transfer from mother to embryo

    International Nuclear Information System (INIS)

    Toader, M.; Vasilache, R.A.; Scridon, R.; Toader, M.L.

    1998-01-01

    The transfer of radionuclides from mother to embryo is still a matter of high interest. Therefore, the relation was investigated between the amount of radionuclides in the embryo and the dietary intake of the mother, this for two scenarios: a recurrent intake of variable amounts of radionuclides, and a long-term intake of a relatively constant amount of radionuclides, the radionuclide being 137 Cs. In the first case, the amount of radionuclides present in the embryo increases with the age of the embryo and with the intake of the mother. In the second case, no correlation could be found between the age of the embryo and its radioactive content; only the correlation between the intake of the mother and the radionuclide content of the embryo remained. (A.K.)

  13. Radiological safety assessment of Thoron inhalation hazards during DDU handling at UMP, Trombay

    International Nuclear Information System (INIS)

    Shailesh, M.; Belhe, M.S.; Malti; Narayani, K.; Satpati, S.K.

    2012-01-01

    Uranium Extraction Division, Bhabha Atomic Research Centre, Mumbai has been producing nuclear grade uranium metal from Ammonium di-uranate received from IRE to meet the fuel requirement of research reactors of Bhabha Atomic Research Centre at Uranium Metal Plant (UMP) in Trombay. In UMP, uranium oxide powder (U 3 O 8 and UO 3 ) is first reduced to uranium dioxide in reduction reactor and is converted to uranium tetra fluoride in hydro fluorination reactor. After removing moisture and acid vapour in expulsion area, reduction of uranium tetrafluoride is carried out with magnesium in magnesio-thermic reduction (MTR) reactor, pure uranium metal ingot with magnesium fluoride slag is produced. Finally natural uranium ingot is separated from slag in ingot discharging area. However deeply depleted uranium (DDU) metal was produced from uranium oxide (reprocessed uranium) received from PREFRE, Tarapur, as a special campaign. External radiation hazards are not dominant during the processing of natural uranium in uranium metal Plant. However it was observed that during processing of DDU metal, external and internal hazards are significant because of daughter products of thoron. Inhalation dose due to thoron was found less during charging of UO 3 powder operation than ingot discharge operation because of pneumatic powder transport system used for charging operation. It is estimated that after introduction of new blower system in different powder handling operation areas, the potential effective inhalation dose due to thoron inhalation may get reduced by 60% - 80%

  14. Radionuclide diagnosis of emergency states

    International Nuclear Information System (INIS)

    Ishmukhametov, A.I.

    1985-01-01

    Solution of emergency state radionuclide diagnostics from the technical point of view is provided by the application of the mobile quick-operating equipment in combination with computers, by the use of radionuclides with acceptable for emergency medicine characteristics and by development of radionuclide investigation data propcessing express-method. Medical developments include the study of acute disease and injury radioisotope semiotics, different indication diagnostic value determining, comparison of the results, obtained during radionuclide investigation, with clinicolaboratory and instrumental data, separation of methodical complex series

  15. Nicotine Oral Inhalation

    Science.gov (United States)

    ... with a smoking cessation program, which may include support groups, counseling, or specific behavioral change techniques. Nicotine inhalation ... and pharmacist what prescription and nonprescription medications, vitamins, nutritional supplements, and herbal products you are taking or ...

  16. Anthropogenic radionuclides in the environment

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Q; Weng, J; Wang, J

    2007-11-15

    Studies of radionuclides in the environment have entered a new era with the renaissance of nuclear energy and associated fuel reprocessing, geological disposal of high-level nuclear wastes, and concerns about national security with respect to nuclear non-proliferation. This work presents an overview of anthropogenic radionuclide contamination in the environment, as well as the salient geochemical behavior of important radionuclides. We first discuss the following major anthropogenic sources and current development that contribute to the radionuclide contamination of the environment: (1) nuclear weapons program; (2) nuclear weapons testing; (3) nuclear power plants; (4) commercial fuel reprocessing; (5) geological repository of high-level nuclear wastes, and (6) nuclear accidents. Then, we summarize the geochemical behavior for radionuclides {sup 99}Tc, {sup 129}I, and {sup 237}Np, because of their complex geochemical behavior, long half-lives, and presumably high mobility in the environment. Biogeochemical cycling and environment risk assessment must take into account speciation of these redox-sensitive radionuclides.

  17. Radionuclide daughter inventory generator code: DIG

    International Nuclear Information System (INIS)

    Fields, D.E.; Sharp, R.D.

    1985-09-01

    The Daughter Inventory Generator (DIG) code accepts a tabulation of radionuclide initially present in a waste stream, specified as amounts present either by mass or by activity, and produces a tabulation of radionuclides present after a user-specified elapsed time. This resultant radionuclide inventory characterizes wastes that have undergone daughter ingrowth during subsequent processes, such as leaching and transport, and includes daughter radionuclides that should be considered in these subsequent processes or for inclusion in a pollutant source term. Output of the DIG code also summarizes radionuclide decay constants. The DIG code was developed specifically to assist the user of the PRESTO-II methodology and code in preparing data sets and accounting for possible daughter ingrowth in wastes buried in shallow-land disposal areas. The DIG code is also useful in preparing data sets for the PRESTO-EPA code. Daughter ingrowth in buried radionuclides and in radionuclides that have been leached from the wastes and are undergoing hydrologic transport are considered, and the quantities of daughter radionuclide are calculated. Radionuclide decay constants generated by DIG and included in the DIG output are required in the PRESTO-II code input data set. The DIG accesses some subroutines written for use with the CRRIS system and accesses files containing radionuclide data compiled by D.C. Kocher. 11 refs

  18. FUTURE STUDIES AT PENA BLANCA: RADIONUCLIDE MIGRATION IN THE VADOSE ZONE OF AN ALLUVIAL FAN

    Energy Technology Data Exchange (ETDEWEB)

    P. Goodell; J. Walton; P.J. Rodriguez

    2005-07-11

    The pathway to the accessible environment at Yucca Mountain contains volcanic rocks and alluvial fill. Transport properties in alluvial fill, specifically retardation and dispersivity, may be significant in determining the overall performance of the repository. Prior relevant studies, with the exception of the Nye County Tracer Test, are almost entirely in bedrock material. The proposed study will provide field data on radionuclide migration in alluvial material. High grade uranium ore was mined at the Nopal I deposit. This mined ore (60,000 tons) was moved in 1994 to its present site as open piles on an alluvial fan in the Boquilla Colorada Microbasin. Precipitation is approximately 20 cm/year, and has caused migration of radionuclides into the subsurface. We propose partial removal of an ore pile, excavation into the alluvial fan, sampling, and determination of radionuclide mobilities from the uranium decay chain. The proposed research would be taking advantage of a unique opportunity with a known time frame for migration.

  19. FUTURE STUDIES AT PENA BLANCA: RADIONUCLIDE MIGRATION IN THE VADOSE ZONE OF AN ALLUVIAL FAN

    International Nuclear Information System (INIS)

    Goodell, P.; Walton, J.; Rodriguez, P.J.

    2005-01-01

    The pathway to the accessible environment at Yucca Mountain contains volcanic rocks and alluvial fill. Transport properties in alluvial fill, specifically retardation and dispersivity, may be significant in determining the overall performance of the repository. Prior relevant studies, with the exception of the Nye County Tracer Test, are almost entirely in bedrock material. The proposed study will provide field data on radionuclide migration in alluvial material. High grade uranium ore was mined at the Nopal I deposit. This mined ore (60,000 tons) was moved in 1994 to its present site as open piles on an alluvial fan in the Boquilla Colorada Microbasin. Precipitation is approximately 20 cm/year, and has caused migration of radionuclides into the subsurface. We propose partial removal of an ore pile, excavation into the alluvial fan, sampling, and determination of radionuclide mobilities from the uranium decay chain. The proposed research would be taking advantage of a unique opportunity with a known time frame for migration

  20. Critical review: Radionuclide transport, sediment transport, and water quality mathematical modeling; and radionuclide adsorption/desorption mechanisms

    Energy Technology Data Exchange (ETDEWEB)

    Onishi, Y.; Serne, R.J.; Arnold, E.M.; Cowan, C.E.; Thompson, F.L. [Pacific Northwest Lab., Richland, WA (United States)

    1981-01-01

    This report describes the results of a detailed literature review of radionuclide transport models applicable to rivers, estuaries, coastal waters, the Great Lakes, and impoundments. Some representatives sediment transport and water quality models were also reviewed to evaluate if they can be readily adapted to radionuclide transport modeling. The review showed that most available transport models were developed for dissolved radionuclide in rivers. These models include the mechanisms of advection, dispersion, and radionuclide decay. Since the models do not include sediment and radionuclide interactions, they are best suited for simulating short-term radionuclide migration where: (1) radionuclides have small distribution coefficients; (2) sediment concentrations in receiving water bodies are very low. Only 5 of the reviewed models include full sediment and radionuclide interactions: CHMSED developed by Fields; FETRA SERATRA, and TODAM developed by Onishi et al, and a model developed by Shull and Gloyna. The 5 models are applicable to cases where: (1) the distribution coefficient is large; (2) sediment concentrations are high; or (3) long-term migration and accumulation are under consideration. The report also discusses radionuclide absorption/desorption distribution ratios and addresses adsorption/desorption mechanisms and their controlling processes for 25 elements under surface water conditions. These elements are: Am, Sb, C, Ce, Cm, Co, Cr, Cs, Eu, I, Fe, Mn, Np, P, Pu, Pm, Ra, Ru, Sr, Tc, Th, {sup 3}H, U, Zn and Zr.

  1. Probabilistic inhalation risk assessment due to radioactivity released from coal fired thermal power plants

    International Nuclear Information System (INIS)

    Tiwari, M.; Ajmal, P.Y.; Bhangare, R.C.; Sahu, S.K.; Pandit, G.G.

    2014-01-01

    This paper deals with assessment of radiological risk to the general public around in the neighborhood of a 1000 MWe coal-based thermal power plant. We have used Monte Carlo simulation for characterization of uncertainty in inhalation risk due to radionuclide escaping from the stack of thermal power plant. Monte Carlo simulation treats parameters as random variables bound to a given probabilistic distribution to evaluate the distribution of the resulting output. Risk assessment is the process that estimates the likelihood of occurrence of adverse effects to humans and ecological receptors as a result of exposure to hazardous chemical, radiation, and/or biological agents. Quantitative risk characterization involves evaluating exposure estimates against a benchmark of toxicity, such as a cancer slope factor. Risk is calculated by multiplying the carcinogenic slope factor (SF) of the radionuclide by the dose an individual receives. The collective effective doses to the population living in the neighborhood of coal-based thermal power plant were calculated using Gaussian plume dispersion model. Monte Carlo Analysis is the most widely used probabilistic method in risk assessment. The MCA technique treats any uncertain parameter as random variable that obeys a given probabilistic distribution. This technique is widely used for analyzing probabilistic uncertainty. In MCA computer simulation are used to combine multiple probability distributions associated with the dose and SF depicted in risk equation. Thus we get a probabilistic distribution for the risk

  2. Further investigations on removal of 134,137Cs from animal meat

    International Nuclear Information System (INIS)

    Il'enko, A.I.; Krapivko, T.P.

    1992-01-01

    This paper deals with the process of removing cesium radionuclides from the meat of ungulates and fish. The fish, boar and moose were contaminated after the 1986 accident at Chernobyl. The premise of this experiment was that saturation of the deactivating solution with potassium, a chemical analog of cesium, or with an absorbent such as kaolin, would promote faster and more complete washing out of radionuclides from the object to be deactivated. The conclusions reached were that increasing the frequency of changing the deactivating solution reduces with total deactivation time for the meat of ungulates, as well as for fish by almost two times. Moose meat is easier to deactivate that boar meat. The addition of potassium KMnO 4 to the basic solution significantly accelerates washing out of cesium radionuclides. Also, preliminary freezing of fish significantly increases the effectiveness of deactivation

  3. Chitosan-ferrocyanide sorbent for Cs-137 removal from mineralized alkaline media

    Energy Technology Data Exchange (ETDEWEB)

    Egorin, Andrei [Far Eastern Federal Univ., Vladivostok (Russian Federation); Institute of Chemistry FEBRAS, Vladivostok (Russian Federation); Ozyorsk Technical Institute MEPHI, Ozersk (Russian Federation); Tokar, Eduard [Far Eastern Federal Univ., Vladivostok (Russian Federation); Zemskova, Larisa [Institute of Chemistry FEBRAS, Vladivostok (Russian Federation)

    2016-11-01

    An organomineral sorbent based on mixed nickel-potassium ferrocyanide and chitosan to be used in removal of Cs-137 radionuclide from highly mineralized media with high pH has been fabricated. The synthesized sorbent was applied to remove Cs-137 from model solutions under static and dynamic conditions. The effects of contact time, pH, and presence of sodium ions and complexing agents in the process of Cs-137 removal have been investigated. The sorbent is distinguished by increased stability to the impact of alkaline media containing complexing agents, whereas the sorbent capacity in solutions with pH 11 exceeds 1000 bed volumes with the Cs-137 removal efficiency higher than 95%.

  4. The measurement of released radionuclides during TIG-Welding and Grinding

    Energy Technology Data Exchange (ETDEWEB)

    Reichelt, A.; Lehmann, K.-H. [Technical Inspection Agency of Southern Germany (TUEV Sueddeutschland), Subdepartment Environmental Radioactivity, Munich (Germany); Reineking, A. [Isotope Laboratory for Biological and Medical Research, Georg-August-University of Goettingen, Goettingen (Germany); Eder, E. [Government of Bavaria, State Ministry for State Development and Environmental Affairs, Munich (Germany)

    2000-05-01

    The radiological relevance of the TIG welding using thoriated tungsten electrodes has recently been proved by means of different studies. As a result of this the TUEV Sueddeutschland and the University of Goettingen have carried out special investigations concerning the release of radionuclides during TIG welding. The main emphasis of these investigations were the representativity of various sampling techniques, the influence of various parameters during welding as well as the determination of activity size distributions related to the aerodynamic diameter of the inhaled aerosols. The properties of the tungsten rods are improved through the addition of radioactive thorium. We investigated the radiation exposure by handling with thoriated tungsten welding rods. We investigated the different exposure pathways and determined the specific activity in dependence to the different types of welding rods. By carrying out surveys with the users, we determined the exposure pathways for the individual exposed persons: TIG - hand-welders', TIG 'machine-welders', labourers, other persons. We measured the activity concentration of the breathing air while welding, at grinding the electrodes and by staying in the rooms where usually it's welded. The size distribution of the aerosol-attached activity was determined with several kinds of impactors. The main emphasis was the comparison of the different sampling systems at the measuring of the activity concentration of the breathing air. Selective sampling by impactors: {center_dot} Berner-impactor, stationary {center_dot} Sierra-impactor, stationary {center_dot} Anderson-Imcaktor, stationary {center_dot} Marple-impactor, personal sampler Aerosol sampling by air samplers {center_dot} 5 personal air sampler {center_dot} 2 stationary sampler, ring face {center_dot} 2 stationary sampler, open face Rn-220-Measurements {center_dot} Thoron-monitor Determination of activitys on measuring filters {center_dot} alpha

  5. Feasibility Assessment of Cesium Removal using Microaglae

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ilgook; Ryu, Byung-Gon; Seo, Bum-Kyoung; Moon, Jei Kwon; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The aim of this work is to assess the feasibility of selected one of microalgae in the uptake of Cs+. The obtained results showed the maximum Cs+ removal by D. armatus SCK was 280μM indicating 70% removal efficiency. Also, D. armatus SCK could uptake Cs+ in the presence of K+, is particularly known to be transported into cells as an analog of Cs+ in freshwater condition. Recently, increased attention has been directed on the use of biological technologies for the removal of radionuclides as the cheap and eco-friendly alternative to the non-biological methods. Metal including radioactive compounds uptake by microorganisms can be occurred by metabolism –independent and/or -dependent processes. One involves biosorption based on the ability of microbial cells to bind dissolved metals; on the other involves bioaccumulation, which depends on the metabolic ability of cells to transport metals into the cytoplasm. The purpose of this work is to investigate the feasibility of microalgae in bioaccumulation system to remove cesium from solution. The effect of different environmental parameters on cesium removal was also examined.

  6. A whiff of death: fatal volatile solvent inhalation abuse.

    Science.gov (United States)

    Steffee, C H; Davis, G J; Nicol, K K

    1996-09-01

    Inhalation abuse of volatile solvents, previously known generically as "glue sniffing," is typically pursued by adolescents. A wide range of legal, easily obtained products containing volatile substances are available for abuse. We report two illustrative cases of fatal volatile substance abuse: gasoline sniffing in a 20-year-old man and aerosol propellant gas inhalation (aerosol air freshener) in a 16-year-old girl with underlying reactive airway disease. Although the ratio of deaths to nonfatal inhalation escapades is extremely low, volatile solvent abuse carries the risk of sudden death due to cardiac arrest after a dysrhythmia or vasovagal event, central nervous system respiratory depression, hypoxia and hypercapnia due to the techniques of inhalation, and other mechanisms. Investigation of the patient's substance abuse history, examination of the scene of death, and special toxicologic analyses are critical to identifying volatile substance inhalation abuse as the cause of death because anatomic autopsy findings will typically be nonspecific. Above all, physicians must suspect the diagnosis of volatile substance inhalation abuse, especially in any case of sudden death involving an otherwise healthy young person.

  7. Affinity of hydroxyapatite by radionuclides parent/child in 188Re/188W generator for radiotherapy

    International Nuclear Information System (INIS)

    Carrera D, A. A.; Badillo A, V.; Badillo A, V. E.; Monroy G, F.

    2009-10-01

    To assess the feasibility of using apatites as matrices of 188 W/ 188 Re generator is essential to obtain the distribution coefficients as much of parent radionuclide as child radionuclide in apatite, that is to say to know their affinity for the solid. It was selected the mineral species more representative as adsorbent, the hydroxyapatite Ca 10 (PO 4 ) 6 (OH) 2 it is known for its great capacity of ions retention and by presenting a large affinity for anionic species in their surface. In this paper we use a synthetic hydroxyapatite marketed by Bio-Rad. This paper presents the preliminary results regarding the affinity of hydroxyapatite for the anionic species tungstates (WO 4 2- ) and perrhenates (ReO 4 - in EDTA, as background electrolyte expressed as distribution coefficients between two immiscible phases obtained with the help of radioactive tracers 187 W and 188 Re respectively. The retention measures of these ions, traces show that Bio-Gel hydroxyapatite presents moderate values of distribution coefficients for anionic species of W(Vi) in EDTA 0.01 mol/L that are in the range p H 5 to 6.5; the parent radionuclide of generator 188 Re/ 188 W is fixed but not enough to consider it a good absorbent. By contrast, the fixation of perrhenate ions is virtually wiped as may be easily removed from a hydroxyapatite column packed with a saline solution. The influence of this saline solution in the removal of perrhenate ions is null practically. (Author)

  8. IVO's nuclide removal system takes to the road

    International Nuclear Information System (INIS)

    Tusa, E.H.

    1995-01-01

    The successful and routine use of IVO's treatment system for the removal of cesium from the evaporator concentrates at the Loviisa WER plant in Finland is described. The system uses a granular inorganic hexacyanoferate-based ion exchanger to separate cesium from liquid radioactive wastes. The compactness of the original systems at Loviisa suggested the development of a transportable unit. A combined nuclide removal system was created which included a highly efficient ultrafiltration unit to separate nearly all particulate material carrying radionuclides, as well as the cesium removal capability. A 20ft long container carrying the removal package was completed in 1994. This NUclide REmoval System (NURES) was used for the first time in January 1995 to purify liquid waste accumulating at training reactors in Estonia and has performed well. As an extension of nuclide removal, a process has been created to recover boron from liquid wastes. A system for boron recovery and nuclide removal has been designed for use at the Paks plant in Hungary. The removal process has been shown to improve the safety of final waste disposal compared with the alternative treatment by cementation because the cesium is very tightly bound into the ion exchange material. (UK)

  9. Inhaler technique maintenance: gaining an understanding from the patient's perspective.

    Science.gov (United States)

    Ovchinikova, Ludmila; Smith, Lorraine; Bosnic-Anticevich, Sinthia

    2011-08-01

    The aim of this study was to determine the patient-, education-, and device-related factors that predict inhaler technique maintenance. Thirty-one community pharmacists were trained to deliver inhaler technique education to people with asthma. Pharmacists evaluated (based on published checklists), and where appropriate, delivered inhaler technique education to patients (participants) in the community pharmacy at baseline (Visit 1) and 1 month later (Visit 2). Data were collected on participant demographics, asthma history, current asthma control, history of inhaler technique education, and a range of psychosocial aspects of disease management (including adherence to medication, motivation for correct technique, beliefs regarding the importance of maintaining correct technique, and necessity and concern beliefs regarding preventer therapy). Stepwise backward logistic regression was used to identify the predictors of inhaler technique maintenance at 1 month. In total 145 and 127 participants completed Visits 1 and 2, respectively. At baseline, 17% of patients (n = 24) demonstrated correct technique (score 11/11) which increased to 100% (n = 139) after remedial education by pharmacists. At follow-up, 61% (n = 77) of patients demonstrated correct technique. The predictors of inhaler technique maintenance based on the logistic regression model (X(2) (3, N = 125) = 16.22, p = .001) were use of a dry powder inhaler over a pressurized metered-dose inhaler (OR 2.6), having better asthma control at baseline (OR 2.3), and being more motivated to practice correct inhaler technique (OR 1.2). Contrary to what is typically recommended in previous research, correct inhaler technique maintenance may involve more than repetition of instructions. This study found that past technique education factors had no bearing on technique maintenance, whereas patient psychosocial factors (motivation) did.

  10. Treatment of heavy metals and radionuclides in groundwater and wastewater by magnetic separation

    International Nuclear Information System (INIS)

    Bradbury, D.; Elder, G.R.; Tucker, P.M.; Dunn, M.J.

    1992-01-01

    Removal of trace quantities of heavy metal or radionuclide contamination from solutions at high flow rate presents a considerable technical challenge. Low flow methods of treatment such as particle gravity settling require expensive large volume equipment, whereas traditional methods of filtration demand significant energy costs. Magnetic filtration can be used to provide a low cost method of solid-liquid separation at high flow rate, provided contaminants can be selectively bound to a magnetic solid particle. This paper describes recent progress with this technique including performance tests of composite materials produced to selectively remove specific contaminants such as cesium, uranium, lead, cadmium, and mercury from solution

  11. History of medical radionuclide production.

    Science.gov (United States)

    Ice, R D

    1995-11-01

    Radionuclide production for medical use originally was incidental to isotope discoveries by physicists and chemists. Once the available radionuclides were identified they were evaluated for potential medical use. Hevesy first used 32P in 1935 to study phosphorous metabolism in rats. Since that time, the development of cyclotrons, linear accelerators, and nuclear reactors have produced hundreds of radionuclides for potential medical use. The history of medical radionuclide production represents an evolutionary, interdisciplinary development of applied nuclear technology. Today the technology is represented by a mature industry and provides medical benefits to millions of patients annually.

  12. Inhaled antibiotics for lower respiratory tract infections: focus on ciprofloxacin.

    Science.gov (United States)

    Serisier, D J

    2012-05-01

    The administration of antibiotics by the inhaled route offers an appealing and logical approach to treating infectious respiratory conditions. Studies in the cystic fibrosis (CF) population have established the efficacy of this therapeutic concept and inhaled antibiotic therapy is now one of the pillars of management in CF. There are now a number of new inhaled antibiotic formulations that have shown impressive preliminary evidence for efficacy in CF and are commencing phase III efficacy studies. Translation of this paradigm into the non-CF bronchiectasis population has proven difficult thus far, apparently due to problems with tolerability of inhaled formulations. Inhaled versions of ciprofloxacin have shown good tolerability and microbiological efficacy in preliminary studies, suggesting that effective inhaled antibiotics are finally on the horizon for this previously neglected patient population. The increased use of long-term inhaled antibiotics for a wider range of non-CF indications presents risks to the broader community of greater antimicrobial resistance development that must be carefully weighed against any demonstrated benefits. Copyright 2012 Prous Science, S.A.U. or its licensors. All rights reserved.

  13. Inhaled antibiotics in non-cystic fibrosis bronchiectasis: A meta-analysis.

    Science.gov (United States)

    Xu, Li; Zhang, Fei; Du, Shuai; Yu, Qi; Chen, Lin; Long, Li-Hui; Li, Ya-Ming; Jia, Ai-Hua

    2016-09-01

    To evaluate the efficacy and safety of inhaled antibiotics for the treatment of non-cystic fibrosis bronchiectasis (NCFB). Pubmed, Cochrane library, Embase, Elsevier, OVID, Springerlink, Web of knowledge and NEJM were searched for randomized controlled trials (RCTs) on inhaled antibiotics in treatment of NCFB from inception until April 2015. Meta-analysis was conducted to assess the efficacy and safety of inhaled antibiotics in the treatment of NCFB. Twelve RCTs involving 1154 participants were included. They showed that inhaled antibiotics were more effective in reduction of sputum bacterial density, eradication of P. aeruginosa, prolonged time to exacerbation and reduction of new pathogens emergence with no significant difference in adverse events compared with control groups. However, we did not find significant benefits of inhaled antibiotics in reducing the risk of acute exacerbation, improving health-related quality of life and reduction of P. aeruginosa resistance. Moreover, inhaled antibiotics exerted a statistically significant reduction in FEV1%. Inhaled antibiotics may be an alternative pathway to inhibit airway inflammation with no more adverse events in patients with NCFB.

  14. Resorption of radionuclides through the surface of thermal burns and problems of decontamination

    International Nuclear Information System (INIS)

    Il'in, L.A.; Ivannikov, A.T.; Popov, B.A.; Parfenova, I.M.

    1981-01-01

    Resorption of sup(137)Cs, sup(89)Sr, sup(131)I, sup(241)Am during thermal burns of 1-3 degrees and choice of a decontamination method used simultaneously for decontamination and disinfection of burn wounds were studied. It is shown that a degree of burns effects in a certain form on skin penetrability: through burns of 1-2 degrees the resorption increases 1 5-3 times, through burns of the thir degree the resorption decreases slightly as compared to the resorption through intact skin. High efficiency of 3% soap solution for removing radionuclides from burn csurfae of skin has been established. For burns accompanied with the disturbance of epidermis integrality, when considerable absorption of radionuclides is possible, decontamination must be accomplished as soon and complete as possible [ru

  15. Characteristics of patients making serious inhaler errors with a dry powder inhaler and association with asthma-related events in a primary care setting

    Science.gov (United States)

    Westerik, Janine A. M.; Carter, Victoria; Chrystyn, Henry; Burden, Anne; Thompson, Samantha L.; Ryan, Dermot; Gruffydd-Jones, Kevin; Haughney, John; Roche, Nicolas; Lavorini, Federico; Papi, Alberto; Infantino, Antonio; Roman-Rodriguez, Miguel; Bosnic-Anticevich, Sinthia; Lisspers, Karin; Ställberg, Björn; Henrichsen, Svein Høegh; van der Molen, Thys; Hutton, Catherine; Price, David B.

    2016-01-01

    Abstract Objective: Correct inhaler technique is central to effective delivery of asthma therapy. The study aim was to identify factors associated with serious inhaler technique errors and their prevalence among primary care patients with asthma using the Diskus dry powder inhaler (DPI). Methods: This was a historical, multinational, cross-sectional study (2011–2013) using the iHARP database, an international initiative that includes patient- and healthcare provider-reported questionnaires from eight countries. Patients with asthma were observed for serious inhaler errors by trained healthcare providers as predefined by the iHARP steering committee. Multivariable logistic regression, stepwise reduced, was used to identify clinical characteristics and asthma-related outcomes associated with ≥1 serious errors. Results: Of 3681 patients with asthma, 623 (17%) were using a Diskus (mean [SD] age, 51 [14]; 61% women). A total of 341 (55%) patients made ≥1 serious errors. The most common errors were the failure to exhale before inhalation, insufficient breath-hold at the end of inhalation, and inhalation that was not forceful from the start. Factors significantly associated with ≥1 serious errors included asthma-related hospitalization the previous year (odds ratio [OR] 2.07; 95% confidence interval [CI], 1.26–3.40); obesity (OR 1.75; 1.17–2.63); poor asthma control the previous 4 weeks (OR 1.57; 1.04–2.36); female sex (OR 1.51; 1.08–2.10); and no inhaler technique review during the previous year (OR 1.45; 1.04–2.02). Conclusions: Patients with evidence of poor asthma control should be targeted for a review of their inhaler technique even when using a device thought to have a low error rate. PMID:26810934

  16. Effects of water treatment processes used at waterworks on natural radionuclide concentrations

    International Nuclear Information System (INIS)

    Haemaelaeinen, K.; Vesterbacka, P.; Maekelaeinen, I.; Arvela, H.

    2004-08-01

    The occurrence of uranium and other natural radionuclides in waters of waterworks and the effects of the conventional water treatment processes on radionuclide concentrations were investigated. Water samples were collected from 17 waterworks. Radionuclide concentrations of the collected samples were compared to the currently valid concentrations according to the Finnish regulation, ST guide 12.3. Similarly the measured concentrations were compared to the values presented in the 98/83/EC directive and in the Commission recommendation, 2001/928/Euratom. The guidelines based on chemical toxicity of uranium were also considered. This report presents a summary of the radionuclide concentrations in waters distributed by waterworks. Short-term and logn-term temporal variation of radionuclide levels in raw water were also investigated. Waterworks selected to this study used different kinds of raw water sources and a variety of water treatment processes. Water samples were collected from 46 water catchments which used groundwater in soil, artificial groundwater or groundwater in bedrock as a source of raw water. The most common water treatment used in these catchments was alkalization. Other treatment processes used were various types of filtrations (sand, anthracite, slow sand and membrane filtration) and aeration. Four of the catchments distributed water without treatment. Sampling was carried out in co-operation with local health inspectors and waterworks staff in spring 2002. Later that autumn, monitoring samples were collected from eight catchments. The maximum value for radon, presented in ST guide 12.3, was exceeded in three water catchments that used groundwater in bedrock as a source of raw water. No exceedings were found in those water catchments that use groundwater in soil or artificial groundwater. The limits of uranium and radium calculated from the total indicative dose (98/83/EC) were not exceeded but the guidelines for lead and polonium, given in the

  17. Clinical effectiveness of the Respimat® inhaler device in managing chronic obstructive pulmonary disease: evidence when compared with other handheld inhaler devices

    Directory of Open Access Journals (Sweden)

    et al

    2011-02-01

    Full Text Available Felix SF Ram1, Celso R Carvallho2, John White31School of Health and Social Services, Massey University, Auckland, New Zealand; 2Department of Physical Therapy, School of Medicine, University of São Paulo, Brazil; 3York Hospitals NHS Foundation Trust, York Hospital, York, UKObjectives: Medication for the management of chronic obstructive pulmonary disease (COPD may be delivered by a number of different inhaler devices. This study was undertaken to determine the clinical effectiveness of the Respimat® handheld inhaler device compared with other handheld inhaler devices for the delivery of medication in stable COPD.Methodology: A systematic review of high-quality randomized controlled clinical trials comparing Respimat with other inhaler devices using the same medication was performed. Studies were searched for in the Cochrane Central Register of Controlled Trials as well as other relevant electronic databases. Manufacturers of inhaled COPD medication were also contacted for potential trials.Results: Seven studies of high methodological quality with 3813 participants were included in the review. Three trials used Handihaler® as the comparator inhaler, three used a chlorofluorocarbon metered-dose inhaler (CFC-MDI, and one trial used a hydroflouroalkane (HFA-MDI. When Respimat was compared with Handihaler, the following reported outcomes were not significantly different: trough forced expiratory volume in 1 second (FEV1 (weighted mean difference [WMD] 0.01 L; P = 0.14, trough forced vital capacity (FVC (WMD 0.001 L: P = 0.88, peak FEV1 (WMD 0.01 L: P = 0.08, peak FVC (WMD 0.01 L: P = 0.55, morning peak expiratory flow rate (PEFR (WMD 5.06 L/min: P = 0.08, and evening PEFR (WMD 4.39 L/min: P = 0.15. Furthermore, there were no differences when Respimat was compared with Handihaler for risk of exacerbations (relative risk [RR] 0.94: P = 0.81, dry mouth (RR 1.57: P = 0.34, or nasopharyngitis (RR 1.42: P = 0.22. For Respimat compared with CFC-MDI, the

  18. Effects of p-xylene inhalation on axonal transport in the rat retinal ganglion cells

    Energy Technology Data Exchange (ETDEWEB)

    Padilla, S.S.; Lyerly, D.P. (Environmental Protection Agency, Research Triangle Park, NC (USA))

    1989-12-01

    Although the solvent xylene is suspected of producing nervous system dysfunction in animals and humans, little is known regarding the neurochemical consequences of xylene inhalation. The intent of this study was to determine the effect of intermittent, acute, and subchronic p-xylene exposure on the axonal transport of proteins and glycoproteins within the rat retinofugal tract. A number of different exposure regimens were tested ranging from 50 ppm for a single 6-hr exposure to 1600 ppm 6 hr/day, 5 days/week, for a total of 8 exposure days. Immediately following removal from the inhalation chambers rats were injected intraocularly with (35S)methionine and (3H)fucose (to label retinal proteins and glycoproteins, respectively) and the axonal transport of labeled macromolecules to axons (optic nerve and optic tract) and nerve endings (lateral geniculate body and superior colliculus) was examined 20 hr after precursor injection. Only relatively severe exposure regimens (i.e., 800 or 1600 ppm 6 hr/day, 5 days/week, for 1.5 weeks) produced significant reductions in axonal transport; there was a moderate reduction in the axonal transport of 35S-labeled proteins in the 800-ppm-treated group which was more widespread in the 1600 ppm-treated group. Transport of 3H-labeled glycoproteins was less affected. Assessment of retinal metabolism immediately after isotope injection indicated that the rate of precursor uptake was not reduced in either treatment group. Furthermore, rapid transport was still substantially reduced in animals exposed to 1600 ppm p-xylene and allowed a 13-day withdrawal period. These data indicate that p-xylene inhalation decreases rapid axonal transport supplied to the projections of the rat retinal ganglion cells immediately after cessation of inhalation exposure and that this decreased transport is still apparent 13 days after the last exposure.

  19. Effects of p-xylene inhalation on axonal transport in the rat retinal ganglion cells

    International Nuclear Information System (INIS)

    Padilla, S.S.; Lyerly, D.P.

    1989-01-01

    Although the solvent xylene is suspected of producing nervous system dysfunction in animals and humans, little is known regarding the neurochemical consequences of xylene inhalation. The intent of this study was to determine the effect of intermittent, acute, and subchronic p-xylene exposure on the axonal transport of proteins and glycoproteins within the rat retinofugal tract. A number of different exposure regimens were tested ranging from 50 ppm for a single 6-hr exposure to 1600 ppm 6 hr/day, 5 days/week, for a total of 8 exposure days. Immediately following removal from the inhalation chambers rats were injected intraocularly with [35S]methionine and [3H]fucose (to label retinal proteins and glycoproteins, respectively) and the axonal transport of labeled macromolecules to axons (optic nerve and optic tract) and nerve endings (lateral geniculate body and superior colliculus) was examined 20 hr after precursor injection. Only relatively severe exposure regimens (i.e., 800 or 1600 ppm 6 hr/day, 5 days/week, for 1.5 weeks) produced significant reductions in axonal transport; there was a moderate reduction in the axonal transport of 35S-labeled proteins in the 800-ppm-treated group which was more widespread in the 1600 ppm-treated group. Transport of 3H-labeled glycoproteins was less affected. Assessment of retinal metabolism immediately after isotope injection indicated that the rate of precursor uptake was not reduced in either treatment group. Furthermore, rapid transport was still substantially reduced in animals exposed to 1600 ppm p-xylene and allowed a 13-day withdrawal period. These data indicate that p-xylene inhalation decreases rapid axonal transport supplied to the projections of the rat retinal ganglion cells immediately after cessation of inhalation exposure and that this decreased transport is still apparent 13 days after the last exposure

  20. Inhaling habits among smokers of different types of cigarette

    Energy Technology Data Exchange (ETDEWEB)

    Wald, N.J.; Idle, M.; Boreham, J.; Bailey, A.

    1980-12-01

    Inhaling habits were studied in 1316 men who freely smoked their usual brands of cigarette. An index of inhaling was calculated for each person by dividing the estimated increase in carboxyhaemoglobin level from a standard number of cigarettes by the carbon monoxide yield of the cigarette smoked. Smokers of ventilated filter cigarettes inhaled 82% more than smokers of plain cigarettes (p less than 0.001) and those who smoked unventilated filter cigarettes inhaled 36% more (p less than 0.001). Cigarette consumption was similar among smokers of each type of cigarette. Assuming that the intake of tar and nicotine is proportional to the inhaling index, the intake in either group of filter cigarette smokers would have been less than that in plain cigarette smokers. Among smokers of unventilated cigarettes, however, the intake would not have been much less.

  1. Transfer of fallout radionuclides derived from Fukushima NPP accident: 1 year study on transfer of radionuclides through hydrological processes

    Science.gov (United States)

    Onda, Yuichi; Kato, Hiroaki; Patin, Jeremy; Yoshimura, Kazuya; Tsujimura, Maki; Wakahara, Taeko; Fukushima, Takehiko

    2013-04-01

    Previous experiences such as Chernobyl Nuclear Power Plant accident have confirmed that fallout radionuclides on the ground surface migrate through natural environment including soils and rivers. Therefore, in order to estimate future changes in radionuclide deposition, migration process of radionuclides in forests, soils, ground water, rivers should be monitored. However, such comprehensive studies on migration through forests, soils, ground water and rivers have not been conducted so far. Here, we present the following comprehensive investigation was conducted to confirm migration of radionuclides through natural environment including soils and rivers. 1)Study on depth distribution of radiocaesium in soils within forests, fields, and grassland 2)Confirmation of radionuclide distribution and investigation on migration in forests 3)Study on radionuclide migration due to soil erosion under different land use 4)Measurement of radionuclides entrained from natural environment including forests and soils 5)Investigation on radionuclide migration through soil water, ground water, stream water, spring water under different land use 6)Study on paddy-to-river transfer of radionuclides through suspended sediments 7)Study on river-to-ocean transfer of radionuclides via suspended sediments 8)Confirmation of radionuclide deposition in ponds and reservoirs

  2. Bone tumors induced by inhalation of 238PuO2 in dogs

    International Nuclear Information System (INIS)

    Park, J.F.; Lund, J.E.; Ragan, H.A.; Hackett, P.L.; Frazier, M.E.

    1976-01-01

    Plutonium-238, an alpha-emitting radionuclide, is used as a heat source in thermoelectric power generators such as have been employed on lunar expeditions of communications satellites and in cardiac pacemakers. It has an 86.4 year half-life and emits 5.5 MeV alpha particles. Beagle dogs were given single 10 to 30 minute exposures to 238 PuO 2 aerosols to study the long-term translocation of plutonium and biologicl effects. Dogs with a terminal body burden ranging from 7 to 260 MuCi were euthanized due to respiratory insufficiency related to plutonium-induced pneumonitis during the first 3 years after exposure. Nine of the 11 dogs euthanized during the 4 to 6 year postexposure period had osteosarcomas. The terminal plutonium body burden in the tumor-bearing dogs ranged from 0.5 to 2.6 muCi with 30 to 55 percent of the plutonium in the skeleton. Experiments are in progress to further define the dose-effect relationship of inhaled 238 PuO 2 and investigate the mechanisms of plutonium-induced neoplasia

  3. Opportunities for inhaler device selection in elderly patients with asthma or COPD

    Directory of Open Access Journals (Sweden)

    Barrons R

    2015-12-01

    Full Text Available Robert Barrons,1 James Wheeler,2 J Andrew Woods1 1Wingate University School of Pharmacy, Wingate, NC, USA; 2University of Tennessee Health Science Center, Nashville, TN, USA Abstract: An anticipated surge in the elderly population will be accompanied by a rise in aging patients with asthma or COPD. Clinician selection of inhalers needs to address the unique challenges to elderly patients. These challenges to the use of inhalers include diminished physical and cognitive abilities, as well as cost reimbursement issues associated with polypharmacy and the Medicare gap. Clinicians should consider patient preferences for an inhaler device that provides ease of administration, and addresses conveniences such as portability, visual, and auditory indicators of dosing completion. The addition of spacer devices resolves hand-breath coordination difficulty with pressurized metered dose inhalers, but reduces overall inhaler convenience. Soft mist inhalers (Respimat® improve ease of administration, but use may be limited by cost and formulary availability. Multiple dose dry powder inhalers provide convenience and simplified use by requiring only one to two steps prior to administration, but concerns of peak inspiratory flow requirements remain among patients with advanced age and severity of COPD. If unaddressed, these challenges to inhaler selection contribute to inappropriate use of inhalers in 41% to 69% of patients, accompanied by at least 51% non-adherence to treatment. Clinicians must first avail themselves of reputable educational resources regarding new inhaler developments and administration, for competent patient instruction. Patient education should include a checklist of inhaler technique, with physical demonstration of each device by the patient and provider. Device demonstration significantly improves inhaler technique and identifies the need for nebulization therapy. Clinician and patient knowledge of available inhalers and their

  4. Inhalation of uranium ores

    International Nuclear Information System (INIS)

    Stuart, B.O.; Jackson, P.O.

    1975-01-01

    In previous studies the biological dispositions of individual long-lived alpha members of the uranium chain ( 238 U, 234 U and 230 Th) were determined during and following repeated inhalation exposures of rats to pitchblende (26 percent U 3 O 8 ) ore. Although finely dispersed ore in secular equilibrium was inhaled, 230 Th/ 234 U radioactivity ratios in the lungs rose from 1.0 to 2.5 during 8 weeks of exposures and increased to 9.2 by four months after cessation of exposures. Marked non-equilibrium levels were also found in the tracheobronchial lymph nodes, kidneys, liver, and femur. Daily exposures of beagle dogs to high levels of this ore for 8 days resulted in lung 230 Th/ 234 U ratios of >2.0. Daily exposures of dogs to lower levels (0.1 mg/1) for 6 months, with sacrifice 15 months later, resulted in lung and thoracic lymph node 230 Th/ 234 U ratios ranging from 3.6 to 9 and nearly 7, respectively. The lungs of hamsters exposed to carnotite (4 percent U 3 O 8 ) ore in current lifespan studies show 230 Th/ 234 U ratios as high as 2.0 during daily inhalation of this ore in secular equilibrium. Beagle dogs sacrificed after several years of daily inhalations of the same carnotite ore plus radon daughters also showed marked non-equilibrium ratios of 230 Th/ 234 U, ranging from 5.6 to 7.4 in lungs and 6.2 to 9.1 in thoracic lymph nodes. This pattern of higher retention of 230 Th than 234 U in lungs, thoracic lymph nodes, and other tissues is thus consistent for two types of uranium ore among several species and suggests a reevaluation of maximum permissible air concentrations of ore, currently based only on uranium content

  5. Inhalant abuse of computer cleaner manifested as angioedema.

    Science.gov (United States)

    Kurniali, Peter C; Henry, Letitia; Kurl, Rita; Meharg, Joseph V

    2012-01-01

    Inhalant abuse is the intentional inhalation of chemical vapors or volatile substance to achieve a euphoric effect. Although no statistical data are reported yet, inhalant abuse is potentially life-threatening and has resulted in a wide range of toxic effects such as central nervous system depression, seizures, aspiration, cardiac arrhythmia, asphyxiation, hypoxia, metabolic acidosis, and sudden death among others. We are reporting a 25-year-old white man who was brought to the emergency department after inhaling aerosolized computer-cleaning spray composed of difluoroethane. He was found to have marked upper and lower lip facial swelling consistent with angioedema. The patient also had a prolonged QT interval, mild inspiratory stridor, but no urticaria. In this case, we believe the difluoroethane-related angioedema represents either idiopathic or bradykinin-induced angioedema.

  6. Inhaled plutonium nitrate in dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.

    1987-01-01

    The major objective of this project is to determine dose-effect relationships of inhaled plutonium nitrate in dogs to aid in predicting health effects of accidental exposure in man. For lifespan dose-effect studies, beagle dogs were given a single inhalation exposure to 239 Pu(NO 3 ) 4 , in 1976 and 1977. The earliest biological effect was on the hematopoietic system; lymphopenia and neutropenia occurred at the two highest dose levels. They have also observed radiation pneumonitis, lung cancer, and bone cancer at the three highest dose levels. 1 figure, 3 tables

  7. Inhaled plutonium nitrate in dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.

    1986-01-01

    The major objective of this project is to determine dose-effect relationships of inhaled plutonium nitrate in dogs to aid in predicting health effects of accidental exposure in man. For lifespan dose-effect studies, beagle dogs were given a single inhalation exposure to 239 Pu(NO 3 ) 4 , in 1976 and 1977. The earliest biological effect was on the hematopoietic system; lymphopenia and neutropenia occurred at the two highest dose levels. The authors have also observed radiation pneumonitis, lung cancer, and bone cancer at the three highest dose levels. 1 figure, 4 tables

  8. Inhaled plutonium nitrate in dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.

    1982-01-01

    The major objective of this project is to determine dose-effect relationships of inhaled plutonium nitrate in dogs to aid in the prediction of health effects of accidental exposure in man. For lifespan dose-effect studies, beagle dogs were given a single inhalation exposure to 239 Pu(NO 3 ) 4 , in 1976 and 1977. The earliest biological effect was on the hematopoietic system; as described in previous Annual Reports, lymphopenia and neutropenia occurred at the two highest dose levels. Radiation pneumonitis, lung cancer, and bone cancer have been observed at the highest dose levels

  9. On the contents of some radionuclides in precipitation (deposits) of Yerevan city, Armenia

    International Nuclear Information System (INIS)

    Ananyan, V.; Appleby, P.; Danagulyan, A.; Nalbandyan, A.

    2004-01-01

    Biosphere is exposed to cosmic and α -, β -, γ -radiation of numerous radionuclides dispersed in rocks, groundwater, terrestrial water of rivers, seas and oceans, air and biota. The main components of natural radiation are 40 K, 238 U, 232 Th and radioactive products of their decay. The goal of this investigation was to determine radionuclide composition of atmospheric precipitation (deposits) of Yerevan city. For sample collection we used sedimentation method, which covers all deposits on 1 m 2: admixtures, dust and sand fractions during wind (precipitation deposits). The dish made of neutral material (50 x 50 cm) was positioned at a height 1,5 m in a selected sampling site. The bottom of the dish was underlain by filtering paper. The samples were taken monthly. After deposit evaporation and ashing at 450 degree C the deposits were weighed. Total weight of such samples made 41 g for 2000 (12 months). For measurements one sample per season was selected (totally 4 samples). Radionuclide measurements were done on a low-background gamma-spectrometer with Hp Ge semiconductor detector. The exposures of sample measurement and background made 117,34 h each. The sample was positioned close to the detector. After removal of background, radionuclide concentrations were determined. Concentrations of all isotopes of uranium family (234 Th,214 Pb, 214 Bi), except 210 Pb in sample are similar (within the limits of error), so in natural environment they stay in equilibrium. The same is relevant also to radionuclides of thorium family. Concentrations of 210 Pb are almost threefold higher, this deserving further detailed research. Among the remaining isotopes, contents of 40 K are the highest as it greatly contributes to natural radioactive background (N RB). Concentrations of 137 Cs were minimal, as this radionuclide derives only from global man-made environmental pollution. Thus, the results have revealed the radionuclide composition of the sample of atmospheric deposits in

  10. Conditions and processes affecting radionuclide transport

    Science.gov (United States)

    Simmons, Ardyth M.; Neymark, Leonid A.

    2012-01-01

    Characteristics of host rocks, secondary minerals, and fluids would affect the transport of radionuclides from a previously proposed repository at Yucca Mountain, Nevada. Minerals in the Yucca Mountain tuffs that are important for retarding radionuclides include clinoptilolite and mordenite (zeolites), clay minerals, and iron and manganese oxides and hydroxides. Water compositions along flow paths beneath Yucca Mountain are controlled by dissolution reactions, silica and calcite precipitation, and ion-exchange reactions. Radionuclide concentrations along flow paths from a repository could be limited by (1) low waste-form dissolution rates, (2) low radionuclide solubility, and (3) radionuclide sorption onto geological media.

  11. Influence of lavage therapy on the distribution patterns of inhaled, relatively insoluble particles in the lung

    International Nuclear Information System (INIS)

    Snipes, M.B.; Runkle, G.E.; Muggenburg, B.A.

    1977-01-01

    Four Beagle dogs were exposed by inhalation to a polydisperse fused aluminosilicate aerosol labeled with 147 Pm and 169 Yb. The left or right lung of each dog was lavaged one or five times to remove a portion of the lung burden. Autoradiographic and computer techniques were combined to determine the dispersion pattern of radioactive particles still in the lung after lavage therapy. For all four dogs the dispersion pattern of particles in the lung was the same for the lavaged and non-lavaged lung lobes. Examination of the autoradiograms indicated that lavage therapy did not preferentially remove particles from some areas of the lung. The similarity of particle dispersion patterns suggests that a minimal relocation of particles in lung results from lavage therapy

  12. Radionuclide contaminant analysis of small mammals at Area G, Technical Area 54, 1996 (with cumulative summary for 1994--1996)

    International Nuclear Information System (INIS)

    Biggs, J.R.; Bennett, K.D.; Fresquez, P.R.

    1997-07-01

    Small mammals were sampled at two waste burial sites at Area G, Technical Area (TA) 54 and a control site within the proposed Area G expansion area in 1996 to (1) identify radionuclides that are present within rodent tissues at waste burial sites, (2) to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and (3) to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of approximately five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for 241 Am, 90 Sr, 238 Pu, 239 Pu, total U, 137 Cs, and 3 H. Higher levels of total U, 241 Am, 238 Pu, and 239 Pu were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. Due to low sample sizes in total number of animals captured, statistical analysis to compare site to site could not be conducted. However, mean concentrations of total U, 238 Pu, 239 Pu, and 137 Cs in rodent carcasses were higher at Site 1 than site 2 or the Control Site and 241 Am was higher at Site 2 than Site 1 or the Control Site

  13. Phyto-inhalation for treatment of complications of acute respiratory viral diseases

    Directory of Open Access Journals (Sweden)

    I.B. Ershova

    2017-03-01

    Full Text Available Inhalations (inhalation of medicinal substances are one of the effective ways to treat upper respiratory tract diseases and colds. Inhalation therapy is used to treat rhinitis, sinusitis, tonsillitis, pharyngitis, laryngitis, bronchitis and pneumonia, which can be complications of acute respiratory viral infections. The main rules of inhalation are as follows to conduct the procedure better after 1.5 hours after eating; clothes should not impede breathing; the procedure can be carried out only while sitting or standing; solution for the inhaler for treatment of bronchitis should be fresh; it is necessary to strictly keep the prescribed dosage; the time of the procedure should also be respected — usually it is from 1 to 4 minutes, sometimes for adults up to 10 minutes, for children the inhalation period is shorter — 1–2 minutes. Contraindications to inhalation are body temperature above 37.5 degrees; propensity to nasal blee­ding in a patient; propensity to increased arterial pressure, with cardiovascular failure; purulent inflammation of the tonsils; respiratory failure. The procedure should be stopped immediately in case of appearance of adverse symptoms such as shortness of breath, dizziness, difficulty in breathing. Therefore, inhalations must be prescribed by a doctor after examination of a patient. During inhalations in rhinitis, you should try to inhale the vapor through the nose. For effective treatment of rhinitis, inhalations from conife­rous plants are very suitable: fir, pine, juniper, larch, from steamed dried chamomile flowers, mint, and blackberry leaves. Honey inhalations can be used for the treatment of acute and chronic diseases of the upper respiratory tract (tonsillitis, pharyngitis, laryngitis and tracheitis. Medical herbal inhalation for children should be carried out from the age of two years. This must be done under the constant supervision of an adult. Leaves of coniferous trees: pine, fir, if or juniper, cedar

  14. Does inhalation injury predict mortality in burns patients or require redefinition?

    Directory of Open Access Journals (Sweden)

    Youngmin Kim

    Full Text Available Inhalation injury is known to be an important factor in predicting mortality in burns patients. However, the diagnosis is complicated by the heterogeneous presentation and inability to determine the severity of inhalation injury. The purpose of this study was to identify clinical features of inhalation injury that affect mortality and the values that could predict the outcome more precisely in burns patients with inhalation injury. This retrospective observational study included 676 burns patients who were over 18 years of age and hospitalized in the Burns Intensive Care Unit between January 2012 and December 2015. We analyzed variables that are already known to be prognostic factors (age, percentage of total body surface area (%TBSA burned, and inhalation injury and factors associated with inhalation injury (carboxyhemoglobin and PaO2/FiO2 [PF] ratio by univariate and multivariate logistic regression. Age group (odds ratio [OR] 1.069, p<0.001, %TBSA burned (OR 1.100, p<0.001, and mechanical ventilation (OR 3.774, p<0.001 were identified to be significant predictive factors. The findings for presence of inhalation injury, PF ratio, and carboxyhemoglobin were not statistically significant in multivariate logistic regression. Being in the upper inhalation group, the lower inhalation group, and having a PF ratio <100 were identified to be significant predictors only in univariate logistic regression analysis (OR 4.438, p<0.001; OR 2.379, p<0.001; and OR 2.765, p<0.001, respectively. History and physical findings are not appropriate for diagnosis of inhalation injury and do not predict mortality. Mechanical ventilation should be recognized as a risk factor for mortality in burns patients with inhalation injury.

  15. Radiation Doses to Members of the U.S. Population from Ubiquitous Radionuclides in the Body: Part 3, Results, Variability, and Uncertainty

    International Nuclear Information System (INIS)

    Watson, David J.; Strom, Daniel J.

    2011-01-01

    This paper is part three of a three-part series investigating annual effective doses to residents of the United States from intakes of ubiquitous radionuclides, including radionuclides occurring naturally, radionuclides whose concentrations are technologically enhanced, and anthropogenic radionuclides. The radionuclides of interest are the 238 U series (14 nuclides), the actinium series (headed by 235 U; 11 nuclides), and the 232 Th series (11 nuclides); primordial radionuclides 87 Rb and 40 K; cosmogenic and fallout radionuclides 14 C and 3 H; and purely anthropogenic radionuclides 137 Cs- 137m Ba, 129 I and 90 Sr- 90 Y. This series of papers explicitly excludes intakes from inhaling 222 Rn, 220 Rn, and their short-lived decay products; it also excludes intakes of radionuclides in occupational and medical settings. Part one reviewed, summarized, characterized, and grouped all published and some unpublished data for U.S. residents on ubiquitous radionuclide concentrations in tissues and organs. Part two described the methods used to organize the data collected in part one and segregate it into the ages and genders defined by the study, imputed missing values from the existing data, apportioned activity in bone, and imputed activity in hollow organ contents and the remainder of the body. This paper estimates equivalent doses to target tissues from source regions and maps target tissues to lists of tissues with International Commission on Radiation Protection (ICRP) tissue-weighting factors or to surrogate tissue regions when there is no direct match. Effective doses, using ICRP tissue-weighting factors recommended in 1977, 1990, and 2007, are then calculated, and an upper bound of variability of the effective dose is estimated by calculating the average coefficients of variation (CV), assuming all variance is due to variability. Most of the data were for adult males, whose average annual effective dose is estimated to be 337 (micro)Sv y -1 (CV = 0.65, geometric mean

  16. Knowledge of spacer device, peak flow meter and inhaler technique ...

    African Journals Online (AJOL)

    Background: Metered dose inhalers are cornerstone in effective management of bronchial asthma when correctly used. Most studies hitherto have focused on assessing patient's knowledge of inhaler technique. We sought to assess the knowledge of inhaler technique, spacer device and peak flow meter among doctors and ...

  17. A model for radionuclide Migration in Urban Environment and Drainage Systems

    International Nuclear Information System (INIS)

    Garcia, E.; Gallego, E.; Jimenez, F.

    1998-01-01

    The Model for Radionuclide Migration in Urban Environment and Drainage Systems aims to estimate the discharge of radioactivity removed by natural or forced decontamination into the receiving waters from the drainage system, as well as the radioactivity joined with the sludge produced in treatments plants, whose various applications can mean a potential hazard. This model, built in Powersim, is included in the MOIRA system, a project whose main aim is the evaluation of the situation after a radioactive contamination of the aquatic ecosystems and the estimation of optimal remedial strategies to restore the contaminated waters. Powersim is an easy-to-use software package which simulates dynamic processes. Two sub-models compose the global model: one, simulating the evolution of Cs-137 in urban areas, and the other, the behaviour of this radionuclide, once it ha entered the drainage systems, with the various existing alternatives of waste water treatment in Europe. (Author) 8 refs

  18. Detection and evaluation of left atrial myxoma by gated radionuclide imaging

    International Nuclear Information System (INIS)

    Sugihara, Hiroki; Adachi, Haruhiko; Nakagawa, Hiroaki

    1985-01-01

    Radionuclide imaging plays an important role in diagnosising left atrial myxoma (LAM). We discussed diagnostic value of Fourier analysis with phase image and evaluated left ventricular filling function using indices such as 1/3 Filling Fraction, Rapid Filling Fraction and Peak Filling Rate derived from left ventricular volume curve. Equillibrium radionuclide angiocardiography was performed in 6 LAM patients. Phase delay in the basal portion of the left ventricle was shown in 5 of 6 LAM patients, and standard deviation of left ventricular phase was larger than these of controls. Left ventricular filling disturbance was suggested in 5 of 6 LAM patients. After surgical remove of myxoma phase delay was disappeared and standard deviation was normalized. And left ventricular filling was improved. We concluded that the phase image of Fourier analysis revealed a left atrial mass prolapsing in the left ventricule during the diastole, and that diastolic indices were useful for left ventricular filling disturbance due to LAM. (author)

  19. Behavior and removal of organic species in the Savannah River Plant effluent treatment facility

    International Nuclear Information System (INIS)

    Oblath, S.B.; Georgeton, G.K.

    1988-01-01

    The effluent treatment facility (ETF) at the Savannah River Plant (SRP) is a new facility designed to treat and decontaminate low-level radioactive wastewater prior to release to the environment. The wastewater is primarily composed of evaporator overheads from the chemical separations and waste handling facilities at SRP. Primarily a 2000 mg/L NaNO 3 solution, the wastewater also contains microcurie-per-liter quantities of radionuclides and milligram-per-liter concentrations of heavy metals and organic components. This paper shows a block diagram of the major process steps. The pH adjustment, filtration, mercury removal, reverse osmosis, and cation-exchange polishing steps give a significant reduction of inorganic species and radionuclide (except trittium) concentrations. The activated carbon removal step was recently added to remove organic species to ensure that the effluent discharge permit limits for oil and grease and biochemical oxygen demand are met. The concentrates and regenerates from each of the treatment steps are further concentrated by evaporation to reduce the volume sufficiently for incorporation into and disposal as a grout

  20. Inhaled plutonium oxide in dogs

    International Nuclear Information System (INIS)

    Park, J.F.

    1985-01-01

    This project is concerned with long-term experiments to determine the lifespan dose-effect relationships of inhaled 239 PuO 2 and 238 PuO 2 in beagles. The data will be used to estimate the health effects of inhaled transuranics. Beagle dogs given a single exposure to 239 PuO 2 or 238 PuO 2 aerosols to obtain graded levels of initial lung burdens are being observed for lifespan dose-effect relationships. Mortality due to radiation pneumonitis and lung tumor increased in the four highest dose-level groups exposed to 239 PuO 2 , during the 13-yr postexposure period. During the 10 1/2 years after exposure to 238 PuO 2 , mortality due to lung and/or bone tumors increased in the three highest dose-level groups. Chronic lymphopenia, occurring 0.5 to 2 year after exposure, was the earliest observed effect after inhalation of either 239 PuO 2 or 238 PuO 2 in the four highest dose-level groups that had initial lung burdens greater than or equal to 80 nCi. 3 figures, 6 tables