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Sample records for aktivnostej izotopov 239pu

  1. Status of 239Pu evaluations

    International Nuclear Information System (INIS)

    Kawano, Toshihiko; Talou, Patrick; Chadwick, Mark B.

    2014-01-01

    This paper summarises the current status of nuclear data evaluations for n+ 239 Pu. The nuclear data we address include fission, capture, scattering cross-sections, as well as the prompt fission neutron energy spectrum, which has large sensitivities to the criticality benchmark testing. The evaluated nuclear data files currently available for 239 Pu are compared, and the source of differences in the cross-sections are discussed. Some open questions on the statistical model calculations for deformed systems are also given. (authors)

  2. Evaluating 239Pu levels using field detectors

    International Nuclear Information System (INIS)

    Wahl, L.E.; Smith, W.J. II; Martin, B.

    1996-01-01

    At Los Alamos National Laboratory, cleanup was planned at three septic tanks where surface soil in the outfall drainage areas was found to be contaminated with 239 Pu. To meet budget and deadline constraints, a technique was developed that used field instruments to verify 239 Pu soil contamination at levels less than 2.8 Bq g -1 , the established cleanup level. The drainage areas were surveyed using a low-energy gamma probe to identify likely areas of 239 Pu contamination. Between 40 and 135 0.1-min gamma radiation measurements were obtained from each drainage area. From these data, locations were identified for subsequent screening for alpha radioactivity. Soil samples from between 11 and 18 locations at each drainage area were placed in petri dishes, dried, and counted for 10 minutes using an alpha probe. Alpha counts were then related to 239 Pu concentrations using a curve developed from local soils containing known concentrations of 239 Pu. Up to six soil samples from each drainage area, representing a range of alpha radioactivity levels, were sent for laboratory analysis of isotopic plutonium to confirm field measurement results. Analytical and field results correlated well at all but one outfall area. At this area, field measurements predicted more 239 Pu than was measured in the laboratory, indicating the presence of another alpha-emitting radionuclide that might have been missed if only laboratory analyses for plutonium had been used. This technique, which combined a large number of gamma radioactivity measurements, a moderate number of alpha radioactivity measurements, and a few isotopic plutonium measurements, allowed quick and inexpensive comparison of 239 Pu with the cleanup level

  3. Low level scintillation counting of 239Pu

    International Nuclear Information System (INIS)

    Fueloep, M.; Minarik, F.; Cierna, V.

    1984-01-01

    For measuring the content of 239 Pu in samples taken from the working or living environment, methods should be used which are sufficiently sensitive for determining activities of the order of 10 -3 Bq. It is useful to use liquid scintillators for reasons of their 4π geometry and the exclusion of kinetic energy losses of particles detected in the sample and on the path between the sample and the detector. The method of background discrimination according to pulse shape may be used to suppress gamma background in the area of alpha particle peaks to the level 2.5x10 -4 s -1 . The diagram is given of electronic circuits for shape discrimination. The scintillator used was a SLS-31 with a PBD activator, a POPOP spectrum shifter and a mixture of solvents: toluene, dioxane and methanol. The efficiency of 239 Pu alpha particle detection is estimated at 78% and may further be improved by improving shape discrimination. (M.D.)

  4. Age and carcinogenesis of 239Pu

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Sikov, M.R.; Hess, J.O.; Zwicker, G.M.; Carr, D.B.

    1979-01-01

    The late effects of 239 Pu have been studied after its administration to perinatal, juvenile and adult rats. Adults and weanlings were injected intravenously, newborns intracardially and 19-day foetuses by intravenous injection of the dam. Dose levels were selected to deliver radiation doses of approximately 7, 23, or 70 rads to the femur of all ages during the first 10 days post injection; in general these values were achieved as shown by tissue analysis. Dose rates subsequently diverged, resulting in widely varying cumulative radiation doses for the four age groups. Survival times of rats exposed post-natally were progressively decreased by increasing dose. No decrement in survival was found for those exposed prenatally. Bone tumour incidence was increased by exposure to Pu in all age groups. The younger rats were less sensitive on an administered dose basis, but perhaps more sensitive on the basis of cumulative radiation dose. Prenatally exposed animals, which were cross-fostered to control females, showed a higher incidence of bone tumours than did those that remained with their mother. In the adult the predominant fraction of the bone tumours was found in the extremities with a lesser fraction in the vertebrae, pelvis and other sites. In the two younger age groups the majority of the tumours were in the head with few in the extremities or vertebrae. The incidence of mammary tumours was also elevated in the adult, weanling and prenatal groups by the administration of 239 Pu. (author)

  5. 239Pu standards for quantitative neutron-induced autoradiography

    International Nuclear Information System (INIS)

    Smith, J.M.; Atherton, D.R.; Wronski, T.J.; Jee, W.S.S.

    1977-01-01

    The present study deals with the preparation of 239 Pu standards for neutron bone tissue autoradiography and the calibration of these standards with respect to uranium reference standards. Known concentrations of 239 Pu were prepared in methyl methacrylate and Bioplastic casting resin bars. Wafers sawed from these bars served as standards. Solid state nuclear tract detectors (Lexan polycarbonate) were used to record fission fragment tracks after the standards were exposed to a thermal neutron flux. The original bars were found to contain a uniform distribution of 239 Pu. To confirm the concentration of 239 Pu in the wafers, the induced track density from the 239 Pu standards was compared with that from uranium reference standards. The average fission fragment detection efficiency for all of the standards was 0.51

  6. Dosimetry of 239Pu in dogs that inhaled monodisperse aerosols of 239PuO2

    International Nuclear Information System (INIS)

    Guilmette, R.A.; Muggenburg, B.A.; Hahn, F.F.; Mewhinney, J.A.; Seiler, F.A.; Boecker, B.B.; McClellan, R.O.

    1987-01-01

    Existing data from human exposure cases and experimental animal studies on the fate and dosimetry of inhaled insoluble Pu particles are inadequate to provide a comprehensive description and evaluation of the tissues at risk from the alpha radiations of Pu. To improve our knowledge of the dosimetry of inhaled insoluble 239 PuO 2 , this paper describes the uptake and retention of 239 Pu in the tissues of dogs that received single inhalation exposures to monodisperse aerosols of 239 PuO 2 . These data include times through 3 years after exposure. Using analytical functions fitted to each tissue data set, 1100-day radiation doses were calculated for lung, liver, skeleton, kidney, spleen, and tracheobronchial, mediastinal, sternal, hepatic, mandibular, and retropharyngeal lymph nodes. The dosimetry results suggest that the lung and lymph nodes associated with lymphatic drainage of the respiratory tract are the principal sites of alpha irradiation. However, the doses for the different respiratory tract lymph nodes vary by a factor of 2000, suggesting that assuming equivalent doses to respiratory tract lymph nodes is not appropriate. Other tissues receive radiation doses also but at levels one to three orders of magnitude less than the lung. Particle size dependence on uptake and retention was noted for the skeleton, mediastinal lymph nodes, hepatic lymph nodes, retropharyngeal lymph nodes, and mandibular lymph nodes

  7. Biosorption of 239Pu by immobilized sargassum fusiforme

    International Nuclear Information System (INIS)

    Liang Zhirong; Chen Qi; Wu Yusheng

    2009-01-01

    Sargassum fusiforme was immobilized with calcium alginates and its biosorption property to 239 Pu was studied by batch and column methods. Biosorption equilibrium time of immobilized Sargassum fusiforme biosorbent to 239 Pu is 120 min and biosorption efficiency is over 99.2% when the initial concentration of 239 Pu is 21.5 kBq/L and pH is 2.5-5.0. After five times repetition biosorption-desorption cycles biosorption efficiency is still over 98.0% when the velocity of flow is 2 ml/min in column experiment. Immobilized Sargassum fusiforme biosorbent is better to 239 Pu due to its better chemical stability, mechanical strength, lower cost, high biosorption efficiency and repeated biosorption-desorption cycles. (authors)

  8. Transfer of 239Pu to mouse fetoplacental tissues

    International Nuclear Information System (INIS)

    Kubota, Yoshihisa; Sato, Hiroshi; Koshimoto, Chihiro; Takahashi, Sentaro

    1993-01-01

    Cross-placental transfer of 239 Pu from the mother to fetus was studied in C3H mice. The activity of 239 Pu in the conceptus was measured 24 hrs after the intravenous injection of 239 Pu citrate on days 10.5 to 16.5 of gestation. More 239 Pu was transferred to the conceptus when the plutonium was administered in the later stages of gestation; 0.12% of the injected dose per conceptus on day 10.5 and 1.3% on day 16.5. In all the gestational stages examined, the yolk sac and decidua contained more than 89% of the total activity distributed in the conceptus. The concentration of 239 Pu in the yolk sac was about two orders of magnitude greater than that in the fetus. The 239 Pu concentration in the maternal liver decreased with the gestational stage. In the early gestational stages the concentration in the maternal liver was greater than that in the yolk sac; but, this relationship was reversed in the later stages. (author)

  9. Critical mass variation of 239Pu with water dilution

    International Nuclear Information System (INIS)

    Pearlstein, S.

    1996-01-01

    The critical mass of an unreflected solid sphere of 239 Pu is ∼ 10 kg. The increase in critical mass observed for small water dilutions of unreflected 239 Pu spheres is paradoxical. Introducing small amounts of water uniformly throughout the sphere increases the spherical volume containing the same amount of 239 Pu as the critical solid sphere. The increase in radius decreases the surface-to-volume ratio of the sphere, which has the effect to first order of decreasing the neutron leakage, which is proportional to the surface, relative to the fissions, which are proportional to the volume. The reduction in neutron leakage is expected to reduce the critical mass, but instead, the critical mass is observed to increase. It is discussed how changes in the fast neutron spectrum with corresponding changes in the nuclear parameters result in an increase in critical mass for small water dilutions

  10. Selection of bone samples for 239Pu analyses in man

    International Nuclear Information System (INIS)

    Jee, W.S.S.; Wronski, T.J.; Smith, J.M.; Kimmel, D.B.; Miller, S.C.; Stover, B.J.

    1981-01-01

    Studies on the skeletal macrodistribution, microdistribution, and toxicity of 239 Pu and studies on bone turnover rates show that trabecular bone sites with high turnover rates have the greatest affinity for 239 Pu. In the adult beagle, these high-turnover, trabecular bone sites also show a higher occurrence of osteosarcomas. Correspondingly, high-turnover bone sites in the human would include the ilium (pelvis) and lumbar vertebrae (LVB), sites that are readily obtainable at autopsy. We recommend that the trabecular bone of the ilium and of the LVB be sampled to determine the skeletal radionuclide content of humans

  11. Late effects of 239Pu administered at representative stages of gestation

    International Nuclear Information System (INIS)

    Andrew, F.D.; Sikov, M.R.

    1979-01-01

    Evaluation of effects on postnatal growth and survival times up to about 21 months following 239 Pu administration support our working hypothesis that prenatal 239 Pu exposures may adversely affect the growth and survival of the offspring

  12. Subcellular binding of 239Pu in the liver of selected species of rodents

    International Nuclear Information System (INIS)

    Winter, R.

    1980-01-01

    The subcellular distribution of 239 Pu in the liver of selected rodent species was investigated as well as the relation between 239 Pu and the iron metabolism. The goal of the investigation was to find out why the liver discharge of 239 Pu from the liver varies so much between species. (orig.) [de

  13. Inhaled 239PuO2 in rats with pulmonary emphysema

    International Nuclear Information System (INIS)

    Lundgren, D.L.; Mauderly, J.L.; Hahn, F.F.

    1984-01-01

    The modifying effects of a pre-existing lung disease (emphysema) on the deposition, distribution, retention, and effects of inhaled 239 PuO 2 in the rat are being investigated. Preliminary observations indicated that the deposition and retention patterns for 239 Pu particles inhaled by rats with emphysema and control rats were similar, but the distribution of inhaled 239 Pu immediately after exposure was different. Respiratory function measured through one year after exposure to 239 Pu was consistent with emphysema and was not altered by the 239 Pu lung burden. Long-term observations are continuing. 4 references, 2 tables

  14. Phytoextraction studies for removal of 239Pu using Vetiveria zizanoides plants

    International Nuclear Information System (INIS)

    Singh, Shraddha; Fulzele, D.P.; Kaushik, C.P.

    2015-01-01

    The potential of Vetiveria zizanoides, a plant used for environmental conservation was tested for remediation of radionuclide plutonium ( 239 Pu). While the plant could remediate high levels of 239 Pu (65%) from solutions, remediation of radionuclides from soil was limited. Addition of chelating agents such as citric acid (CA) and diethylenetriaminepentaacetic acid (DTPA) enhanced phytoremediation of 239 Pu from soil. Translocation of 239 Pu to the shoot biomass showed an enhancement in the presence of chelating agents. The present studies have shown that V. zizanoides is a suitable candidate plant for remediation of 239 Pu and addition of DTPA enhanced translocation of radionuclide to shoot which may further lead to phytoextraction. (author)

  15. Soil components that influence the chemical behavior of 239Pu

    International Nuclear Information System (INIS)

    Nishita, H.; Hamilton, M.

    1978-08-01

    Soil components that influence the extractability of 239 Pu from an artificially contaminated kaolinitic soil in relation to pH have been examined. This was done by using an equilibrium batch technique with CH 3 COOH--NH 4 OH and HNO 3 --NaOH extracting systems. Soil organic matter and free iron oxides had an appreciable effect depending on the pH and the extracting system. The free silica and alumina and amorphous alumino-silicates had lesser influence. With the untreated soil (control), the CH 3 COOH--NH 4 OH system generally extracted more 239 Pu than did the HNO 3 --NaOH system in the acidic pH range, whereas the latter system extracted markedly greater amounts of it in the alkaline pH range. With the soil from which the organic matter was removed, the CH 3 COOH--NH 4 OH system extracted appreciably greater amounts of 239 Pu than the HNO 3 --NaOH system in the acidic pH range, but there was only little, if any, difference between the two extracting systems in the alkaline pH range. The causes and the implications of these results are discussed

  16. Solution species of 239Pu [V] in the environment

    International Nuclear Information System (INIS)

    Rai, D.; Serne, R.J.; Swanson, J.L.

    1978-01-01

    Information regarding the oxidation states of Pu in environmental samples is needed for estimating its migration through the geologic media. Thermodynamic data were used to develop stability fields for different Pu species. The data indicate that in the Eh-pH range of natural aqueous environments, the dominant species of Pu is likely to be Pu[V] in relatively oxidizing environments and Pu[III] in reducing environments. Because of the lack of methods of determining Pu[V] in environmental samples containing trace concentrations of Pu, Pu[V] has not been previously identified in these samples. Plutonium [VI] is generally assumed to be the dominant species in relatively oxidizing environments. However, a combination of solvent extraction and spectrophotometric techniques used in this study show that solutions (> 10 -5 4 M Pu) in equilibrium with 239 Pu[IV] hydroxide contain Pu[V], which is in agreement with the thermodynamic predictions. Although this method could not be used conclusively with the remaining solutions ( -5 4 M Pu) contacting 239 Pu[IV] hydroxide and 239 PuO 2 , the solvent extraction and Eh-pH results are similar for all the samples suggesting the strong possibility that all samples contain Pu[V]. Thus the possibility, ignored in the past, that Pu[V] may be the dominant species in relatively oxidizing environments should be considered

  17. Simulation of 239Pu location in trabecular bone: a computerized model of adult endosteal bone remodeling and its interaction with injected 239Pu

    International Nuclear Information System (INIS)

    Kimmel, D.B.; Jee, W.S.S.

    1979-01-01

    A computer simulation of the relationship of bone microanatomic metabolic activity to the microscopic location of 239 Pu in bone has been attempted. The model incorporates the rate of bone turnover, cell location and density, bone resorptive activity (as it removes 239 Pu from bone), bone formation activity (as it buries 239 Pu in bone), recycling of 239 Pu, and liver translocation of 239 Pu to bone, such that the skeletal retention curve for 239 Pu injected in monomeric form into the young adult beagle is matched. The eventual aim of this work is to calculate the radiation dose to bone cells, knowing the relative location of 239 Pu deposited in bone and the cells that reside at bone surfaces as it changes throughout the lifespan of an animal. Early results indicate that osteosarcoma incidence may be proportional to the number of alpha hits which occur to osteoprogenitor cells and osteoblasts, the dividing cell population found near surfaces where bone turnover is in progress

  18. Neutron spectra of /sup 239/Pu-Be neutron sources

    Energy Technology Data Exchange (ETDEWEB)

    Kumar, A; Nagarajan, P S [Bhabha Atomic Research Centre, Bombay (India). Div. of Radiation Protection

    1977-01-01

    Neutron spectra of /sup 239/Pu-Be(..cap alpha..,n) sources have been calculated by using the most recent data on the differential cross sections and angular distributions. The contribution from the multibody break-up reaction /sup 9/Be(..cap alpha..,..cap alpha..n)/sup 8/Be has also been incorporated. Modifications to the primary spectrum due to the secondary interactions in the source such as elastic scattering with beryllium, oxygen and plutonium and the /sup 9/Be(n,2n) and /sup 239/Pu(n,f) reaction have been calculated for different strengths and geometries. The present calculation has shown that the spectrum changes considerably because of these events within the source by way of smearing of peaks and filling up of valleys and raising the low energy part of the spectrum. Increase in H/D value leads to channeling of extra neutrons into the equatorial plane at the cost of the neutrons along the axial direction. The present calculations show that inclusion of secondary interactions to the extent considered in this work does not account completely for the increased intensity in the lower energy end of the measured spectrum.

  19. Low-level 239PuO2 lifespan studies

    International Nuclear Information System (INIS)

    Sanders, C.L.

    1985-01-01

    This project will produce data to generate a dose-response curve (and to evaluate other statistical methods that also incorporate survival time) for lung-tumor incidence in Wistar rats following inhalation of 239 PuO 2 at levels producing lifetime radiation doses to the lung of 2000 rad. The lung clearance of 239 Pu is best represented by a two-exponential equation, with 78% of the initial alveolar depositions (IAD) cleared with a half-time of 19 days and 22% cleared with a half-time of 180 days. A total of 593 of 2134 exposed and 242 of 1058 sham-exposed rats have died. Among the dead rats, the percent with primary lung tumors was 71% for the 150-nCi group, 70% for the 82-nCi group, and 23% for the 32-nCi group. No lung tumors have been found in controls, and only three have been found at an IAD of < 7.5 nCi. 1 figure, 3 tables

  20. Characterization of a neutron source of 239PuBe

    International Nuclear Information System (INIS)

    Hernandez V, R.; Chacon R, A.; Hernandez D, V. M.; Mercado, G. A.; Vega C, H. R.; Ramirez G, J.

    2009-10-01

    The spectrum equivalent dose and environmental equivalent dose f a 239 PuBe source have been determined. The appropriate handling of a neutron source depends on the knowledge of its characteristics, such as its energy distribution, total rate of flowing and dosimetric magnitudes. In many facilities have not spectrometer that allows to determine the spectrum and then area monitors are used that give a dosimetric magnitude starting from measuring the flowing rate and the use of conversion factors, however this procedure has many limitations and it is preferable to measure the spectra and starting from this information the interest dosimetric magnitudes are calculated. In this work a Bonner sphere spectrometer has been used with a 6 LiI(Eu) scintillator obtaining the count rates that produce, to a distance of 100 cm, a 239 PuBe source of 1.85E(11) Bq. The spectrum was reconstructed starting from the count rates using BUNKIUT code and response matrix UTA4. With the spectrum information was calculated the source intensity, total flow, energy average, equivalent dose rate, environmental equivalent dose rate, equivalent dose coefficient and environmental equivalent dose coefficient. By means of two area monitors for neutrons, Eberline ASP-1 and LB 6411 of Berthold the equivalent dose and environmental equivalent dose were measured. The determinate values were compared with those reported in literature and it found that are coincident inside 17%. (Author)

  1. Gamma-ray Output Spectra from 239 Pu Fission

    International Nuclear Information System (INIS)

    Ullmann, John

    2015-01-01

    Gamma-ray multiplicities, individual gamma-ray energy spectra, and total gamma energy spectra following neutron-induced fission of 239 Pu were measured using the DANCE detector at Los Alamos. Corrections for detector response were made using a forward-modeling technique based on propagating sets of gamma rays generated from a paramaterized model through a GEANT model of the DANCE array and adjusting the parameters for best fit to the measured spectra. The results for the gamma-ray spectrum and multiplicity are in general agreement with previous results, but the measured total gamma-ray energy is about 10% higher. A dependence of the gamma-ray spectrum on the gamma-ray multplicity was also observed. Global model calculations of the multiplicity and gamma energy distributions are in good agreement with the data, but predict a slightly softer total-energy distribution

  2. Mechanical resuspension of 239Pu from unpaved roads

    International Nuclear Information System (INIS)

    Hodgin, C.R.

    1982-01-01

    The impacts of resuspended plutonium from two unpaved roads at the Rocky Flats Plant on nearby air samplers were investigated. Because the sources were complex fugitive dust emitters and because of the small source-receptor distances, traditional dispersion modeling techniques could not be employed. Thus two specialized techniques, one for fugitive dust emissions and one for near distance dispersion, were developed and used to calculate atmospheric dust concentrations at the subject air samplers. Atmospheric 239 Pu impacts were then determined from measurements of plutonium concentrations in the resuspendible dust on the road surfaces. As a final step in the process the calculated plutonium impacts were compared to the 1980 annual average 239 Pu concentration at four samplers. The impact calculated for the Gunnery Range Road represented 2.1 percent of the observed annual concentration, with a 95 percent confidence interval of 1.1 to 7.9 percent. The Southeast Perimeter Road produced a more substantial effect with a point estimate of 3.8 percent. The 95 percent confidence interval for this source was 2.0 to 9.1 percent. The combined impact of the two roads on the subject samplers was 5.9 percent of the observed plutonium concentration, with a 95 percent confidence interval of 3.2 to 17.0 percent. Thus it was shown that fugitive plutonium emissions from the Gunnery Range Road and Southeast Perimeter Road are not substantial contributors to the plutonium concentrations observed at the subject samplers. Even an increase in dust control efficiency to 90 percent (as with paving) would result in only a four percent decrease in the overall atmosperic plutonium concentration at the site

  3. R-matrix analyses of the 235U and 239Pu neutron cross sections

    International Nuclear Information System (INIS)

    Derrien, H.; de Saussure, G.; Larson, N.M.; Leal, L.C.; Perez, R.B.

    1988-01-01

    The resonance parameter analysis code SAMMY was used to perform consistent resonance analyses of several 235 U and 239 Pu fission and capture cross section and transmission measurements up to 110 eV for 235 U and up to 1 keV for 239 Pu. The method of analysis, the measurement selection and the results are briefly outlined in this paper

  4. Inhaled 239PuO2 in rats with pulmonary emphysema. II

    International Nuclear Information System (INIS)

    Lundgren, D.L.; Mauderly, J.L.; Carlton, W.W.; Hahn, F.F.

    1988-01-01

    The modifying effects of pre-existing pulmonary emphysema on deposition, distribution, retention, and effects of inhaled 239 PuO 2 in the rat were investigated. The presence of emphysema in the rats tested was indicated by respiratory function measurements and confirmed microscopically. Initial lung burdens of 239 Pu per kg body weight were less in rats with emphysema than in control rats; however, the retention of 239 Pu was similar in emphysematous and control rats. Survival and lung tumor occurrence were similar in emphysematous and control rats exposed to 239 PuO 2 . We concluded that rats with pre-existing pulmonary emphysema were not more sensitive to the effects of inhaled 239 PuO 2 than control rats. (author)

  5. Inhaled {sup 239}PuO{sub 2} in rats with pulmonary emphysema. II

    Energy Technology Data Exchange (ETDEWEB)

    Lundgren, D L; Mauderly, J L; Carlton, W W; Hahn, F F

    1988-12-01

    The modifying effects of pre-existing pulmonary emphysema on deposition, distribution, retention, and effects of inhaled {sup 239}PuO{sub 2} in the rat were investigated. The presence of emphysema in the rats tested was indicated by respiratory function measurements and confirmed microscopically. Initial lung burdens of {sup 239}Pu per kg body weight were less in rats with emphysema than in control rats; however, the retention of {sup 239}Pu was similar in emphysematous and control rats. Survival and lung tumor occurrence were similar in emphysematous and control rats exposed to {sup 239}PuO{sub 2}. We concluded that rats with pre-existing pulmonary emphysema were not more sensitive to the effects of inhaled {sup 239}PuO{sub 2} than control rats. (author)

  6. Chronic cigarette smoke exposure increases the pulmonary retention and radiation dose of 239Pu inhaled as 239PuO2 by F344 rats

    International Nuclear Information System (INIS)

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

    1998-01-01

    As a portion of a study to examine how chronic cigarette smoke exposure might alter the risk of lung tumors from inhaled 239 PuO 2 in rats, the effects of smoke exposure on alpha-particle lung dosimetry over the life-span of exposed rats were determined. Male and female rats were exposed to inhaled 239 PuO 2 alone or in combination with cigarette smoke. Animals exposed to filtered air along served as controls for the smoke exposure. Whole-body exposure to mainstream smoke diluted to concentrations of either 100 or 250 mg total particulate matter m -3 began at 6 wk of age and continued for 6 h d -1 , 5 d wk -1 , for 30 mo. A single, pernasal, acute exposure to 239 PuO 2 was given to all rats at 12 wk of age. Exposure to cigarette smoke caused decreased body weight gains in a concentration dependent manner. Lung-to-body weight ratios were increased in smoke-exposed rats. Rats exposed to cigarette smoke before the 239 PuO 2 exposure deposited less 239 Pu in the lung than did controls. Except for male rats exposed to LCS, exposure to smoke retarded the clearance of 239 Pu from the lung compared to control rats through study termination at 870 d after 239 PuO 2 exposure. Radiation doses to lungs were calculated by sex and by exposure group for rats on study for at least 360 d using modeled body weight changes, lung-to-body weight ratios, and standard dosimetric calculations. For both sexes, estimated lifetime radiation doses from the time of 239 PuO 2 exposure to death were 3.8 Gy, 4.4 Gy, or 6.7 Gy for the control, LCS, or HCS exposure groups, respectively. Assuming an approximately linear dose-response relationship between radiation dose and lung neoplasm incidence, approximate increases of 20% or 80% in tumor incidence over controls would be expected in rats exposed to 239 PuO 2 and LCS or 239 PuO 2 and HCS, respectively

  7. 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.)

  8. Study of the number of neutrons produced by fission of {sup 239}Pu; Etude du nombre de neutrons produits par la fission de {sup 239}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Jacob, M [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1958-07-01

    Study of the number of neutrons produced by fission of {sup 239}Pu. The counting by coincidence of fissions and neutrons produced by these fissions allows the study of the variation of the mean number of neutrons emitted by {nu} fission. In the first chapter, it studied the variation of the mean number of neutrons emitted by {sup 239}Pu fission with the energy of the incident neutron. A description of the experiment is given: a spectrometer with a crystal of sodium chloride or beryllium (mounted on a goniometer) is used, a fission chamber containing 10 mg of {sup 239}Pu and the neutron detection system constituted of BF{sub 3} counters which are enriched in {sup 10}B. In the second part, the counting by coincidence of fissions and neutrons produced by the same fission and received by two different groups of counters allow the determination of a relationship between the root mean square and the average of neutron number produced by fission. The variation of the mean number of neutrons emitted by fission of {sup 239}Pu is studied when we change from a thermal spectra of neutrons to a fission spectra of incident neutrons. Finally, when separating in two different part the fission chamber, it is possible to measure the mean number of neutrons emitted from fission of two different sources. It compared the mean number of neutrons emitted by fission of {sup 239}Pu and {sup 233}U. (M.P.)

  9. Independent fission yields of Rb and Cs from thermal-neutron-induced fission of 239Pu

    International Nuclear Information System (INIS)

    Balestrini, S.J.; Forman, L.

    1975-01-01

    The relative independent fission yields of Rb and Cs from thermal-neutron-induced fission of 239 Pu have been measured on line using a mass spectrograph and thermalized neutrons from a burst reactor. Independent yields were derived by normalizing the measurements to products of chain yields and fractional independent yields, estimating the latter from measured cumulative yields of Kr and Xe. Comparing the independent yields with those from 238 U fission, the 239 Pu results show shifts in isotopic yield distribution toward lower mass for both Rb and Cs and also toward the production of more Cs and less Rb when 239 Pu is fissioned

  10. Numerical prediction of 239Pu migration in unsaturated porous media under infiltration scenario

    International Nuclear Information System (INIS)

    Liu Dongxu; Si Gaohua; Wang Qinghai; Yu Jing

    2011-01-01

    In terms of the study on site selection of a radioactive waste disposal repository in northwest China, a numerical prediction of 239 Pu migration for potential groundwater pollution in the unsaturated zone was conducted with the HYDRUS-1D model. The results showed that the groundwater will not be contaminated by the migration of soluble 239 Pu. And there is little possibility that 239 Pu migration through groundwater path might have an unacceptable impact on exosphere. Measurements of the distribution coefficient, K d , are critical in the determination of sorption-induced retardation of radionuclide transport. (authors)

  11. Numerical prediction of 239Pu migration for groundwater pollution in the infiltration case

    International Nuclear Information System (INIS)

    Liu Dongxu; Si Gaohua; Wang Qinghai; Yu Jing

    2010-01-01

    In terms of the study on site selection of geological disposal of LIL radioactive waste in north-west China, a numerical prediction of 239 Pu migration for potential groundwater pollution in the unsaturated zone was conducted with the HYDRUS-ID model. The results showed that the groundwater will not be contaminated by the migration of soluble 239 Pu. And there is a faint possibility that 239 Pu migration through groundwater path might have an unacceptable impact on ecosphere. Measurements of the distribution coefficient, K d , are critical in the determination of sorption-induced retardation of radionuclide transport. (authors)

  12. Annual and life-time doses from acute and chronic intakes of 239Pu

    International Nuclear Information System (INIS)

    Bhati, Sharda; Rudran, Kamala

    1994-01-01

    A procedure to estimate annual, committed and life time doses from acute and chronic intakes of a long-lived radionuclide 239 Pu, is described. Annual dose computations, presented for 239 Pu of 5μm activity median aerodynamic diameter (AMAD), takes into account contribution from previous years intakes. Annual limits on intakes (ALI) for W and Y class of 239 Pu are computed as per the new internal dose limitation system of ICRP-61. Life time doses, corresponding to chronic intakes of 1 ALI/y for working periods of 40 and 50 years are presented for life span of 70 years of a radiation worker. These results are useful in assigning annual doses for occupational workers handling 239 Pu. (author). 5 refs., 2 tabs

  13. Late effects of 239Pu administered at representative stages of gestation

    International Nuclear Information System (INIS)

    Andrew, F.D.; Sikov, M.R.; Dagle, G.E.; Carr, D.B.

    1980-01-01

    Prenatal exposure to 239 Pu depressed offspring growth and survival rates in a relatively dose-related fashion. Histopathological evaluations of the tumors and other lesions removed at necropsy are currently underway

  14. Toxicity of 239PuO2 inhaled by aged Beagle dogs. X

    International Nuclear Information System (INIS)

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

    1988-01-01

    The influence of age at exposure on the metabolism, dosimetry, and biological effects of inhaled 239 PuO 2 particles is being studied in aged Beagle dogs (8.0-10.5 yr of age at exposure). Forty-eight dogs inhaled 239 PuO 2 particles with an activity median aerodynamic diameter of 1.5 mm to achieve graded levels of initial pulmonary burdens (IPB) ranging from 0.02-0.66 μCi 239 Pu/kg body weight (0.75-24 kBq/kg). Twelve other dogs were exposed to the aerosol diluent only. All forty-eight exposed dogs have died, including two in the past year. The twelve control dogs have also died, including one in the past year. Radiation pneumonitis and pulmonary fibrosis have been the primary causes of death in these aged dogs exposed to 239 PuO 2 . (author)

  15. Early retention of 237Pu + 239Pu in mature beagles

    International Nuclear Information System (INIS)

    Lloyd, R.D.; McFarland, S.S.; Atherton, D.R.; Bruenger, F.W.; Taylor, G.N.; Mays, C.W.

    1978-01-01

    Five mature beagles, ranging in age from 57 to 84 months, were injected intravenously with about 0.05-0.1 μCi/kg of 239 Pu(IV) citrate to which tracer amounts of the photon-emitter 237 Pu had been added. Plutonium retention in liver and in non-liver tissue (mainly skeleton) was measured periodically in the living dogs for nearly 4 months after injection by a combination of total-body and partial-body counting. All excreta were collected during the first 21 days and analysed for their Pu content. One dog was sacrificed at 14 days and another at 118 days for distribution studies. About 17% (14-20%) of the injected Pu was excreted in the urine and feces in the first 3 weeks, about the same as that excreted in a corresponding time by beagles injected as young adults (14%), but substantially more than beagles injected as juveniles (11%). In contrasts to juvenile beagles injected at 3 months of age, in which early retention was about 12% in liver and 68% in the skeleton, mature beagles retained about 30% in liver and 50% in the skeleton. Retention in young adult beagles injected at 17 months of age was similar to that of mature dogs. Relative distribution of skeletal plutonium among various bones was similar in the mature animals to that seen previously in young adults, but quite different from that of juveniles. A notable exception was the humerus for which there was no significant difference (P>0.2) in the % of retained skeletal Pu represented by the humerus among the juvenile, young adult and mature dogs. (author)

  16. Chromosome aberration frequency in blood lymphocytes of animals with 239Pu lung burdens

    International Nuclear Information System (INIS)

    Brooks, A.L.; LaBauve, R.J.; McClellan, R.O.; Jensen, D.A.

    1976-01-01

    Other investigators have suggested a causal relationship between accidental 239 Pu exposures in man and the presence of chromosome aberrations in blood lymphocytes. For experimental assessment of this relationship, 16 rhesus monkeys and 171 Chinese hamsters were exposed to 239 PuO 2 aerosols and an additional five hamsters were injected with 239 Pu citrate, and the frequency of aberrations in blood lymphocyte was determined. Hamsters with the highest lung burden had a median survival time of about 80 days. No deaths occurred in any of the other treated hamsters or monkeys by 250 days after 239 Pu inhalation. Hamsters sacrificed at 30 days showed an increase in chromosome aberration frequency with increasing dose to lungs. By 120 days after inhalation, the aberration frequency in the controls was 0.012. The frequency in animals with doses that produced significant life shortening had decreased to 0.018 and to 0.032 aberration/cell in animals with lower doses. At 380 days after injection of 2 nCi of 239 Pu citrate per gram of body weight, hamster lymphocytes had an aberration frequency of 0.048 aberration/cell. The level of chromosome damage in the 239 PuO 2 -exposed monkeys at 30 and 90 days after inhalation was not different from that observed in controls. Possible reasons for differences between the experimental animal observations and findings in man are discussed

  17. Low-level inhaled-239PuO2 life-span studies in rats

    International Nuclear Information System (INIS)

    Sanders, C.L.; McDonald, K.E.; Killand, B.W.; Mahaffey, J.A.; Cannon, W.C.

    1986-01-01

    This study determined the dose-response curve for lung tumor incidence in rats after inhalation of high-fired 239 PuO 2 , which gave radiation doses to the lung of from ∼5 to >1000 rads. Exposed rats were given a single, nose-only, inhalation exposure to 169 Yb- 239 PuO 2 aerosol (AMAD, 1.6 +- 0.11 μm). The effective half-time for 169 Yb in the lung was 14 days, whereas ∼76% of 239 Pu was cleared with a half-time of 20 days and 24%, with a half-time of 180 days. Whole-body counting for 169 Yb at 14 days after exposure was an accurate method for determining 239 Pu IAD in individual rats, even at IAD's as low as 0.60 nCi of 239 Pu. The 239 Pu lung-clearance curve and an equation describing changes in lung weight with body weight and age were used to determine lung radiation doses. The IAD's of exposure groups were 0.60 +- 0.15 nCi of 239 Pu (1000 rats), 0.98 +- 0.25 (531 rats), 2.4 +- 0.69 (209 rats), 5.7 +- 1.2 (98 rats), and 7.5 +- 2.0 to 150 +- 37 nCi (300 rats); corresponding radiation doses to the lung estimated at 3 years after exposure were 8.3, 14, 33, 79, and 100 to 2100 rads, respectively. 71 refs., 5 figs., 4 tabs

  18. Study of the number of neutrons produced by fission of 239Pu

    International Nuclear Information System (INIS)

    Jacob, M.

    1958-01-01

    Study of the number of neutrons produced by fission of 239 Pu. The counting by coincidence of fissions and neutrons produced by these fissions allows the study of the variation of the mean number of neutrons emitted by ν fission. In the first chapter, it studied the variation of the mean number of neutrons emitted by 239 Pu fission with the energy of the incident neutron. A description of the experiment is given: a spectrometer with a crystal of sodium chloride or beryllium (mounted on a goniometer) is used, a fission chamber containing 10 mg of 239 Pu and the neutron detection system constituted of BF 3 counters which are enriched in 10 B. In the second part, the counting by coincidence of fissions and neutrons produced by the same fission and received by two different groups of counters allow the determination of a relationship between the root mean square and the average of neutron number produced by fission. The variation of the mean number of neutrons emitted by fission of 239 Pu is studied when we change from a thermal spectra of neutrons to a fission spectra of incident neutrons. Finally, when separating in two different part the fission chamber, it is possible to measure the mean number of neutrons emitted from fission of two different sources. It compared the mean number of neutrons emitted by fission of 239 Pu and 233 U. (M.P.)

  19. The Distribution of 239Pu in the Surface Soils at the Ujung Lemahabang Area

    International Nuclear Information System (INIS)

    Tarigan, Cerdas

    2000-01-01

    The study distribution of 239 Pu in the surface soil at the Ujung Lemahabang Area has been carried out. The aim of study to get information about 239 Pu activity in the depth of soil at 0 - 5 cm. 5 - 10 cm, 10 - 15 cm, 15 - 20 cm and 20 - 25 cm respectively. Sampling was done at random from 3 stations amount 1 kg respectively. The analytical method used was decomposition and leaching process using acid, chemical purification with anion exchange resin and measurement of activity with a spectrometry Result of the measurement showed that the average 239 Pu activity was 10.16 mBq/kg and this method was very good because its have high recovery of separation about 80 %. The activity of 239 Pu was lower than the result of measurement in another location in the world. The result of the study showed that the possibility of 239 Pu came from natural and fallout from atmospheric nuclear tests in the last period 1950 - 1960. (author)

  20. Biochemical effects of inhaled 239PuO2 on lung lipids

    International Nuclear Information System (INIS)

    Tombropoulos, E.G.; Hadley, J.G.; Thomas, J.M.; Craig, D.K.

    1977-01-01

    Results of experiments carried out to assess the effect of 239 Pu α irradiation on lung lipid biosynthesis and to determine the lungs ability to incorporate palmitate into lavage lecithin and its turnover are reported. The experiments were carried out on rats which had inhaled 239 PuO 2 particles. The study of palmitate incorporation into lipids shows conclusively that for medium (23 to 42 nCi) or high (more than 100 nCi) lung depositions the incorporation by isolated mitochondria is significantly (P 239 PuO 2 were positive, with respect to controls in 8 of 10 instances, when measured following the label of palmitate in lung lavage lecithin. The interpretation of the significant result (P < 0.05) is that: (1) initial and/or final lecithin pool sizes were different, (2) transfer rates were affected between blood and lung, or (3) rates of degradation of lung lavage lecithin were affected. (U.K.)

  1. /sup 239/Pu contamination in snakes inhabiting the Rocky Flats Plant site

    Energy Technology Data Exchange (ETDEWEB)

    Geiger, R.A.; Winsor, T.F.

    1975-01-01

    For approximately four years studies have been under way at the Rocky Flats plant to determine contamination patterns and concentrations of Pu in the biota. Contamination of the Rocky Flats environs has resulted from at least three incidents, a September 1957 fire, a May 1969 fire, and leaking barrels containing plutonium-laden cutting oil. The latter incident was considered by far the major source of the plutonium contamination. Results are reported from a study conducted to determine whether snake tissues of the area contained detectable amounts of /sup 239/Pu and, if so, at what concentrations. Eastern yellow-bellied racers (Coluber constrictor flaviventris, bullsnakes (Pituophis melanoleucus sayi, and prairie rattlesnakes (Crotalus viridis viridis, were collected for /sup 239/Pu bioassay of lung, liver, and bone tissues. Snakes were captured using drift fences terminating in funnel traps and by opportunistic sampling. Results led to the conclusion that snakes are not an important organism in the redistribution of /sup 239/Pu. (CH)

  2. 239Pu contamination in snakes inhabiting the Rocky Flats Plant site

    International Nuclear Information System (INIS)

    Geiger, R.A.; Winsor, T.F.

    1975-01-01

    For approximately four years studies have been under way at the Rocky Flats plant to determine contamination patterns and concentrations of Pu in the biota. Contamination of the Rocky Flats environs has resulted from at least three incidents, a September 1957 fire, a May 1969 fire, and leaking barrels containing plutonium-laden cutting oil. The latter incident was considered by far the major source of the plutonium contamination. Results are reported from a study conducted to determine whether snake tissues of the area contained detectable amounts of 239 Pu and, if so, at what concentrations. Eastern yellow-bellied racers (Coluber constrictor flaviventris, bullsnakes (Pituophis melanoleucus sayi, and prairie rattlesnakes (Crotalus viridis viridis, were collected for 239 Pu bioassay of lung, liver, and bone tissues. Snakes were captured using drift fences terminating in funnel traps and by opportunistic sampling. Results led to the conclusion that snakes are not an important organism in the redistribution of 239 Pu

  3. Toxicity of inhaled 239PuO2 in Fischer 344 rats

    International Nuclear Information System (INIS)

    Redman, H.C.; Boecker, B.B.; Muggenburg, B.A.; Griffith, W.C.; Guilmette, R.A.; Mewhinney, J.A.; Scott, B.R.

    1979-01-01

    Studies on the biological effects of inhaled particles of 239 PuO 2 have been initiated in the Fischer 344 rat. To obtain information on the importance of homogeneity or nonhomogeneity of radiation dose to the lung, young adult (84 +- 7 days) animals have been exposed to monodisperse aerosols (sigma/sub g/ 239 PuO 2 of 1.0 and 2.8 μm aerodynamic diameter (AD). To determine the effects of age at exposure, aged rats (600 to 660 days) have been exposed to monodisperse aerosols of 239 PuO 2 of 1.0 μm aerodynamic diameter. To date, 480 young adult rats have been exposed to 239 PuO 2 : 240 rats to 1.0 μm AD particles and 240 rats to 2.85 μm AD particles. The projected exposure level ranged from 0.012 to 0.115 μCi/kg body weight. One hundred sixty rats were sham-exposed and maintained as controls. Also, 240 aged rats have been exposed to date to 1.0 μm AD particles of 239 PuO 2 . The projected activity level ranged from 0.012 to 0.115 μCi/kg body weight. Eighty rats were sham-exposed and maintained as controls. In addition, a serial sacrifice study to determine radiation-dose pattern in rats resulting from the inhalation of these monodisperse aerosols of 239 PuO 2 has been initiated in the young adult rat

  4. Risk estimates for lung tumours from inhaled 239PuO2, 238PuO2, and 239Pu(NO3)4 in beagle dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Park, J.F.; Gilbert, E.S.; Weller, R.E.

    1989-01-01

    Lung cancer risks are being studied in beagle dogs given single exposures to aerosols of 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 . A major objective of these studies is to examine the risk of lung cancer relative to the specific activity of the radionuclide, rate of dose accumulation due to differences in solubilities of the radionuclides, and the presence of competing risk from extrapulmonary lesions. Dose-response relationships were studied for the three groups of dogs, with analyses specifically designed to evaluate differences in response. Based on estimated cumulative dose to the lung, risks were found to differ significantly among the radionuclides; they were highest for 239 Pu(NO 3 ) 4 and lowest for 238 PuO 2 . A model in which the risk was assumed to be a pure quadratic function of dose fitted the data much better than a pure linear model. Currently, all three groups of dogs can be compared only to 10 years after exposure. However, it is apparent that the average cumulative dose to the lung may not be an adequate predictor of lung cancer risk for different isotopic and physicochemical forms of plutonium. (author)

  5. Effects of 239Pu administered at 9 days of gestation on hematologic development of the rat

    International Nuclear Information System (INIS)

    Joshima, H.; Hackett, P.L.; Kujawa, M.J.; Doctor, P.G.; Sikov, M.R.

    1977-01-01

    Injection of pregnant rats with monomeric 239 Pu after 9 days of gestation decreased their leukocyte and reticulocyte counts at 5 and 10 days postexposure. Most of the fetal hematologic enumerative values were unaffected by injection of monomeric 239 Pu. There was, however, a major change in the maturation of the cells of the erythroid series, as indicated by a difference in the distribution between cell types. The weight of the yolk sac and fetal liver, and the cellularity of the fetal spleen were decreased

  6. Effects of pregnancy and lactation on the toxicity of 239Pu

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Hess, J.O.; Sikov, M.R.

    1980-01-01

    Nulliparous, pregnant, or lactating Wistar rats were injected intravenously with 0, 0.5 or 2.0 μCi of 239 Pu per kilogram of body weight. Half of each group were repeatedly bred while the others were held for observation without further treatment. Treatment with either dose of 239 Pu decreased the median time to appearance of mammary tumors. Repeated breeding tended to increase the mean time to appearance. Longevity was decreased in a dose-related fashion by Pu administration. Repeated breeding did not influence survival in a major way

  7. Behavior and biological action of 239Pu while getting into skin abrasions

    International Nuclear Information System (INIS)

    Bazhin, A.G.; Lyubchanskij, Eh.R.; Nifatov, A.N.; Sinyakov, E.G.

    1983-01-01

    The levels of the radionuclide resorption are given through abrasions in applying 224-906 kBk of 239 Pu on them (0.6=1.5 % for 600 days), the nature of distribution and parameters of its exchange in the test skin area, skeleton and liver. Data of morphological studies are presented. The influence of prolonged complexon therapy on 239 Pu content in organs and tissues, mean life span, the frequency of appearance of morphological changes in test skin areas with the contamination density of 40; 184 and 722 kBk of 239 Pu/cm 2 and the frequency of tumor development including malignancy in case of applying 224 and 906 kBk of 239 Pu to abrasions is evaluated. It has been established that as a result of complexon therapy dosage exposure of the skeleton lessened by 4-5 times, the mean life span of rats with tumors increased, the development of osteosarcomas caused by Pu reduced from 23.6-36.2 to 4.4-6.2 % but the therapy did not influence the frequency of pathological changes in the test skin area

  8. First radiochemical studies on the transmutation of 239Pu with spallation neutrons

    International Nuclear Information System (INIS)

    Wan, J.-S.; Langrock, E.-J.; Westmeier, W.

    2000-01-01

    Incineration studies of plutonium were carried out at the synchrophasotron of the Joint Institute for Nuclear Research (Dubna) using proton beams with energies of 0.53 GeV and 1.0 GeV. Solid lead target (8 cm in diameter and 20 cm long) was surrounded with 6 cm thick paraffin as neutron moderator and then irradiated. The transmutation of 239 Pu and the associated production of fission products 91 Sr, 92 Sr, 97 Zr, 99 Mo, 103 Ru, 105 Ru, 129 Sb, 132 Te, 133 I, 135 I and 143 Ce were studied. The plutonium samples (each 449 mg) were placed on the outer surface of moderator. For 1.0 GeV proton beam, the fission rate of 239 Pu is 0.0032 fissions per proton in one gram plutonium samples, for 0.53 GeV proton this value is 0.0022. The experimental uncertainty is about 15%. The experiments are compared to two theoretical model calculations with moderate success, using the Dubna Cascade Model (CEM) and the LAHET code. The practical incineration rate of 239 Pu is very high. For example: if one uses 10mA, 1 GeV proton beams under the same (fictive) experimental conditions, the incineration rate of 239 Pu via fission is 3 mg out of the 449 mg sample per day. For 0.53 GeV protons the corresponding rate is 2 mg per day

  9. R-matrix analysis of the 239Pu cross sections up to 1 keV

    International Nuclear Information System (INIS)

    Derrien, H.; de Saussure, G.; Perez, R.B.; Larson, N.M.; Macklin, R.L.

    1986-06-01

    The results are reported of an R-matrix resonance analysis of the 239 Pu neutron cross sections up to 1 keV. After a description of the method of analysis the nearly 1600 resonance parameters obtained are listed and extensive graphical and numerical comparisons between calculated and measured cross-section and transmission date are presented. 47 refs., 47 figs., 8 tabs

  10. Determination of 239Pu/240Pu isotopic ratio by high resolution alpha-particle spectrometry

    International Nuclear Information System (INIS)

    Amoudry, F.; Burger, P.

    1983-05-01

    The development of passivated ion-implanted silicon detectors and of very thin alpha-particle sources improves the resolution of alpha-particle spectra and allows to separate energy pics up to now unseparate. The 239 Pu/ 240 Pu isotopic ratio of a mixture has been measured using the alpha spectrometry deconvolution code DEMO [fr

  11. Transmutation of 129I, 237Np, 238Pu, 239Pu, and 241Am using ...

    Indian Academy of Sciences (India)

    Results of transmutation studies of 129I, 237Np, 238Pu, 239Pu and 241Am are presented. Keywords. ... J Adam et al. Table 1. Samples properties for 0.7 and 1 GeV experiments. ..... If we suppose that this conclusion is true also for ratios in ...

  12. 8-group relative delayed neutron yields for monoenergetic neutron induced fission of 239Pu

    International Nuclear Information System (INIS)

    Piksaikin, V.M.; Kazakov, L.E.; Isaev, S.G.; Korolev, G.G.; Roshchenko, V.A.; Tertychnyj, R.G

    2002-01-01

    The energy dependence of the relative yield of delayed neutrons in an 8-group model representation was obtained for monoenergetic neutron induced fission of 239 Pu. A comparison of this data with the available experimental data by other authors was made in terms of the mean half-life of the delayed neutron precursors. (author)

  13. Retention of 241Am and 239Pu in the rat as influenced by Triton WR 1339

    International Nuclear Information System (INIS)

    Gruner, R.; Siedel, A.

    1976-01-01

    A lysosomotropic agent, the non-ionic detergent Triton WR 1339 (a poly-oxyethylene ether of formaldehyde polymers of octylphenol) is known to be stored in rat liver lysosomes. The results of a study made to determine whether Triton WR 1339 exerts an influence on the metabolic fate of monomeric 239 Pu and 241 Am in the rat as well as on the removal of these nuclides by DTPA, since Triton WR 1339 and transuranic elements share the same deposition site, are reported. The influence of Triton WR 1339 on the 241 Am content (per cent of 241 Am dose) of rat organs (skeleton, liver, kidneys) at different times after Triton WR 1339 injection, the influence of the time of Triton WR 1339 injection on the 241 Am content (per cent of 241 Am dose) of the same rat organs, and the influence of Triton WR 1339 Zn-DTPA and the combination of them on the retention of monomeric 239 Pu in the same rat organs (per cent of 239 Pu dose), are shown in tabular form. The mechanism whereby Triton WR 1339 appears to shorten the biological half-life of 239 Pu and 241 Am in rat liver is discussed. (U.K.)

  14. The comparative carcinogenicity of 239Pu, 241Am, and 244Cm in the rat

    International Nuclear Information System (INIS)

    Taylor, D.M.

    1986-01-01

    Five completed studies compared the effects of 239 Pu, 241 Am, and 244 Cm in August-Marshall F 1 hybrid rats. Osteosarcomas were observed in all the treated groups but not in any control group. More than 70% of the osteosarcomas occurred in the lumber or thoracic vertebrae, the femur, or the tibia with all three radionuclides, but there is an indication that a smaller proportion of the tumors arises in the vertebrae after 239 Pu administration than after either of the other two radionuclides. Risk coefficients are 239 Pu, 487 +- 52; 241 Am, 175 +- 32; 244 Cm, 162 +- 45. These risk coefficients suggest that in the rat 239 Pu is about three times more effective for bone tumor induction than the other two radionuclides. A small number of leukemias, mainly of myelogenous origin, and a small number of other soft-tissue tumors were observed in the radionuclide-injected groups. No leukemias were observed in many hundreds of control animals. 14 refs., 4 tabs

  15. Effects of inhaled insoluble 239PuO2 on immune responses following lung immunization

    International Nuclear Information System (INIS)

    Bice, D.E.; Harris, D.L.; Brooks, A.L.; Mewhinney, J.A.

    1978-01-01

    To determine if inhaled 239 PuO 2 suppresses immunity in lung-associated lymph nodes, Chinese hamsters were exposed to a polydisperse aerosol of 239 PuO 2 produced at 1150 0 C. The mean lung burden of these animals was estimated to be 10 nCi at 8 days after exposure. At 128, 256 and 400 days after exposure, sham exposed controls and experimental animals were immunized by intratracheal instillation of 1 x 10 8 sheep red blood cells (SRBC). Six days later, they were sacrificed and the number of antibody forming cells (AFC) in lung-associated lymph nodes, spleen and cervical lymph nodes was evaluated. Results of these studies indicated that the number of AFC in lung-associated lymph modes was significantly lower in animals exposed to 239 PuO 2 . Only a few AFC were found in spleen and cervical lymph nodes after intratracheal immunization and the number in exposed animals was not significantly different than in the controls. These data indicate that even though the 239 PuO 2 exposure had suppressed immune responses in lung-associated lymph nodes, their filtering capacity was unaffected and antigen did not translocate to the spleen. We conclude that, at the sacrifice intervals evaluated, the immune function of lung-associated lymph nodes was suppressed and that distant lymphoid tissue (e.g., spleen and cervical lymph nodes) did not replace the immune function of the lung-associated lymph nodes

  16. DTPA treatment schedules for decorporation of /sup 239/Pu from simulated wounds

    Energy Technology Data Exchange (ETDEWEB)

    Gemenetzis, E; Volf, V [Kernforschungszentrum Karlsruhe (Germany, F.R.). Inst. fuer Strahlenbiologie

    1977-06-01

    Rats were injected intramuscularly with /sup 239/Pu in the form of citrate or nitrate and the effect of daily subcutaneous injections of 30 ..mu..mole kg/sup -1/ Ca-DTPA was compared with that of higher Zn-DTPA doses administered in single daily injections or in a continuous infusion. Treatment reduced uptake by the organs of /sup 239/Pu, but did not influence its translocation. When /sup 239/Pu was injected as citrate, it was not only more readily translocated, but also more easily chelated than after injection as /sup 239/Pu-nitrate. The higher decorporation effectiveness of Ca-DTPA could be compensated only by increasing the Zn-DTPA dosage by a factor of 33. Maintenance of a sustained Zn-DTPA blood level proved to be of little significance. Thus, from the decorporation point of view, there is at present no reason to replace single daily injections of Ca-DTPA by Zn-DTPA during early treatment of incorporated plutonium.

  17. Late effects of 239Pu administered at representative stages of gestation

    International Nuclear Information System (INIS)

    Andrew, F.D.; Sikov, M.R.

    1977-01-01

    The protocol for a systematic comprehensive study of the influence of prenatal exposure on the tumorigenic and other adverse effects of 239 Pu is described. The study has been initiated, all animals have been weaned, and postnatal function is being evaluated, although results are not yet available

  18. Isotope ratios of 240Pu/239Pu in soil samples from different areas

    International Nuclear Information System (INIS)

    Muramatsu, Yasuyuki; Yoshida, Satoshi; Yamazaki, Shinnosuke

    2003-01-01

    Plutonium concentrations and 240 Pu/ 239 Pu atom ratios in soil samples from Japan and other areas in the world (including IAEA standard reference materials) were determined by ICP-MS. The range of 240 Pu/ 239 Pu atom ratios observed in 21 Japanese soil samples was 0.155 - 0.194 and the average was 0.180 ± 0.011, which is comparable to the global fallout value. A low ratio of about 0.05, which is derived from Pu-bomb, was found in samples from Nishiyama (Nagasaki) and Mururoa Atoll (IAEA-368), while a high ratio of about 0.31 was found in a sample from Bikini Atoll (Marshall Islands). The ratio for Irish Sea sediment (IAEA-135) was 0.21, which was higher than the global fallout value, suggesting the influence by the contamination from the Sellafield facility. The 240 Pu/ 239 Pu atom ratios in soils from the Chernobyl area were determined, and the ratio was found to be very high (about 0.4), indicating the high burn-up grade of the reactor fuel. These results show that the 240 Pu/ 239 Pu ratio can be used as a finger print to identify the source of the contamination. (author)

  19. Determination of {sup 240}Pu/{sup 239}Pu ratio and its significance in environmental studies

    Energy Technology Data Exchange (ETDEWEB)

    Muramatsu, Yasuyuki [National Inst. of Radiological Sciences, Chiba (Japan)

    1999-03-01

    Analytical procedures for the determination of Pu concentrations and its isotopic ratios in environmental samples were developed by using ICP-MS. Detection limit of Pu by ICP-MS was about 0.02 pg ml{sup -1} (0.05 mBq ml{sup -1} for {sup 239}Pu; 0.17 mBq ml{sup -1} for {sup 240}Pu) in the sample solution. Analytical results of {sup 239+240}Pu in IAEA standard reference materials indicated that the accuracy of this method was satisfactory. Data on the {sup 240}Pu/{sup 239}Pu atom ratios, which are rare in the literature, were also obtained for soil and sediment samples (including IAEA standard reference materials) from different areas such as Irish Sea, Mururoa Atoll, Marshall Islands, Chernobyl, Kyshtym, Nagasaki and some other places in Japan. The range of the {sup 240}Pu/{sup 239}Pu ratios was about 0.04-0.4, and the ratios are depending on the origin of the materials. Analytical results for the {sup 240}Pu/{sup 239}Pu atom ratios provide information about the source of the contamination and the transfer of plutonium in the environment. (author)

  20. Pulmonary distribution of inhaled 239PuO2 in dogs

    International Nuclear Information System (INIS)

    McShane, J.F.; Dagle, G.E.; Park, J.F.; Catt, D.L.

    1980-01-01

    Dogs exposed to 239 PuO 2 by inhalation were killed from 1 to 69 mo postexposure. The distribution of plutonium in the lungs, which was studied by analyzing autoradiographs, changed relative to time postexposure. This study investigates methods of measuring these changes

  1. Modifying effects of pre-existing fibrosis in rats exposed to aerosols of 239PuO2. II

    International Nuclear Information System (INIS)

    Lundgren, D.L.; Mauderly, J.L.; Gillett, N.A.; Hahn, F.F.

    1988-01-01

    We have initiated a study using rats to determine the modifying effects of pre-existing pulmonary fibrosis on the retention and biological effects of inhaled 239 PuO 2 . Pulmonary fibrosis was induced by intratracheal instillation of 8.5 IU/kg body weight of bleomycin at 45 to 49 days before inhalation exposure to an aerosol of 239 PuO 2 . The clearance of 239 Pu from the lungs of rats was decreased significantly (p 239 Pu, apparently by entrapping the particles in fibrotic areas of the lung. The life span of the rats with pulmonary fibrosis was decreased by up to 25% compared with control rats having similar initial lung burdens of 239 Pu. (author)

  2. European roe deer antlers as an environmental archive for fallout 236U and 239Pu

    International Nuclear Information System (INIS)

    Froehlich, M.B.; Steier, P.; Wallner, G.; Fifield, L.K.

    2016-01-01

    Anthropogenic 236 U and 239 Pu were measured in European roe deer antlers hunted between 1955 and 1977 which covers and extends beyond the period of intensive nuclear weapons testing (1954–1962). The antlers were hunting trophies, and hence the hunting area, the year of shooting and the approximate age of each animal is given. Uranium and plutonium are known to deposit in skeletal tissue. Since antler histology is similar to bone, both elements were expected in antlers. Furthermore, roe deer shed their antlers annually, and hence antlers may provide a time-resolved environmental archive for fallout radionuclides. The radiochemical procedure is based on a Pu separation step by anion exchange (Dowex 1 × 8) and a subsequent U purification by extraction chromatography using UTEVA ® . The samples were measured by Accelerator Mass Spectrometry at the VERA facility (University of Vienna). In addition to the 236 U and 239 Pu concentrations, the 240 Pu/ 239 Pu isotopic ratios were determined with a mean value of 0.172 ± 0.023 which is in agreement with the ratio of global fallout (∼0.18). Rather high 236 U/ 238 U ratios of the order of 10 −6 were observed. These measured ratios, where the 236 U arises only from global fallout, have implications for the use of the 236 U/ 238 U ratio as a fingerprint for nuclear accidents or releases from nuclear facilities. Our investigations have shown the potential to use antlers as a temporally resolved archive for the uptake of actinides from the environment. - Highlights: • Roe deer antlers were studied as an environmental archive for the retrospective study of fallout isotopes 236 U and 239 Pu. • The rather high 236 U/ 238 U ratios of about 10 −6 suggest 236 U as a fingerprint tool for nuclear material releases. • The 240 Pu/ 239 Pu atom ratio underpins global fallout as the main anthropogenic contributor in antlers.

  3. Characterization of a neutron source of {sup 239}PuBe; Caracterizacion de una fuente de neutrones de {sup 239}PuBe

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez V, R.; Chacon R, A.; Hernandez D, V. M.; Mercado, G. A.; Vega C, H. R. [Universidad Autonoma de Zacatecas, Unidad Academica de Estudios Nucleares, Calle Cipres No. 10, Fracc. La Penuela, 98068 Zacatecas (Mexico); Ramirez G, J. [Instituto Nacional de Estadistica Geografia e Informatica, Direccion General de Innovacion y Tecnologia de Informacion, Av. Heroes de Nacozari Sur 2301, Fracc. Jardines del Parque, 20276 Aguascalientes (Mexico)], e-mail: ruben_zac@yahoo.com

    2009-10-15

    The spectrum equivalent dose and environmental equivalent dose f a {sup 239}PuBe source have been determined. The appropriate handling of a neutron source depends on the knowledge of its characteristics, such as its energy distribution, total rate of flowing and dosimetric magnitudes. In many facilities have not spectrometer that allows to determine the spectrum and then area monitors are used that give a dosimetric magnitude starting from measuring the flowing rate and the use of conversion factors, however this procedure has many limitations and it is preferable to measure the spectra and starting from this information the interest dosimetric magnitudes are calculated. In this work a Bonner sphere spectrometer has been used with a {sup 6}LiI(Eu) scintillator obtaining the count rates that produce, to a distance of 100 cm, a {sup 239}PuBe source of 1.85E(11) Bq. The spectrum was reconstructed starting from the count rates using BUNKIUT code and response matrix UTA4. With the spectrum information was calculated the source intensity, total flow, energy average, equivalent dose rate, environmental equivalent dose rate, equivalent dose coefficient and environmental equivalent dose coefficient. By means of two area monitors for neutrons, Eberline ASP-1 and LB 6411 of Berthold the equivalent dose and environmental equivalent dose were measured. The determinate values were compared with those reported in literature and it found that are coincident inside 17%. (Author)

  4. Intertidal mangrove mudflat 240+239Pu signatures, confirming a 210Pb geochronology on the southeastern coast of Brazil

    International Nuclear Information System (INIS)

    Sanders, C.J.; Patchineelam, S.R.; Ketterer, M.E.

    2010-01-01

    A sediment core was taken to determine if sediment accumulation rates could be conducted using 240+239 Pu signatures in the coastal mangrove mudflats of southeastern Brazil. The results from this study show that 240+239 Pu fallout activities are sufficient and well preserved in the coastal sediments of this region. Sediment accumulation rates determined from the 240+239 Pu signatures were 4.4 mm/year and 4.1 from 210 Pb (CIC) method. A sediment mixing coefficient rate was calculated using chlorophyll-a profile (9.5 cm 2 ). (author)

  5. {sup 239}Pu and {sup 240}Pu inventories and {sup 240}Pu/{sup 239}Pu atom ratios in the equatorial Pacific Ocean water column

    Energy Technology Data Exchange (ETDEWEB)

    Yamada, Masatoshi, E-mail: myamada@cc.hirosaki-u.ac.jp [Department of Radiation Chemistry, Institute of Radiation Emergency Medicine, Hirosaki University, 66-1 Hon-cho, Hirosaki, Aomori 036-8564 (Japan); Zheng, Jian [Research Center for Radiation Protection, National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage, Chiba 263-8555 (Japan)

    2012-07-15

    The {sup 239+240}Pu concentrations and {sup 240}Pu/{sup 239}Pu atom ratios were determined by alpha spectrometry and inductively coupled plasma mass spectrometry for seawater samples from two stations, one at the equator and the other in the equatorial South Pacific. To better understand the fate of Pu isotopes, this study dealt with the contribution of the close-in fallout Pu from the Pacific Proving Grounds (PPG) in water columns of the Pacific Ocean. The {sup 239}Pu, {sup 240}Pu and {sup 239+240}Pu inventories over the depth interval 0-3000 m at the equator station were 10.4, 8.9 and 19.3 Bq m{sup -2}, respectively. Further, no noticeable difference was observed in {sup 239}Pu, {sup 240}Pu and {sup 239+240}Pu inventories over the depth interval 0-3000 m between the two stations. The total {sup 239+240}Pu inventories were significantly higher than the expected cumulative deposition density of global fallout. Water column {sup 239+240}Pu inventories measured in this study were lower than those reported for comparable stations in the Geochemical Ocean Sections Study, indicating that these inventories have been decreasing at average rates of 0.89 {+-} 0.07 and 0.16 {+-} 0.07 Bq m{sup -2} yr{sup -1} at the equator and equatorial South Pacific stations, respectively, from 1973 to 1990. The obtained {sup 240}Pu/{sup 239}Pu atom ratios were higher than the mean global fallout ratio of 0.18. These high atom ratios proved the existence of close-in tropospheric fallout Pu from the PPG in the Marshall Islands. The {sup 239+240}Pu inventories originating from the close-in fallout in the entire water column were estimated to be 11.1 Bq m{sup -2} at the equator station and 7.1 Bq m{sup -2} at the equatorial South Pacific Ocean station, and the relative percentages of close-in fallout Pu were 40% at the former and 34% at the latter. A significant amount of close-in fallout Pu originating from the PPG has been transported to deep layers below the 1000 m depth in the equatorial

  6. Neutron and gamma-ray spectra of 239PuBe and 241AmBe

    International Nuclear Information System (INIS)

    Vega-Carrillo, H.R.; Manzanares-Acuna, Eduardo; Becerra-Ferreiro, A.M.; Carrillo-Nunez, Aureliano

    2002-01-01

    Neutron and gamma-ray spectra of 239 PuBe and 241 AmBe were measured and their dosimetric features were calculated. Neutron spectra were measured using a multisphere neutron spectrometer with a 6 LiI(Eu) scintillator. The 239 PuBe neutron spectrum was measured in an open environment, while the 241 AmBe neutron spectrum was measured in a closed environment. Gamma-ray spectra were measured using a NaI(Tl) scintillator using the same experimental conditions for both sources. The effect of measuring conditions for the 241 AmBe neutron spectrum indicates the presence of epithermal and thermal neutrons. The low-resolution neutron spectra obtained with the multisphere spectrometer allows one to calculate the dosimetric features of neutron sources. At 100 cm both sources produce approximately the same count rate as that of the 4.4 MeV gamma-ray per unit of alpha emitter activity

  7. Electrofission of 239Pu in the energy range 7 endash 12 MeV

    International Nuclear Information System (INIS)

    Arruda-Neto, J.D.; Yoneama, M.; Dias, J.F.; Garcia, F.; Reigota, M.A.; Likhachev, V.P.; Guzman, F.; Rodriguez, O.; Mesa, J.

    1997-01-01

    The electrofission cross section of 239 Pu(e,f) is measured between 7 and 12 MeV. The data are analyzed by means of the virtual photon formalism, assuming that E1, E2 (T=0), and M1 transitions are involved. Using known estimates for the E1 and E2 (T=0) fission strengths, it is deduced an M1 fission strength of 19±4μ N 2 concentrated near the fission barrier (between 5.4 and 5.8 MeV). The levels of the 239 Pu transition nucleus are theoretically obtained; a bunch of positive-parity levels shows up between 5.5 and 5.9 MeV, which might well be associated with the deduced M1 strength, since the E2 strength is negligible in this energy interval. copyright 1997 The American Physical Society

  8. Toxicity of inhaled 239PuO2 in aged beagle dogs

    International Nuclear Information System (INIS)

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

    1980-01-01

    Studies to determine the effects of age at exposure on metabolism, dosimetry and biological effects of inhaled particles of 239 PuO 2 have been initiated in aged beagle dogs (8.0 to 10.5 years of age at exposure). Beagle dogs have been exposed to 1.5 μm AD particles of 239 PuO 2 resulting in initial lung burdens ranging from 0.03 to 0.76 μCi/kg body weight. Dogs exposed to the aerosol diluent serve as controls. There were four blocks exposed in the past year, one of males and three of female dogs. Nine dogs died during the year. Seven of these had radiation pneumonitis and two died of nonradiation induced diseases. The surviving dogs are as long as 538 days after exposure. There are three blocks of male dogs planned for exposure in the next 12 months

  9. Analysis of the 239Pu neutron cross sections from 300 to 2000 eV

    International Nuclear Information System (INIS)

    Derrien, H.; de Saussure, G.

    1990-01-01

    A recent high-resolution measurement of the neutron fission cross section of 239 Pu has allowed the extension from 1 to 2 keV of a previously reported resonance analysis of the neutron cross sections, and an improvement of the previous analysis in the range 0.3 to 1 keV. This report analyzes this region. 8 refs., 1 fig., 2 tabs

  10. Early effects of inhaled 239Pu(NO3)4 aerosols in beagle dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Ragan, H.A.; Watson, C.R.; Stevens, D.L.; Rowe, S.E.; Madison, R.M.; Wierman, E.L.; Schirmer, R.E.

    1979-01-01

    Beagle dogs given a single inhalation exposure to 239 Pu(NO 3 ) 4 , and observed for life-span dose-effect relationship, died from radiation pneumonitis (4 of 5) at the highest dosage level, 14 to 25 mo postexposure. There were also indications in these dogs of radiation osteosis, characterized by peritrabecular fibrosis. Leukopenia, lymphopenia, neutropenia and decreased numbers of circulating monocytes and eosinophils occurred at the two highest dosage levels, as previously reported

  11. Distribution of skeletal malignancies in beagles injected with 239Pu citrate

    International Nuclear Information System (INIS)

    Lloyd, R.D.; Taylor, G.N.; Angus, W.

    1994-01-01

    The distribution of skeletal malignancies among our beagles injected with 239 Pu as young adults roughly seems to follow the distribution of skeletal mass and skeletal 239 Pu. These findings are similar to those we reported previously for a group of dogs given 226 Ra. Although there were differences in tumor distribution between the animals given 239 Ra and those given 239 Pu, most of them were not statistically significant; however, the radium dogs seemed to show a greater sensitivity to bone tumor origin in the tibia, while there may have been a tendency among the plutonium dogs toward increased relative sensitivity in the scapula, lumbar vertebrae, sacrum, and ribs. In contrast, the most common site for the formation of naturally-occurring bone malignancy in the dog is the distal radius. Perhaps there were too few tumors and too few dogs to establish statistical significance. A correlation between tumor location and at least two anatomical-physiological factors in the skeleton indicated that these two factors (site-specific bone turnover rate and percent of red marrow at the site, which is correlated with vascularity) may influence the appearance of malignancies both individually and in combination. Except for the femur, there appeared to be no difference between the relative distribution of skeletal malignancies of low-level (30 Bq-2 Bq kg -1 injected) and high-level (3-122 kBq kg -1 ) dogs. Distribution of bone tumors between the axial and appendicular skeleton was 50% vs. 50% for 239 Pu (42 and 42), but it was 39% axial vs. 61% appendicular (22 and 35, respectively) for dogs given 226 Ra. This difference was not significant (p > 0.2). 15 refs., 4 tabs

  12. Calibration of the polycarbonate dosimeter for the microdosimetry of 239Pu alpha particles in bone

    International Nuclear Information System (INIS)

    Stillwagon, G.B.; Morgan, K.Z.

    1977-01-01

    There has been some criticisms of the maximum permissible organ burden (MPOB) in bone for 239 Pu in recent years. These criticisms allude to the relative dearth of experimental data available concerning the actual dose delivered to the endosteal face of osseous tissue by the 239 Pu alpha particle. A dosimeter recently developed has been recommended for application to this microdosimetry problem. The tissue equivalence of polycarbonate dosimeters would allow dose equivalent to be read directly from the foil rather than determining activity from emulsions, in which the alpha particle range is different than in tissue, then relating this activity measurement to absorbed dose by some calculations. Although this dosimeter has been calibrated to read dose equivalent for fast neutron dosimetry, the need exists to determine the factor to multiply by the number of 239 Pu alpha-induced tracks to obtain dose equivalent. This problem is being approached in the following manner. A device called the vacuum-sealed alpha-calibrator has been designed and constructed which will allow the handling of a standard 239 Pu solution obtained for this purpose. The calibrator will first be connected to surface barrier detectors which feed data into a multi-channel analyzer. The counts obtained under the alpha peaks at various heights above the source and the accumulated time are input into a computer program recently written to convert this data into dose rate in rems/unit time. Next the measurements are duplicated, this time using the polycarbonate dosimeter. The results will produce a factor relating the number of alpha-induced tracks to dose

  13. Distribution and retention of 239Pu administered to rats at representative stages of gestation

    International Nuclear Information System (INIS)

    Sikov, M.R.; Andrew, F.D.

    1979-01-01

    The distribution of 239 Pu in tissues of mothers and their offspring, as well as in other fetoplacental unit components, was measured following intravenous injection at 9, 15, or 19 days of gestation. Deposition levels and retention were markedly different at the earliest time of gestation, but less difference was seen between the two later times. Radiation dose to the fetus was similar for all ages, but dose to specific organs and tissues varied with stage of gestation

  14. Long-term effects of 239Pu injection in adult, weanling, newborn and fetal rats

    International Nuclear Information System (INIS)

    Sikov, M.R.; Mahlum, D.D.; Hess, J.O.; Carr, D.B.

    1979-01-01

    We have completed biological evaluations comparing long-term effects in rats exposed to 239 Pu citrate as adults, weanlings, newborns, or late fetuses, and statistical analyses have been initiated. In rats exposed postnatally, statistically significant alterations in terminal body weight and in weights of several organs were found at higher doses. Survivorship decreased with increasing dose in the postnatal groups, but not in rats exposed prenatally

  15. Presence of plutonium isotopes, {sup 239}Pu and {sup 240}Pu, in soils from Chile

    Energy Technology Data Exchange (ETDEWEB)

    Chamizo, E., E-mail: echamizo@us.es [Centro Nacional de Aceleradores, Avda. Thomas Alba Edison, 7, 41092 Sevilla (Spain); Garcia-Leon, M., E-mail: manugar@us.es [Departamento de Fisica Atomica, Molecular y Nuclear, Universidad de Sevilla, Avda. Reina Mercedes sn, 41012 Seville (Spain); Peruchena, J.I., E-mail: jiperuchena@gmail.com [Centro Nacional de Aceleradores, Avda. Thomas Alba Edison, 7, 41092 Sevilla (Spain); Cereceda, F., E-mail: francisco.cereceda@usm.cl [Laboratorio de Quimica Ambiental, Centro de Tecnologias Ambientales (CETAM), Universidad Tecnica Federico Santa Maria, Casilla 110-V, Valparaiso (Chile); Vidal, V., E-mail: victor.vidal@usm.cl [Laboratorio de Quimica Ambiental, Centro de Tecnologias Ambientales (CETAM), Universidad Tecnica Federico Santa Maria, Casilla 110-V, Valparaiso (Chile); Pinilla, E., E-mail: epinilla@unex.es [Departamento de Quimica Analitica, Facultad de Ciencias, Universidad de Extremadura, Avda. de Elvas sn, 06071 Badajoz (Spain); Miro, C., E-mail: cmiro@unex.es [Departamento de Fisica Aplicada, Universidad de Extremadura, Avda. de la Universidad sn, 10071 Caceres (Spain)

    2011-12-15

    Plutonium is present in every environmental compartment, due to a variety of nuclear activities. The Southern Hemisphere has received about 20% of the global {sup 239}Pu and {sup 240}Pu environmental inventory, with an important contribution of the so-called tropospheric fallout from both the atmospheric nuclear tests performed in the French Polynesia and in Australia by France and United Kingdom, respectively. In this work we provide new data on the impact of these tests to South America through the study of {sup 239}Pu and {sup 240}Pu in soils from different areas of Northern, Central and Southern Chile. The obtained results point out to the presence of debris from the French tests in the 20-40 Degree-Sign Southern latitude range, with {sup 240}Pu/{sup 239}Pu atomic ratios quite heterogeneous and ranging from 0.02 to 0.23. They are significantly different from the expected one for the global fallout in the Southern Hemisphere for the 30-53 Degree-Sign S latitude range (0.185 {+-} 0.047), but they follow the same trend as the reported values by the Department of Energy of United States for other points with similar latitudes. The {sup 239+240}Pu activity inventories show as well a wider variability range in that latitude range, in agreement with the expected heterogeneity of the contamination.

  16. Presence of plutonium isotopes, 239Pu and 240Pu, in soils from Chile

    International Nuclear Information System (INIS)

    Chamizo, E.; García-León, M.; Peruchena, J.I.; Cereceda, F.; Vidal, V.; Pinilla, E.; Miró, C.

    2011-01-01

    Plutonium is present in every environmental compartment, due to a variety of nuclear activities. The Southern Hemisphere has received about 20% of the global 239 Pu and 240 Pu environmental inventory, with an important contribution of the so-called tropospheric fallout from both the atmospheric nuclear tests performed in the French Polynesia and in Australia by France and United Kingdom, respectively. In this work we provide new data on the impact of these tests to South America through the study of 239 Pu and 240 Pu in soils from different areas of Northern, Central and Southern Chile. The obtained results point out to the presence of debris from the French tests in the 20–40° Southern latitude range, with 240 Pu/ 239 Pu atomic ratios quite heterogeneous and ranging from 0.02 to 0.23. They are significantly different from the expected one for the global fallout in the Southern Hemisphere for the 30–53°S latitude range (0.185 ± 0.047), but they follow the same trend as the reported values by the Department of Energy of United States for other points with similar latitudes. The 239+240 Pu activity inventories show as well a wider variability range in that latitude range, in agreement with the expected heterogeneity of the contamination.

  17. Importance of resonance parameters of fertile nuclei and of 239Pu isotope for fast power reactors

    International Nuclear Information System (INIS)

    Barre, J.Y.; Khairallah, A.

    1975-01-01

    The importance of resonance parameters of fertile nuclei and of 239 Pu isotope for fast power reactors will be restricted, in this presentation, to mixed oxide-uranium-plutonium fuelled sodium-cooled and uranium-oxide-sodium reflected fast reactors. The power range lies between 200 and 2000 MWe. Among the topics of this specialist meeting, the isotopes to be considered are, primarly 239 Pu then 238 U and 240 Pu. Resonance parameters are mainly used in fast power reactor calculations through the well-known concept of self shielding factors. After a short description of the determination and the use of these self-shielding factors, their sensitivities to resonance parameters are characterized from some specific examples: those sensitivities are small. Then, the main design parameters sensitive to the amplitude of self-shielding factors are considered: critical enrichment, global breeding gain. The relative importance of isotope, reaction rate and energy range are mentionned. In a third part, the Doppler effect, sensitive to the temperature variation of self-shielding factors, is considered in the same way. Finally, it is concluded that the present knowledge of resonance parameters for 238 U, 239 Pu and 240 Pu is sufficient for fast power reactors from a designer point of view [fr

  18. Transplantation of hamster lung lesions induced by 239PuO2 or benz(a)pyrene

    International Nuclear Information System (INIS)

    McDonald, K.E.; Sanders, C.L.

    1980-01-01

    None(0%) of 1000 recipients of lung lesions for 239 PuO 2 -exposed hamsters that were transplanted into other hamsters' cheek pouches, developed tumors, whereas 90% of transplants from benz(a)pyrene-induced lung lesions were malignant

  19. Neutron inelastic-scattering cross sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu

    International Nuclear Information System (INIS)

    Smith, A.B.; Guenther, P.T.

    1982-01-01

    Differential-neutron-emission cross sections of 232 Th, 233 U, 235 U, 238 U, 239 Pu and 240 Pu are measured between approx. = 1.0 and 3.5 MeV with the angle and magnitude detail needed to provide angle-integrated emission cross sections to approx. 232 Th, 233 U, 235 U and 238 U inelastic-scattering values, poor agreement is observed for 240 Pu, and a serious discrepancy exists in the case of 239 Pu

  20. Modifying effects of preexisting pulmonary fibrosis on biological responses of rats to inhaled 239PuO2

    International Nuclear Information System (INIS)

    Lundgren, D.L.; Mauderly, J.L.; Rebar, A.H.; Gillett, N.A.; Hahn, F.F.

    1991-01-01

    We investigated the modifying effects of preexisting, bleomycin-induced pulmonary fibrosis on the deposition, retention, and biological effects of inhaled 239PuO2 in the rat. Among rats exposed to similar airborne concentrations of 239PuO2, initial lung burdens of 239Pu per kilogram body mass were similar whether or not pulmonary fibrosis was present. However, clearance of 239Pu from the lungs was significantly decreased in the rats with preexisting pulmonary fibrosis. The incidence of lung lesions (epithelial hyperplasia, diffuse macrophage increases and aggregation, and loose and dense connective tissue) was significantly greater among rats with preexisting pulmonary fibrosis than among the exposed controls. Rats with preexisting fibrosis had shorter life spans than 239PuO2-exposed control rats. When groups of rats with similar alpha doses to the lungs were compared, the incidences of neoplastic lesions in the lung, the times to death of rats with lung neoplasms, and the risk of lung tumors per unit of alpha dose to the lungs in rats with or without pulmonary fibrosis were similar. The results of this study suggest that humans with uncomplicated pulmonary fibrosis may not be more sensitive to the carcinogenic effects of inhaled 239PuO2 than are individuals with normal lungs, assuming that the total alpha doses to the lungs are similar

  1. Toxicity of 239Pu and 226Ra in young adult beagles: risk estimate in man

    International Nuclear Information System (INIS)

    Miller, S.C.

    1985-01-01

    The overall objective of this research program is to predict the risk to humans following exposure to 239 Pu. The beagle was originally selected for this program because it is relatively long-lived and has skeletal functions and structure analogous to young adults humans, simulating that of a young adult radium dial painter or occupationally exposed person. Young adult (17 month-old) beagles from the moderately inbred colony at the University of Utah were administered one intravenous injection of 239 Pu (0.0007-2.88 μCi/kg in 238 dogs) or 226 Ra (0.007-10.4 μCi/kg in 119 dogs), and compared to appropriate age-matched control beagles. All beagles have been and are being observed clinically throughout their expected 12 to 15 year post-injection lifespan. A thorough clinical and post-mortem survey is conducted to determine causes of death or lesions at death. The clinical findings are being encoded using SNOMED terminology and entered into a computerized database. All beagles in the 226 Ra study are dead and the data are being analyzed and published. The shape of the curve for dose vs. bone tumor incidence is highly linear up to average skeletal doses of 2200 rads. In higher dose groups, the time to tumor appearance is decreased and skeletal tumors occur in almost all animals. The 226 Ra response is being compared with the 239 Pu response in beagles. This toxicity ratio will allow use of the bone tumor response in the radium dial painters to predict the toxicity of plutonium for bone tumor induction in man

  2. Dosimetry and response in rat pulmonary epithelium following inhalation of 239PuO2

    International Nuclear Information System (INIS)

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

    1983-01-01

    The distribution of inhaled 239 PuO 2 and pathologic changes have been studied in the lung of rats. The clearance of inhaled 237 239 PuO 2 from the lung is a function of the amount of deposited Pu with a decrease in early alveolar clearance with increasing lung burden. With increasing time post-exposure there is a greater concentration of PuO 2 and an increased aggregation of PuO 2 particles in subpleural regions of the lung. Fibrotic and metaplastic lesions in the lung were usually focal, being found in subpleural regions associated with aggregates of PuO 2 . An average of 12 +- 6 percent of the lung volume was fibrotic at 530 days after an initial alveolar deposition of 180 nCi 239 Pu. Lung tumors occupied 4 +- 6 percent and epithelial metaplasias less than 1 percent of the lung volume at this time. Cell proliferation as assayed by tritiated thymidine autoradiography was greater in fibrotic, metaplastic and neoplastic regions than in areas of normal alveolar-bronchiolar epithelium. Turnover times ranged from about 6 days for fibrotic lesions to 1 to 3 days for metaplastic and neoplastic lesions. The lung tumor doubling times were 57 to 116 days due to tumor cell necrosis and other factors that limit tumor cell survival. Cell proliferation rates for adenomatous metaplasia were similar to those for adenocarcinoma while those for squamous cell metaplasia were similar to those for squamous cell carcinoma. Squamous lesions exhibited a more rapid growth than did adenomatous lesions

  3. Chromosomal aberrations in lymphocytes of peripheral blood among mayak facility workers who inhaled insoluble forms of 239Pu

    International Nuclear Information System (INIS)

    Okladnikova, N. D.; Scott, B. R.; Tokarskaya, Z. B.; Zhuntova, G. V.; Khokhryakov, V. F.; Syrchikov, V. A.; Grigoryeva, E. S.

    2005-01-01

    A cytogenetic study was performed on 79 plutonium (Pu) workers chronically exposed to alpha radiation from inhaled, low-transportable (insoluble) compounds of airborne 239 Pu and to external gamma rays. Body burden estimates for 239 Pu ranged from 0 to 15.5 kBq. Chromosomal aberrations (CAs) (stable and unstable among peripheral blood lymphocytes and cumulative alpha radiation doses were evaluated ∼25 y after first contact with 239 Pu. For the cytogenetic analyses, a standard two-day peripheral blood lymphocyte culture technique was applied. While alpha radiation doses continually increase up to the time of cytogenetic measurements, significant gamma ray exposures essentially ceased long before the time of measurement, so that alpha and gamma doses were not correlated. For the exposed workers, the mean 239 Pu body burden (estimate), evaluated at the time of the cytogenetic measurement, was 1.23 ± 0.26 kBq and the corresponding mean absorbed external gamma ray dose (estimate) to the total body was 0.076 ± 0.009 Gy. Single and multivariate regression analyses were performed on the CA data. Stable, unstable and total aberrations increased as the 239 Pu body burden increased over the range 0-4.5 kBq. However, above this range little additional increase was observed. CAs were weakly correlated with time since the first intake of 239 Pu. No relationship between chromatid aberrations and 239 Pu incorporation was found. Unstable (but not stable) aberrations were correlated with gamma radiation dose. No significant relationship of CA and smoking was found. (authors)

  4. R-matrix analysis of the /sup 239/Pu neutron cross sections

    Energy Technology Data Exchange (ETDEWEB)

    Saussure, G. de; Perez, R.B.; Macklin, R.L.

    1986-03-01

    /sup 239/Pu neutron cross-section data in the resolved resonance region were analyzed with the R-Matrix Bayesian Program SAMMY. Below 30 eV the cross sections computed with the multilevel parameters are consistent with recent fission and transmission measurements as well as with older capture and alpha measurements. Above 30 eV no suitable transmission data were available and only fission cross-section measurements were analyzed. However, since the analysis conserves the complete covariance matrix, the analysis can be updated by the Bayes method as transmission measurements become available. To date, the analysis of the fission measurements has been completed up to 300 eV.

  5. Direct reduction of 238PuO2 and 239PuO2 to metal

    International Nuclear Information System (INIS)

    Mullins, L.J.; Foxx, C.L.

    1982-02-01

    The process for reducing 700 g 239 PuO 2 to metal is a standard procedure at Los Alamos National Laboratory. This process is based on research for reducing 200 g 238 PuO 2 to metal. This report describes in detail the experiments and development of the 200-g process. The procedure uses calcium metal as the reducing agent in a molten CaCl 2 solvent system. The process to convert impure plutonia to high-purity metal by oxide reduction followed by electrorefining is also described

  6. Toxicity of 239PuO2 in immature Beagle dogs. III

    International Nuclear Information System (INIS)

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

    1981-01-01

    Immature Beagle dogs have been exposed by inhalation to a monodisperse aerosol of 239 PuO 2 (1.5 μm AD) to compare the biological effects with those seen in young adult and aged dogs exposed to a similar aerosol. To date 45 dogs have been exposed to the aerosol, resulting in graded lung burdens from 0.0031 to 0.64 μCi/kg body weight. Six dogs exposed to the dilute ammonium hydroxide aerosol only serve as controls. One experimental dog has died of parvovirus enteritis. Exposures will continue during the coming year to complete the experimental design

  7. 239PU sorption by suspended matter from Hueznar reservoir (Southern Spain): experimental and modelling study

    International Nuclear Information System (INIS)

    El Mrabet, R.; Abril, J.M.; Barros, H.; Manjon, G.

    2004-01-01

    Kinetic transfer coefficients are important parameters to understand and reliably model the behaviour of non-conservative radionuclides in aquatic environments. This report pertains to a series of radiotracer experiments on 239 Pu uptake in natural unfiltered waters from the Hueznar reservoir (southern Spain). The experimental procedure ensures the preservation of environmental conditions and the dissolved Pu activity was measured by liquid scintillation technique. The data suggest that the main pathways for Pu uptake consist of two parallel and reversible reactions followed by a consecutive reversible reaction. We studied the effects of suspended matter concentrations and the specific surface area on the kinetic transfer coefficients. (author)

  8. Effects of cigarette smoke exposure on pulmonary clearance of 239PuO2 in rats

    International Nuclear Information System (INIS)

    Filipy, R.E.; Pappin, J.L.; Stevens, D.L.; Irby, S.G.

    1980-01-01

    Groups of rats were exposed or sham exposed to cigarette smoke for 7 mo, at which time they were exposed to an aerosol of 239 PuO 2 . Rats were then subjected to whole-body counting (17-keV X-rays) periodically, beginning at day 4 after plutonium exposure, and smoke exposures or sham exposures were resumed on day 7. Clearance of plutonium from the lungs of cigarette-smoke-exposed rats was significantly slower than that from the sham-exposed rats' lungs. The difference between the two groups became significant 7 days after the resumption of cigarette-smoke exposures

  9. Dominant lethal tests of male mice given 239Pu salt injections

    International Nuclear Information System (INIS)

    Luening, K.G.; Froelen, H.; Nilsson, A.

    1976-01-01

    To study the possible genetic effects of 239 Pu manifesting in dominant lethals, five test series (E1-E5) were performed. Males from an inbred CBA strain were given 239 Pu salt injections intravenously and mated weekly to 3 CBA females each for 12 to 24 weeks. Some interruptions in the mating scheme were made. For the first two test series (E1, E2) 239 Pu nitrate solution and 239 Pu citrate, used in E3-E5, were prepared. The solution was millipore filtered just prior to injection. Among a total of 10255 implants sired by males given Pu-nitrate in E1 and E2 no significant excess of intra-uterine death relative to 7216 control implants occurred. Test series E3-E5 with 60 males each, used three groups of 20, with one control group. In E3, 0.5 μCi and 0.1 μCi were given per male/group, respectively; in E4 and E5, 0.25 μCi and 0.05 μCi, respectively. The males given 0.5 μCi in E3 became successively sterile from the 7th week. The results in E3-E5 point in the same direction with significant excess of intra-uterine death in E3 and E5. In E4 the females from matings from the 9th, 14th and 16th week, and in E5 females from the 9th week, were allowed to litter to give F 1 offspring. Dominant lethal tests of F 1 males gave concordant results in all four samples, showing significantly excessive death in offspring to F 1 males whose fathers had received Pu. The excessive death was evenly distributed and did not indicate the presence of semisterile F 1 males. In tests of Pu-injected males and of F 1 males a remarkable excess of death in late stages of foetal development was observed. Such effects had never before been observed in this CBA strain in tests of extrinsic and intrinsic exposure to ionizing irradiation

  10. Repeated inhalation exposure of Beagle dogs to aerosols of 239PuO2. XII

    International Nuclear Information System (INIS)

    Diel, J.H.; Hahn, F.F.; Muggenburg, B.A.

    1988-01-01

    Beagle dogs were exposed once or semi-annually for 10 yr by inhalation to aerosols of 239 PuO 2 to study the relative doses and effects of these two types of exposures. All exposures have been completed. Dogs exposed at high levels died predominantly of radiation pneumonitis and pulmonary fibrosis. Dogs exposed at lower levels, either once or repeatedly, are dying of a variety of causes including lung cancer. Dogs have survived up to 11 yr after their first exposure. Preliminary results suggest that single and repeated exposures cause similar health effects for equal accumulated radiation doses. (author)

  11. Alpha-particle emission probabilities in the decay of 239Pu

    International Nuclear Information System (INIS)

    Garcia-Torano, E.; Acena, M.L.; Bortels, G.; Mouchel, D.

    1993-01-01

    The alpha-particle emission probabilities (P α ) of 239 Pu have been measured using material of highest enrichment and radiochemical purity, thin sources produced by vacuum sublimation, and high-resolution α spectroscopy with ion-implanted Si detectors (PIPS). The results for the major emissions are P α0.07 =0.7077±0.0014, P α13 =0.1711±0.0014 and P α51 =0.1194±0.0007, which for the P α0.07 is about 3.6% lower than the recent evaluated value in the literature. (orig.)

  12. Report on the effectiveness of flocculation for removal of 239Pu at concentrations of 1 pCi/L and 0.1 pCi/L

    International Nuclear Information System (INIS)

    Triay, I.R.; Bayhurst, G.K.; Mitchell, A.J.; Cisneros, M.R.; Efurd, D.W.; Roensch, F.R.; Rokop, D.J.; Aguilar, R.D.; Attrep, M.; Nuttall, H.E.

    1993-01-01

    The objective of this work is to assess the effectiveness of flocculation for the removal of Pu from Rocky Flats Plant (RFP) pond waters spiked with 239 Pu at the 1.0 and 0.1 pCi/L level. The flocculation treatment procedure is described in detail. Results are presented for treatment studies for the removal of Pu from C-2 pond water spiked with 239 Pu and from distilled water spiked with 239 Pu

  13. Alligator Rivers Analogue project. Geochemistry of 239Pu, 129I, 99Tc and 36Cl

    International Nuclear Information System (INIS)

    Fabryka-Martin, J.T.; Curtis, D.B.

    1992-01-01

    One objective of this research programme has been to evaluate the applicability of uranium orebodies as natural analogues for testing radionuclide release-rate models used in performance assessment activities. The investigated nuclides included three of the most persistent radioactive constituents of high-level wastes from nuclear fission power reactors: plutonium-239, iodine-129, and technetium-99. The feasibility of uranium minerals as analogues for the behavior of these nuclear reaction products (NRP) in spent fuel relies upon a capability to characterise NRP concentrations in the source minerals. Measured abundances of natural 239 Pu, 99 Tc and 129 I in uranium ores are compared to calculated abundances in order to evaluate the degree to retention of these radionuclides by the ore. This modelling study also shows the extent to which various NRP are correlated, such that one provides a constraint on the production rates of others. Under most conditions, 36 Cl, another long-lived neutron-capture product found in uranium ores, is shown to be an ideal in-situ monitor of the 235 U fission rate, which is the dominant source term for 129 I and possibly a significant one for 99 Tc. Similarly, 239 Pu/U ratios can be used to establish limits on the 238 U neutron-induced fission rate; the ratios measured in this study suggest that 238 U induced fission comprises 129 I and 99 Tc. 79 refs., 21 tabs., 18 figs

  14. Photon-induced Fission Product Yield Measurements on 235U, 238U, and 239Pu

    Science.gov (United States)

    Krishichayan, Fnu; Bhike, M.; Tonchev, A. P.; Tornow, W.

    2015-10-01

    During the past three years, a TUNL-LANL-LLNL collaboration has provided data on the fission product yields (FPYs) from quasi-monoenergetic neutron-induced fission of 235U, 238U, and 239Pu at TUNL in the 0.5 to 15 MeV energy range. Recently, we have extended these experiments to photo-fission. We measured the yields of fission fragments ranging from 85Kr to 147Nd from the photo-fission of 235U, 238U, and 239Pu using 13-MeV mono-energetic photon beams at the HIGS facility at TUNL. First of its kind, this measurement will provide a unique platform to explore the effect of the incoming probe on the FPYs, i.e., photons vs. neutrons. A dual-fission ionization chamber was used to determine the number of fissions in the targets and these samples (along with Au monitor foils) were gamma-ray counted in the low-background counting facility at TUNL. Details of the experimental set-up and results will be presented and compared to the FPYs obtained from neutron-induced fission at the same excitation energy of the compound nucleus. Work supported in part by the NNSA-SSAA Grant No. DE-NA0001838.

  15. New data on the toxicity and translocation of inhaled 239PuO2 in baboons

    International Nuclear Information System (INIS)

    Metivier, H.; Masse, R.; Rateau, G.; Nolibe, D.; Lafuma, J.

    1989-01-01

    In 1973-1974, baboons were exposed to a polydispersed aerosol of 239 PuO 2 , prepared at 1000 0 C, at the Commissariat a l'Energie Atomique in France. The data published in 1978 for these baboons were used by Bair et al (1980), for comparison with those obtained in beagles exposed to 239 PuO 2 at the Pacific Northwest Laboratory, USA. Since our 1978 publication, 8 baboons have died or were killed by euthanasia when moribund, and 11 were still alive when the present report was drafted. Two of the eight baboons died of lung squamous cell carcinoma at 2171 and 2528 days respectively. The remaining 6 died of fibrosis, interstitial pneumonia or diseases unrelated to Pu toxicity. The relationship observed in the eight baboons between initial lung burden and survival time shows that their lifespan was longer than expected from the data curve based on the findings for the first 1000 days. However, this increased survival time was not observed if the lifespan was expressed as a function of the average lung burden. (author)

  16. Comparison of acute mortality in baboons and dogs after inhalation of 239PuO2

    International Nuclear Information System (INIS)

    Bair, W.J.; Park, J.F.; Stevens, D.L.; Watson, C.R.; Metivier, H.; Masse, R.; Nolibe, D.; Lafuma, J.

    1979-01-01

    Results from experiments with baboons were compared with those from experiments with dogs to determine the relative sensitivity of the two species to acute mortality from inhaled 239 PuO 2 . To assure a valid comparison of data developed at two laboratories, methodology differences were minimized by establishing a common pool of raw data, using the same computer programs to analyze the data, and standardizing assumptions regarding the calculation of radiation doses to lungs. Several comparison methods were used involving variations in estimating different parameters such as the concentration of plutonium in the lungs. Although nearly all comparisons suggested baboons were slightly more sensitive, none of the methods for comparing the relationship between dose and survival time showed consistently significant differences between baboons and dogs. Although the baboons were physiologically and morphologically immature when exposed to plutonium, whereas the dogs were mature, it was concluded that adult baboons and dogs are similarly sensitive to the acute effects of inhaled 239 PuO 2 . Since only acute mortality was considered in this comparison, the results do not apply to possible late effects caused by much lower levels of plutonium than were used in these experiments

  17. Toxicity of inhaled 239PuO2 in immature Beagle dogs. VII

    International Nuclear Information System (INIS)

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

    1985-01-01

    Immature Beagle dogs have been exposed by inhalation to a monodisperse aerosol of 239 PuO 2 (1.5 μm AMAD) to compare the biological effects with those observed in dogs exposed to a similar aerosol as young or aged adults. The study includes 96 dogs exposed to 239 PuO 2 and 12 controls. The lung burdens of the plutonium-exposed dogs ranged from 0.00030 to 0.80 μCi/kg body weight (0.011-30 kBq/kg). No dogs died during this year. Seven dogs were diagnosed as having developing lung disease, mainly fibrosis, and one had a developing lung tumor. With 20 dogs having estimated cumulative radiation doses in excess of 1000 rad (10 Gy), the biological response of the dogs exposed as juveniles appears to be less than that seen in mature dogs. However, major uncertainties still exist in the current estimations of radiation dose, particularly regarding the local distribution of alpha radiation dose. 1 reference, 4 figures, 1 table

  18. Lymphocytopenia induced in beagle dogs by inhalation of 239PuO2

    International Nuclear Information System (INIS)

    Ragan, H.A.; Park, J.F.; Olson, R.J.; Buschbom, R.L.

    1976-01-01

    To determine the life-span dose-effect relationships of inhaled plutonium, we gave 124 beagle dogs a single exposure of 239 PuO 2 2 to 3 years ago at six different levels, i.e., 4, 20, 80, 300, 1100, or 5800 nCi mean initial alveolar depositions. Another group (20 dogs) served as controls. All dogs were about 18 months old. At the four highest exposure levels, a chronic lymphocytopenia developed which correlated with the initial alveolar plutonium burden in regard to magnitude of depression and time of development after exposure. The nadir occurred near 10 months after exposure in dogs receiving 5800, 1100, and 300 nCi, with corresponding lymphocyte levels 40, 55, and 75 percent, respectively, of those observed in control dogs. In the 80-nCi level the nadir occurred about 2 years after exposure at approximately 80 percent of control values. At the two lowest doses, i.e., 4 and 20 nCi, no effect on lymphocyte concentrations was noted 3 years after exposure. The persistent lymphocytopenia related to plutonium inhalation may be of significance in the subsequent development of pulmonary neoplasms previously observed in beagles at this laboratory 8 to 11 years after initial lung depositions of 200 to 1000 nCi of 239 Pu

  19. Preliminary evaluation of lung doses for dogs exposed to 239PuO2

    International Nuclear Information System (INIS)

    Fisher, D.R.; Cannon, W.C.; Hadley, R.T.; Park, J.F.

    1986-01-01

    A group of beagle dogs exposed to inhaled 239 PuO 2 is being followed for life-span effects. This paper reports preliminary lung dose estimates and dose-response relationships for incidence of lung tumors and radiation pneumonitis which have been observed to date. Doses were estimated by using both conventional dose-averaging and microdosimetric techniques. Cascade impactor sampling data were used to reconstruct the original plutonium aerosol size distributions unique to each of about 120 individual dogs exposed to 239 PuO 2 . Data providing the initial plutonium lung burden and lifetime lung retention-clearance functions of plutonium for each dog were used for calculating average dose rates, cumulative absorbed doses, and specific energy distributions. A linear dose-response relationship for lung tumor induction was estimated on the basis of cumulative lung dose. Average time to death was estimated as a function of average dose rate. Conclusions regarding the potential value of microdosimetry in the interpretation of such dose-response relationships are discussed. 8 refs., 5 figs., 1 tab

  20. Influence of 239Pu aerosol production temperature on biological responses in Chinese hamsters

    International Nuclear Information System (INIS)

    Brooks, A. L.; Peters, R.F.; Mewhinney, J.A.

    1977-01-01

    Studies on the retention, distribution and effects of inhaled 239 Pu particles produced at different temperatures are continuing in an effort to assess the consequences of accidental inhalation exposures under various conditions. Three groups of Chinese hamsters, 381 animals per group, were exposed to aerosols of 239 Pu which had been treated in a heating column at either 50, 600 or 1150 0 C. Retention and distribution of the plutonium through 600 days after exposure reflected the relative insolubility of the aerosols heated at 1150 and 600 0 C, and the relative solubility of the aerosol heated at 50 0 C. Animals exposed to either of the insoluble aerosols had 80 to 90 percent of the sacrifice body burden in the lung at 400 days after exposure whereas animals exposed to the aerosol heated at 50 0 C had only 10 percent of the sacrifice body burden in the lung at 400 days. Translocation was mainly to the liver. To date, survival of the animals seemed to depend primarily on activity level, with production temperature exerting an influence only at the highest activities

  1. Consistent Data Assimilation of Actinide Isotopes: 235U and 239Pu

    International Nuclear Information System (INIS)

    Palmiottti, G.; Hiruta, H.; Salvatores, M.

    2011-01-01

    In this annual report we illustrate the methodology of the consistent data assimilation that allows to use the information coming from integral experiments for improving the basic nuclear parameters used in cross section evaluation. A series of integral experiments were analyzed using the EMPIRE evaluated files for 235 U, 238 U, and 239 Pu. Inmost cases the results have shown quite large worse results with respect to the corresponding existing evaluations available for ENDF/B-VII. The observed discrepancies between calculated and experimental results were used in conjunction with the computed sensitivity coefficients and covariance matrix for nuclear parameters in a consistent data assimilation. Only the GODIVA and JEZEBEL experimental results were used, in order to exploit information relative to the isotope of interest that are, in this particular case: 235 U and 239 Pu. The results obtained by the consistent data assimilation indicate that with reasonable modifications (mostly within the initial standard deviation) it is possible to eliminate the original large discrepancies on the K eff of the two critical configurations. However, some residual discrepancy remains for a few fission spectral indices that are, most likely, to be attributed to the detector cross sections.

  2. Transuranic advanced disposal systems: preliminary 239Pu waste-disposal criteria for Hanford

    International Nuclear Information System (INIS)

    Kennedy, W.E. Jr.; Napier, B.A.; Soldat, J.K.

    1982-08-01

    An evaluation of the feasibility and potential application of advanced disposal systems is being conducted for defense transuranic (TRU) wastes at the Hanford Site. The advanced waste disposal options include those developed to provide greater confinement than provided by shallow-land burial. An example systems analysis is discussed with assumed performance objectives and various Hanford-specific disposal conditions, waste forms, site characteristics, and engineered barriers. Preliminary waste disposal criteria for 239 Pu are determined by applying the Allowable Residual Contamination Level (ARCL) method. This method is based on compliance with a radiation dose rate limit through a site-specific analysis of the potential for radiation exposure to individuals. A 10,000 year environmental performance period is assumed, and the dose rate limit for human intrusion is assumed to be 500 mrem/y to any exposed individual. Preliminary waste disposal criteria derived by this method for 239 Pu in soils at the Hanford Site are: 0.5 nCi/g in soils between the surface and a depth of 1 m, 2200 nCi/g of soil at a depth of 5 m, and 10,000 nCi/g of soil at depths 10 m and below. These waste disposal criteria are based on exposure scenarios that reflect the dependence of exposure versus burial depth. 2 figures, 5 tables

  3. Occurrence of bone cancer among young adult Beagles given 239Pu

    International Nuclear Information System (INIS)

    Lloyd, R.D.; Taylor, G.N.; Bruenger, F.W.; Angus, W.; Miller, S.C.

    1991-01-01

    Two hundred thirty-five young adult Beagles of both sexes were each given a single intravenous injection of 239 Pu-citrate at graded dose-levels averaging about 0.026 to 106 kBq/kg when they were about 1 1/2 years of age and were maintained for lifespan observation. An additional 133 young adult Beagles of both sexes were entered into the experiment as control animals. All of these animals have now died or have been removed from the colony, and the occurrence of skeletal malignancies has been determined from histological examination. There were a total of 85 radiographically apparent malignant bone tumors in 77 dogs given 239 Pu, and there was one control animal that developed a skeletal malignancy. Most of these were osteosarcomas, but there were seven chondrosarcomas of bone, one liposarcoma of bone, and in addition, there was one plasma cell myeloma and one ameloblastoma (admantinoma). Only those dogs that survived to at least the minimum latent period for death with radiation-induced bone sarcoma are included in the tabulation. There appeared to be a linear relationship between the percent of dogs with bone tumor and the average skeletal dose up to a dose of about 1 Gy. All dose-levels with skeletal doses of about 2 Gy and greater exhibited close to 100% occurrence

  4. Toxicity of 239PuO2 in immature Beagle dogs. VIII

    International Nuclear Information System (INIS)

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

    1986-01-01

    Immature Beagle dogs have been exposed by inhalation to a monodisperse aerosol of 239 PuO 2 (1.5 μm AMAD) to compare the biological effects with those observed in dogs exposed to a similar aerosol as young or aged adults. The study includes 96 dogs exposed to 239 PuO 2 and 12 controls. The lung burdens of the plutonium-exposed dogs ranged from 0.00030 to 0.80 μCi/kg body weight (0.011-30 kBq/kg). A total of 82 experimental and 11 control dogs are still alive. Seven dogs died this year. Of these, six died of radiation-induced lung disease; the other of a nonradiation cause. As is the case for dogs exposed as young adult animals, the primary causes of death have been lung carcinomas and radiation pneumonitis and fibrosis. However, it is premature to compare the dose-response relationships for the two age groups. 4 figures

  5. 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.)

  6. 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

  7. In vitro dose-response of macrophages to 239PuO2 and 241AmO2

    International Nuclear Information System (INIS)

    Schneider, R.P.; Robinson, A.V.

    1979-01-01

    As part of a study designed to examine various means of solubilizing actinide particles within macrophages, we have measured the in vitro effects of 241 AmO 2 and 239 PuO 2 on these cells. Dose distribution within the cell population was estimated by autoradiography and compared to cell detachment as a function of time. The 241 AmO 2 and 239 PuO 2 were toxic in proportion to their radioactivity rather than their mass. Approximately 385 intracellular disintegrations are required from either radionuclide to cause cells to detach from the flask surface

  8. Minidosimetry of alpha-radiation from 239-Pu in the skeleton

    International Nuclear Information System (INIS)

    Polig, E.

    1980-01-01

    A novel technique for evaluating alpha-autoradiograms of the skeleton was developed and applied. The method involves scanning the alpha-track distribution on cellulose-nitrate detector foils and determination of tissue structure from Alizarin-stained bone sections (150 μm) by means of a computer controlled microscope photometer. Geometrical alignment between the two samples is preserved during the measuring process. After combining the files containing the track density distribution with the corresponding digitized bone images on a random access storage medium, detailed information concerning the radionuclide distribution on a microscopic scale, dose rates, hit frequencies etc. are extracted by a sequence of FORTRAN-programs. The potential of the method is demonstrated in a study dealing with the distribution of 239-Pu in the lumbar vertebra of adult rats. The measured dose rate distribution is discussed in terms of hit probabilities for cell nuclei and consequences for quantitative tumour models are indicated. (H.K.)

  9. The evaluation of the mass distribution data for 238U, 239Pu and 242Pu fission

    International Nuclear Information System (INIS)

    Liu Tingjin

    2002-01-01

    The mass distribution data for 238 U at E n =1.5, 5.5, 8.3, 11.3, 14.9, 22.0, 27.5, 50.0, 99.5, 160.0 MeV, E p =20.0, 60.0 MeV 239 Pu at E n =0.17, 7.9, 14.5 MeV and 242 Pu at E n =15.1 MeV were evaluated and recommended based on the main available experimental data up to now. The experimental data were make necessary corrections and their errors were also made necessary adjustments. The problems concerned were discussed

  10. Toxicity of inhaled 239PuO2 in immature beagle dogs

    International Nuclear Information System (INIS)

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

    1980-01-01

    Immature beagle dogs have been exposed by inhalation to a 1.5 μm aerodynamic diameter monodisperse aerosol of 239 PuO 2 to compare the biological effects with those seen in young adult and aged dogs exposed to a similar aerosol. To date, 18 dogs have been exposed to the aerosol, resulting in graded initial lung burdens ranging from 0.003 to 0.38 μCi/kg body weight. Two dogs have been exposed to the aerosol diluent and serve as controls. Two of the 18 exposed animals were sacrificed 8 days after exposure to provide information on initial deposition and distribution. All other exposed animals are alive 400 days after exposure. No dogs were exposed during the past year because of an outbreak of canine parvovirus enteritis which caused death in 8 to 10 week-old dogs

  11. Comparative measurements of independent yields of 239Pu fission fragments induced by thermal and resonance neutrons

    International Nuclear Information System (INIS)

    Gundorin, N.A.; Kopach, Y.N.; Telezhnikov, S.A.

    1994-01-01

    The independent yields of 239 Pu fission fragments by means of gamma-spectroscopy method were measured for light and heavy groups on the IBR-30 reactor in Dubna. Comparative analysis of experimental data for fission induced by thermal and resonance neutrons was performed. The possibilities to increase the measurement's precision consist of the employment of a HPGe detector with high efficiency and its open-quotes activeclose quotes shielding in the gamma spectrometer, as well as a high speed electronics system. In this way the number of identified fragments will be increased and independent yields will be measured to a precision of 1-3%. Measurements at the source with shorter neutron pulse duration to increase neutron energy resolution will be possible after the reconstruction of a modern neutron source in Dubna in accordance with the IREN project

  12. Combined exposure of F344 rats to beryllium metal and 239PuO2 aerosols

    International Nuclear Information System (INIS)

    Finch, G.L.; Carlton, W.W.; Rebar, A.H.; Hahn, F.F.; Hoover, M.D.; Griffith, W.C.; Mewhinney, J.A.; Cuddihy, R.G.

    1994-01-01

    Nuclear weapons industry workers have the potential for inhalation exposures to plutonium (Pu) and other agents, such as beryllium (Be) metal. Inhaled Pu deposited in the lung delivers high linear energy transfer alpha particle radiation and is known to induce pulmonary cancer in laboratory animals. Although the epidemiological evidence implicating Be in the induction of human lung cancer is weak and controversial, various studies in laboratory animals have demonstrated the pulmonary carcinogenicity of Be; Be is currently classified as a suspect human carcinogen in the United States and as a demonstrated human carcinogen by the International Agency for Research on Cancer. The purpose of this study is to investigate the potential interactions between Pu and Be in the production of lung tumors in rats exposed by inhalation to particles of plutonium dioxide ( 239 PuO 2 ), Be metal, or these agents in combination

  13. Comparison of rats and dogs exposed to 239PuO2

    International Nuclear Information System (INIS)

    Mahaffey, J.A.; Sanders, C.L.; Park, J.F.; Dagle, G.E.

    1979-01-01

    Rats and dogs inhaled aerosols of 239 PuO 2 at comparable ages relative to their lifespan. Both received a single exposure. The estimated lung doses at death in dogs were between 1100 and 11,000 rad. From two inhalation experiments, rats receiving doses in this range were chosen from the high-level exposed animals for comparison. Based on this data base, several comparisons were investigated. Metabolism of the material was compared for all animals and for animals which developed lung tumors. The differences in histopathology and tumor incidence in the lung were also reviewed. Although there were several differences between species, there were also many similarities. On-going research in dogs should produce data which will allow clarification of these relationships

  14. /sup 239/PuO/sub 2/ aerosol inhalation with emphasis on pulmonary connective tissue modifications

    Energy Technology Data Exchange (ETDEWEB)

    Metivier, H; Masse, R; Nobil' e, D; Lafuma, J

    1975-09-01

    Inhalation studies were undertaken in which plutonium dioxide (/sup 239/PuO/sub 2/) was administered to either unanesthetized Wistar rats or anaesthetized baboons. In both groups of animals some deaths occurred from acute lung damage resulting from cell necrosis particularly to vascular tissue followed by alveolar oedema. At later stages, marked interstitial pneumonitis and interstitial fibrosis occurred and deaths resulted from respiratory insufficiency preceded by high arterial blood pCO/sub 2/ and low pO/sub 2/. In rats as many as 50% of the animals finally developed lung neoplasms but only two such tumors were found in baboons. Attempts were made to correlate biochemical parameters with observed tissue damage and animal mortality.

  15. The self-absorption effect of gamma rays in 239Pu

    International Nuclear Information System (INIS)

    Hsiaohua Hsu

    1989-01-01

    Nuclear materials assay with gamma-ray spectrum measurement is a well-established method for safeguards. However, for a thick source, the self-absorption of characteristic low-energy gamma rays has been a handicap to accurate assay. The author has carried out Monte Carlo simulations to study this effect using the 239 Pu α-decay gamma-ray spectrum as an example. The thickness of a plutonium metal source can be considered a function of gamma-ray intensity ratios. In a practical application, gamma-ray intensity ratios can be obtained from a measured spectrum. With the help of calculated curves, scientists can find the source thickness and make corrections to gamma-ray intensities, which then lead to an accurate quantitative determination of radioactive isotopes in the material

  16. Aerosols generated by 239PU and 233U droplets burning in air

    International Nuclear Information System (INIS)

    Nelson, L.S.; Raabe, O.G.

    1978-01-01

    The inhalation hazards of radioactive aerosols produced by the explosive disruption and subsequent combustion of metallic plutonium in air are not adequately understood. Results of a study to determine whether uranium can be substituted for plutonium in such a situation in which experiments were performed under identical conditions with laser-ignited, single, freely falling droplets of 239 Pu and 233 U are reported. The total amounts of aerosol produced were studied quantitatively as a function of time during the combustion. Also, particle size distributions of selected aerosols were studied with aerodynamic particle separation techniques. Results showed that the ultimate quantity of aerosols, their final particle size distributions, and depositions as a function of time are not identical mainly because of the different vapor pressures of the metals, and the unlike degrees of violence of the explosions of the droplets

  17. Comparison of potential radiological impacts of 233U and 239Pu fuel cycles

    International Nuclear Information System (INIS)

    Meyer, H.R.; Little, C.A.; Witherspoon, J.P.; Till, J.E.

    1979-01-01

    Nuclear fuel cycles utilizing 233 U are currently the subject of considerable interest in the United States. This paper focuses on the identification of significant differences between the off-site radiological hazards posed by 232 Th/ 233 U (Th/U) and 238 U/ 239 Pu (U/Pu) fuel cycles, and represents a portion of our involvement in the Nonproliferation Alternative Systems Assessment Program (NASAP), to be used in support of the International Fuel Cycle Evaluation (INFCE). The major contributors to radiological dose are likely to be uranium mining and milling (58.5% of total fuel cycle dose), reprocessing (33.9%), and light-water reactor power generation (7.3%). The remainder of the cycle, including enrichment processes, fuel fabrication, transportation, and waste management, contributes only 0.3% to total estimated fuel cycle dose

  18. Evaluation of cross-section uncertainties using physical constraints for 238U, 239Pu

    International Nuclear Information System (INIS)

    De Saint Jean, Cyrille; Privas, Edwin; Archier, Pascal; Noguere, Gilles; Litaize, Olivier; Leconte, Pierre; Bernard, David

    2014-01-01

    Neutron-induced reactions between 0 eV and 20 MeV are based on various physical properties such as nuclear reaction models, microscopic and integral measurements. Most of the time, the evaluation work is done independently between the resolved resonance range and the continuum, giving rise to mismatches for the cross-sections, larger uncertainties on boundary and no cross-correlation between high-energy domain and resonance range. In addition the use of integral experiment is sometimes only related to central values (evaluation is 'working fine' on a dedicated set of benchmarks) and reductions of uncertainties are not straightforward on cross-sections themselves: working fine could be mathematically reflected by a reduced uncertainty. As the CIELO initiative is to bring experts in each field to propose/discuss these matters, after having presented the status of 238 U and 239 Pu cross-sections covariances evaluation (for JEFF-3.2 as well as the WPEC SG34 subgroup), this paper will present several methodologies that may be used to avoid such effects on covariances. A first idea based on the use of experiments overlapping two energy domains appeared in the near past. It was reviewed and extended to the use of systematic uncertainties (normalisation for example) and for integral experiments as well. In addition, we propose a methodology taking into account physical constraints on an overlapping energy domain where both nuclear reaction models are used (continuity of both cross-sections and derivatives for example). The use of Lagrange multiplier (related to these constraints) in a classical generalised least square procedure will be exposed. Some academic examples will then be presented for both point-wise and multi-group cross-sections to present the methodologies. In addition, new results for 239 Pu will be presented on resonance range and higher energies to reduce capture and fission cross-section uncertainties by using integral experiments (JEZEBEL experiment as

  19. A comparative study of the carcinogenetic effects of 241Am, 239Pu and 237Np

    International Nuclear Information System (INIS)

    Wang Yumin; Wei Zhikang; Chen Xueyi; Yao Yongheng; Liu Peibin; Xu Lin; Lun Mingyao

    1984-01-01

    In this experiment, 420 wistar rats were used to study the comparative carcinogenetic effects of 241 Am, 239 Pu and 237 Np. These nuclides were injected to animals intravenously, subcutaneously or directly into the lung (Stansen's lung puncture method) in doses of 1.0, 5.0 and 8.5 μCi/kg, respectively. As soluble nitrate, the nuclides were rapidly transfered from the site of injection into the bone and the liver. Osteosarcomas were found in some animals 8 months to one year after intoxication. Diagnosis of osteosarcoma is based on the histopatological examination and X-ray photography. In the Am-poisoned rats the incidence of osteosarcoma is about 31-74%, varied with different doses and different routes of intoxication; in Pu-poisoned rats, the incidence of osteosarcoma is about 55-66%. while in Np-poisoned rats, it is about 36-53%. Primary lung cancers were also found in those animals poisoned by means of Stansen's lung puncture method with the above three nuclides. The incidence of primary lung cancers is about 6% in Am-and Pu-poisoned rats and 13% in Np-poisoned rats. The incidence of metastasis of osteosarcoma in lung is about 25-65% for Am-poisoned rats, 45-55% for Pu-poisoned rats and 41-80% for Np-poisoned rats. The life-span of above poisoned rats was significantly shorter than that of the normal control animals. The chemical weight for 241 Am, 239 Pu and 237 Np in same unit of radioactivity (1.0 μCi) equals to 0.308 μg, 15.9 μg and 1418.7 μg, respectively. For this reason, we have to pay more attention to the chemical mass effect in carcinogenesis of the above three nuclides

  20. 8-group relative delayed neutron yields for epithermal neutron induced fission of 235U and 239Pu

    International Nuclear Information System (INIS)

    Piksaikin, V.M.; Kazakov, L.E.; Isaev, S.G.; Korolev, G.G.; Roshchenko, V.A.; Tertychnyj, R.G

    2002-01-01

    An 8-group representation of relative delayed neutron yields was obtained for epithermal neutron induced fission of 235 U and 239 Pu. These data were compared with ENDF/B-VI data in terms of the average half- life of the delayed neutron precursors and on the basis of the dependence of reactivity on the asymptotic period. (author)

  1. Comparison of metabolism and late effects in dogs and rats exposed to 239PuO2

    International Nuclear Information System (INIS)

    Mahaffey, J.A.; Sanders, C.L.; Park, J.F.; Dagle, G.E.

    1980-01-01

    Lung tumors were observed proportionally earlier in relation to expected life span in dogs than in rats after inhalation of 239 PuO 2 . Dogs appear to translocate a higher percentage of initial lung burden to liver, skeleton and thoracic lymph nodes than rats

  2. Quantitative study of pulmonary lesions and epithelial proliferation following inhalation of 239PuO2 in rats

    International Nuclear Information System (INIS)

    Rhoads, K.; Adee, R.R.; Sanders, C.L.

    1980-01-01

    Morphometric analyses of lung parenchyma exposed to 239 PuO 2 indicated a volumetric increase in pulmonary fibrosis, epithelial metaplasia, and neoplasia with increasing time after exposure. Metaplastic and neoplastic lesions usually occupied less than 1% of the total lung volume

  3. 239Pu prompt fission neutron spectra impact on a set of criticality and experimental reactor benchmarks

    International Nuclear Information System (INIS)

    Peneliau, Y.; Litaize, O.; Archier, P.; De Saint Jean, C.

    2014-01-01

    A large set of nuclear data are investigated to improve the calculation predictions of the new neutron transport simulation codes. With the next generation of nuclear power plants (GEN IV projects), one expects to reduce the calculated uncertainties which are mainly coming from nuclear data and are still very important, before taking into account integral information in the adjustment process. In France, future nuclear power plant concepts will probably use MOX fuel, either in Sodium Fast Reactors or in Gas Cooled Fast Reactors. Consequently, the knowledge of 239 Pu cross sections and other nuclear data is crucial issue in order to reduce these sources of uncertainty. The Prompt Fission Neutron Spectra (PFNS) for 239 Pu are part of these relevant data (an IAEA working group is even dedicated to PFNS) and the work presented here deals with this particular topic. The main international data files (i.e. JEFF-3.1.1, ENDF/B-VII.0, JENDL-4.0, BRC-2009) have been considered and compared with two different spectra, coming from the works of Maslov and Kornilov respectively. The spectra are first compared by calculating their mathematical moments in order to characterize them. Then, a reference calculation using the whole JEFF-3.1.1 evaluation file is performed and compared with another calculation performed with a new evaluation file, in which the data block containing the fission spectra (MF=5, MT=18) is replaced by the investigated spectra (one for each evaluation). A set of benchmarks is used to analyze the effects of PFNS, covering criticality cases and mock-up cases in various neutron flux spectra (thermal, intermediate, and fast flux spectra). Data coming from many ICSBEP experiments are used (PU-SOL-THERM, PU-MET-FAST, PU-MET-INTER and PU-MET-MIXED) and French mock-up experiments are also investigated (EOLE for thermal neutron flux spectrum and MASURCA for fast neutron flux spectrum). This study shows that many experiments and neutron parameters are very sensitive to

  4. Measurement of the fission cross-section of {sup 235}U and {sup 239}Pu for thermal neutrons; Mesures des sections de fission de {sup 235}U et de {sup 239}Pu en neutrons thermiques

    Energy Technology Data Exchange (ETDEWEB)

    Fraysse, G; Prosdocimi, A; Netter, F; Samour, C [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1965-07-01

    Improved techniques of fast detection have been applied for determining the fission cross-sections of {sup 235}U and {sup 239}Pu with reference to the absorption cross-section of Boron. Monochromatic neutron beams of 0.0322 eV, 0.0626 eV and 0.275 eV have been employed. Use has been made of a Xe-filled gaseous scintillator and of a low-geometry solid state ion chamber. Both measured alpha and fission rates. The results at the reference energy of 0.0253 eV are: ({sigma}{sub F}){sub 0} {sup 235}U = 588 {+-} 10 barns ({sigma}{sub F}){sub 0} {sup 239}Pu = 738 {+-} 7 barns. (authors) [French] Des techniques avancees de comptage rapide ont ete mise en oeuvre pour determiner la section efficace de fission de {sup 235}U et de {sup 239}Pu par rapport a celle d'absorption du bore. Des faisceaux de neutrons monochromatiques de 0,0322 eV, 0,0626 eV et 0,275 eV ont ete employes. Les detecteurs utilises sont un scintillateur gazeux rempli de xenon et une chambre d'ionisation a etat solide a basse geometrie. Les deux ont mesure les taux des desintegrations alpha et des fissions. Les resultats a l'energie de reference de 0,0253 eV sont: ({sigma}{sub F}){sub 0} {sup 235}U = 588 {+-} 10 barns ({sigma}{sub F}){sub 0} {sup 239}Pu = 738 {+-} 7 barns. (auteurs)

  5. Late aftereffect of inhailed 239Pu labelled with Ca or ZnDTPA

    International Nuclear Information System (INIS)

    Levdik, T.I.; Lyubchanskij, Eh.R.; Nifatov, A.P.

    1979-01-01

    Experiments made on rats showed that early (in 30 min and 3 h) aerosol therapy with Ca- or ZnDTPA and subsequent (during 2 months) intraperitoneal administration of respective DTPA salts after inhalation of 0.08-0.06 μCi of 239 Pu nitrate (pH 1.0) give ground to reduce the dose in the lungs from 915-690 down to 440-348 rad, in the skeleton from 74-64 down to 7.0-5.4 rad and also to provide the prolongation of the life span of rats from 522-602 up to 667-658 days. The incidence of inflammatory processes and malignant new growths undergoes no changes under the effect of complexonotherapy but the time of their development draws back, and the spectrum of tumours varies. In the treated rats the incidence of hemangiosarcomas of the lungs and osteosarcomas decreases and that of reticulosarcomas of the lungs increases. The life span of these animals is reduced by 100-150 days against the average in animals (16.6-26.2%) with severe inflammatory processes. The expediency of using antiinflammatory agents and the drugs raising the resistance of the body is discussed

  6. Isotopic yield measurement in the heavy mass region for 239Pu thermal neutron induced fission

    International Nuclear Information System (INIS)

    Bail, A.; Serot, O.; Mathieu, L.; Litaize, O.; Materna, T.; Koester, U.; Faust, H.; Letourneau, A.; Panebianco, S.

    2011-01-01

    Despite the huge number of fission yield data available in the different evaluated nuclear data libraries, such as JEFF-3.1.1, ENDF/B-VII.0, and JENDL-4.0, more accurate data are still needed both for nuclear energy applications and for our understanding of the fission process itself. It is within the framework of this that measurements on the recoil mass spectrometer Lohengrin (at the Institut Laue-Langevin, Grenoble, France) was undertaken, to determine isotopic yields for the heavy fission products from the 239 Pu(n th ,f) reaction. In order to do this, a new experimental method based on γ-ray spectrometry was developed and validated by comparing our results with those performed in the light mass region with completely different setups. Hence, about 65 fission product yields were measured with an uncertainty that has been reduced on average by a factor of 2 compared to that previously available in the nuclear data libraries. In addition, for some fission products, a strongly deformed ionic charge distribution compared to a normal Gaussian shape was found, which was interpreted as being caused by the presence of a nanosecond isomeric state. Finally, a nuclear charge polarization has been observed in agreement, with the one described on other close fissioning systems.

  7. Isotopic yield measurement in the heavy mass region for 239Pu thermal neutron induced fission

    Science.gov (United States)

    Bail, A.; Serot, O.; Mathieu, L.; Litaize, O.; Materna, T.; Köster, U.; Faust, H.; Letourneau, A.; Panebianco, S.

    2011-09-01

    Despite the huge number of fission yield data available in the different evaluated nuclear data libraries, such as JEFF-3.1.1, ENDF/B-VII.0, and JENDL-4.0, more accurate data are still needed both for nuclear energy applications and for our understanding of the fission process itself. It is within the framework of this that measurements on the recoil mass spectrometer Lohengrin (at the Institut Laue-Langevin, Grenoble, France) was undertaken, to determine isotopic yields for the heavy fission products from the 239Pu(nth,f) reaction. In order to do this, a new experimental method based on γ-ray spectrometry was developed and validated by comparing our results with those performed in the light mass region with completely different setups. Hence, about 65 fission product yields were measured with an uncertainty that has been reduced on average by a factor of 2 compared to that previously available in the nuclear data libraries. In addition, for some fission products, a strongly deformed ionic charge distribution compared to a normal Gaussian shape was found, which was interpreted as being caused by the presence of a nanosecond isomeric state. Finally, a nuclear charge polarization has been observed in agreement, with the one described on other close fissioning systems.

  8. Relative effectiveness of 239Pu and some other internal emitters for bone cancer induction in beagles

    International Nuclear Information System (INIS)

    Lloyd, R.D.; Miller, S.C.; Taylor, G.N.; Bruenger, F.W.; Jee, W.S.S.; Angus, W.

    1994-01-01

    The toxicity ratio (relative effectiveness per gray of average skeletal dose) has been estimated for bone cancer induction in beagles injected as young adults with a number of bone-seeking internal emitters. These experiments yielded calculated toxicity ratios (± SD) relative to 226 Ra = 1.0 of 239 Pu = 16 ± 5 (single exposure to monomeric Pu) and 32 ± 10 (continuous exposure from an extraskeletal deposit in the body), 224 Ra = 16 ± 5 (chronic exposure) and approximately 6 ± 2 (single exposure), 228 Th = 8.5 ± 2.3, 241 Am = 6 ± 0.8, 228 Ra = 2.0 ± 0.5, 249 Cf = 6 ± 3, 252 Cf = 4 ±2, 90 Sr = 1.0 ± 0.5 (for high doses) and 0.05 ± 0.03 (for low doses) and 0.01 ± 0.01 (for extremely low doses). Because no skeletal malignancies were observed among beagles given only 253 Es, the toxicity ratio is undefined. 43 refs., 2 tabs

  9. Effects of the herbicide glyphosate on the uptake of 239Pu and 241Am to vegetation

    International Nuclear Information System (INIS)

    Nisbet, A.F.; Shaw, S.

    1990-01-01

    Glyphosate (n-phosphonomethyl glycine) is a broad spectrum herbicide widely used in lowland agriculture, forestry and improved upland pastures. Although its metal chelating properties are well established, its interaction with radionuclides remains unknown. A pot experiment was conducted to determine the effect of soil applications of glyphosate on the uptake of 239 Pu and 241 Am to peas and carrots grown in loam, peat and sand soils. Soil-to-plant transfer factors were calculated for treated and untreated soils at harvest. The most marked effect was an increase in 241 Am uptake to crops grown in loam soil. Supplementary laboratory batch experiments were conducted by shaking radiolabelled soil and its associated soil solution with glyphosate. The activity concentration of 241 Am increased ten fold in the liquid phase of loam soils treated with glyphosate. It is postulated that this 241 Am desorption could have been mediated by the formation of a stable Am-glyphosate complex which was subsequently more available for crop uptake than Am alone. (author)

  10. Effects of combined inhalation exposure of rats to 239PuO2 and beryllium metal

    International Nuclear Information System (INIS)

    Finch, G.L.; Mewhinney, J.A.; Hoover, M.D.; Haley, P.J.; Cuddihy, R.G.; Griffith, W.C.; Boecker, B.B.

    1988-01-01

    We exposed rats acutely to achieve one of two initial lung burdens (ILBs) of 239 PuO 2 alone or in combination with one of three ILBs of beryllium metal. Additional control groups of rats were sham exposed to air. Currently, approximately 58% of all rats planned for inclusion have been exposed. This report describes procedures used for the exposure, maintenance, and evaluation of rats in this study. Most of the animals are to be held for their life span in order to quantitate cancer incidence, with other animals assigned to serial sacrifice groups for quantitation of Pu and Be retention and determination of translocation patterns. Exposure to beryllium at any of the three doses tested retarded clearance of plutonium from the lung by a factor of approximately six. Acute inflammatory responses were studied in a separate group of rats exposed to Be. Except for rats receiving the highest ILB of beryllium metal, no differences between exposed and sham-exposed control groups have yet been noted in terms of mortality, weight changes, and clinical signs. (author)

  11. Distribution of 239Pu and 241Am in the human skeleton

    International Nuclear Information System (INIS)

    McInroy, J.F.; Swint, M.J.

    1984-01-01

    The 241 Am and 239 Pu distribution in the skeletons of two former nuclear workers has been measured. The skeletons of both individuals appear to be within normal limits for Caucasian men about 50 y old. Both had lower limb bones that were heavier than the age controls and Case I had upper-body bones that were lighter than the age control group. The distribution of americium in the skeleton of Case I, 25 years post exposure, indicated that a more rapid turnover of initially deposited americium on the bone surfaces of cancellous bone, as compared to that deposited on the bone surfaces of compact bone, had occurred. This resulted in a larger proportion of americium located in the compact bone of the extremities and a lesser quantity in the more cancellous bones of the vertebral column, pelvis and rib cage. A similar shift in the distribution of plutonium occurred in Case II in the 35 y since initial deposition, but at a slower rate than that for americium. The ratio of each actinide in the liver to that in the systemic system (liver content/systemic system content) was 0.065 and 0.436, for americium and plutonium, respectively, suggesting that a much more rapid turnover of americium in the liver, compared to plutonium, provided a much larger fraction of that nuclide for circulatory feedback to the remodeling skeletal system. 8 references, 3 tables

  12. Using 239Pu as a tracer for fine sediment sources in the Daly River, Northern Australia

    Directory of Open Access Journals (Sweden)

    Lal R.

    2015-01-01

    Full Text Available The Daly River drains a large (52500 km2 and mainly undisturbed catchment in the Australian wet–dry tropics. Clearing and cropping since 2002 have raised concerns about possible increased sediment input into the river and motivated this study of its fine sediment sources. Using 239Pu as a tracer it is shown that the fine sediments originate mainly from erosion by gullying and channel change. Although the results also indicate that the surface soil contribution to the river channel sediments from sheet erosion has increased to 5-22% for the Daly River and 7-28% for the Douglas River (a tributary of the Daly River in 2009 vs. 3-6% for the Daly River and 4-9% for the Douglas River in 2005. This excess top soil likely originates from thecleared land adjacent to the Daly River since 2005. However, channel widening largely as a result of hydrologic change is still the dominant sediment source in this catchment.

  13. Incidence of liver tumors in beagles with body burdens of 239Pu or 241Am

    International Nuclear Information System (INIS)

    Taylor, G.N.; Mays, C.W.; Wrenn, M.E.; Shabestari, L.; Lloyd, R.D.

    1986-01-01

    Tetravalent 239 Pu or trivalent 241 Am in a citrate buffer, given via a single intravenous injection to beagles, induced very pronounced liver changes, usually at relatively long postinjection times. The lesions consisted of cell injury or cell necrosis which was followed by nodular hyperplasia and a significant incidence of primary liver tumors. The most frequent neoplasm was the bile duct adenoma, followed by the bile duct carcinoma. A lesser number of sarcomas were also induced, especially fibrosarcomas. The number of hepatic cell tumors was low. An abnormally high incidence of both hyperplastic nodules and primary liver tumors occurred at long postinjection times and at average doses extending down to ∼10 rads. The various nodular lesions and liver tumors frequently occurred as incidental findings in dogs dying from other causes, especially bone cancer. In comparison to bone neoplasia, the liver was a much less important target organ in the high-dose level groups, but in some of the low-dose groups, especially in the 241 Am groups, the risk of radiation-induced liver cancer was approximately equal to or exceeded the risk of skeletal tumors. However, in any projection of the risks observed in this animal model to man, one should be mindful that the beagle skeleton is approximately 25 times more sensitive to radiation-induced bone neoplasia than is the human skeleton (Mays et al., 1976) and that the radiosensitivity difference for the beagle and human liver is unknown. 41 refs., 8 figs., 5 tabs

  14. Performance of cladding on MOX fuel with low 240Pu/239Pu ratio

    International Nuclear Information System (INIS)

    McCoy, K.; Blanpain, P.; Morris, R.

    2015-01-01

    The U.S. Department of Energy has decided to dispose of a portion of its surplus plutonium by reconstituting it into mixed oxide (MOX) fuel and irradiating it in commercial power reactors. As part of fuel qualification, four lead assemblies were manufactured and irradiated to a maximum fuel rod average burnup of 47.3 MWd/kg heavy metal. This was the world's first commercial irradiation of MOX fuel with a 240 Pu/ 239 Pu ratio less than 0.10. Five fuel rods with varying burnups and plutonium contents were selected from one of the assemblies and shipped to Oak Ridge National Laboratory for hot cell examination. This paper discusses the results of those examinations with emphasis on cladding performance. Exams relevant to the cladding included visual and eddy current exams, profilometry, microscopy, hydrogen analysis, gallium analysis, and mechanical testing. There was no discernible effect of the type of MOX fuel on the performance of the cladding. (authors)

  15. Incidence of brain tumours in rats exposed to an aerosol of 239PuO2

    International Nuclear Information System (INIS)

    Sanders, C.L.; Dagle, G.E.; Mahaffey, J.A.

    1992-01-01

    Incidence of brain tumours was investigated in 3390 female and male Wistar rats exposed to an aerosol of 239 PuO 2 , or as sham-exposed controls. Lung doses ranged from 0.05 to 22 Gy. In females, six brain tumours were found in 1058 control rats (incidence, 0.6%) and 24 brain tumours in 2134 rats exposed to Pu (incidence, 1.1%); the survival-adjusted level of significance was p = 0.29 for comparing control with exposed females. In males, two brain tumours were found in 60 control rats (incidence, 3.3%) and seven brain tumours in 138 rats exposed to Pu (incidence, 5.1%); the survival-adjusted level of significance was p = 0.33. Brain tumour incidence was about five times greater in male than in female rats (p = 0.0001), a highly significant sex difference in brain tumour incidence. Tumour types were distributed similarly among control and Pu-exposed groups of both sexes; most were astrocytomas. Mean lifespans for rats with brain tumours were not significantly different between control and Pu-exposed rats. (author)

  16. Short Lived Fission Product Yield Measurements in 235U, 238U and 239Pu

    Science.gov (United States)

    Silano, Jack; Tonchev, Anton; Tornow, Werner; Krishichayan, Fnu; Finch, Sean; Gooden, Matthew; Wilhelmy, Jerry

    2017-09-01

    Yields of short lived fission products (FPYs) with half lives of a few minutes to an hour contain a wealth of information about the fission process. Knowledge of short lived FPYs would contribute to existing data on longer lived FPY mass and charge distributions. Of particular interest are the relative yields between the ground states and isomeric states of FPYs since these isomeric ratios can be used to determine the angular momentum of the fragments. Over the past five years, a LLNL-TUNL-LANL collaboration has made precision measurements of FPYs from quasi-monoenergetic neutron induced fission of 235U, 238U and 239Pu. These efforts focused on longer lived FPYs, using a well characterized dual fission chamber and several days of neutron beam exposure. For the first time, this established technique will be applied to measuring short lived FPYs, with half lives of minutes to less than an hour. A feasibility study will be performed using irradiation times of < 1 hour, improving the sensitivity to short lived FPYs by limiting the buildup of long lived isotopes. Results from this exploratory study will be presented, and the implications for isomeric ratio measurements will be discussed. This work was performed under the auspices of US DOE by LLNL under Contract DE-AC52-07NA27344.

  17. Risk estimates for lung tumors from inhaled 239PuO2, 238PuO2, and /sup 239Pu/(NO3)4 in beagle dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Park, J.F.; Gilbert, E.S.; Weller, R.E.

    1988-06-01

    Lung-cancer risks are being studied in beagle dogs given single exposures to aerosols of 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 . A major objective of these studies is to examine the risk of lung cancer relative to the specific activity of the radionuclide, rate of dose accumulation due to differences in solubilities of the radionuclides, and the presence of competing risk from extrapulmonary lesions. Dose-response relationships were studied for the three groups of dogs, with analyses specifically designed to evaluate differences in response. Based on estimated cumulative dose to the lung, risks were found to differ significantly among the radionuclides; they were highest for 239 Pu(NO 3 ) 4 and lowest for 238 PuO 2 . A model in which the risk was assumed to be a pure quadratic function of dose fit the data much better than a pure linear model. Currently, all three groups of dogs can be compared only to 10 years after exposure. However, it is apparent that the average cumulative dose to the lung may not be an adequate predictor of lung-cancer risk for different isotopic and physicochemical forms of plutonium. 13 refs., 2 tabs

  18. Proposal for Analysis of the Safeguarded Nuclear Materials 235U and 239Pu by Delayed Neutrons Technique

    International Nuclear Information System (INIS)

    El-Mongy, S.A.

    2000-01-01

    This paper introduces, describes and initiates a very sensitive and rapid non-destructive technique to be used for analysis of the safeguarded nuclear materials 235 U and 239 Pu. The technique is based on fission of the nuclear material by neutrons and then measuring the delayed neutrons produced from the neutron rich fission products. By this technique, fissile isotope content ( 235 U) can be determined in the presence of the other fissile (e.g. 239 Pu) or fertile isotopes (e.g. 238 U) in fresh and spent fuel. The time consumed for analysis of bulk materials by this technique is only 4 minutes. The method is also used for analysis of uranium in rock, sediment, soil, meteorites, lunar, biological, urine, archaeological, zircon sand and seawater samples. The method enables uranium in a sample to be measured without respect to its oxidation state, organic and inorganic elements

  19. Pulmonary retention and tissue distribution of 239Pu nitrate in F344 rats and syrian hamsters inhaling carbon tetrachloride

    International Nuclear Information System (INIS)

    Benson, J.M.; Barr, E.B.; Lundgren, D.L.; Nikula, K.J.

    1994-01-01

    Carbon tetrachloride (CCl 4 ) has been used extensively in the nuclear weapons industry, so it is possible that nuclear plant workers have been exposed to CCl 4 and plutonium compounds. Potential for future exposure exists during open-quotes cleanupclose quotes operations at weapon production sites such as the Hanford, Washington, and Rocky Flats, Colorado, facilities. The current Threshold Limit Value for CCl 4 is 5 ppm; however, concentrations of CCl 4 occurring in the nuclear weapons facilities over the past 40-50 y are unknown and may have exceeded this value. The pilot study described in this report is designed to determine whether subchronic inhalation of CCl 4 by CDF register (F-344)/CrlBR rats and Syrian golden hamsters, at concentrations expected to produce some histologic changes in liver, alters the hepatic retention and toxic effects of inhaled 239 Pu nitrate 239 Pu(NO 3 ) 4

  20. Exploratory study of fission product yield determination from photofission of 239Pu at 11 MeV with monoenergetic photons

    Science.gov (United States)

    Bhike, Megha; Tornow, W.; Krishichayan, Tonchev, A. P.

    2017-02-01

    Measurements of fission product yields play an important role for the understanding of fundamental aspects of the fission process. Recently, neutron-induced fission product-yield data of 239Pu at energies below 4 MeV revealed an unexpected energy dependence of certain fission fragments. In order to investigate whether this observation is prerogative to neutron-induced fission, a program has been initiated to measure fission product yields in photoinduced fission. Here we report on the first ever photofission product yield measurement with monoenergetic photons produced by Compton back-scattering of FEL photons. The experiment was performed at the High-Intensity Gamma-ray Source at Triangle Universities Nuclear Laboratory on 239Pu at Eγ=11 MeV. In this exploratory study the yield of eight fission products ranging from 91Sr to 143Ce has been obtained.

  1. Estimation of uncertainties in resonance parameters of {sup 56}Fe, {sup 239}Pu, {sup 240}Pu and {sup 238}U

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-05-01

    Uncertainties have been estimated for the resonance parameters of {sup 56}Fe, {sup 239}Pu, {sup 240}Pu and {sup 238}U contained in JENDL-3.2. Errors of the parameters were determined from the measurements which the evaluation was based on. The estimated errors have been compiled in the MF32 of the ENDF format. The numerical results are given in tables. (author)

  2. The effect of ν-bar(E) energy dependence at E 239Pu in the lower energy groups

    International Nuclear Information System (INIS)

    Gusejnov, A.G.; Gusejnov, M.A.; Rabotnov, N.S.

    1994-01-01

    The effect of the energy dependence of the average number of prompt neutrons on the 239 Pu fission BNAB-26 group cross-sections has been estimated. It was also found that the values of ν-bar(E) are lowered by approximately 1% when the temperature increases from 300 deg. K to 2000 deg. K. Taking this dependence into account may improve the predictability of the plutonium-fueled reactor characteristics. (author). 7 refs, 1 fig., 2 tabs

  3. Differences in the behavior of 233Pa, 237Np and 239 Pu in bentonite contaminated by sulfate-reducing bacteria

    International Nuclear Information System (INIS)

    Kudo, A.; Fujikawa, Y.; Takigami, H.; Zheng, J.; Asano, H.; Arai, K.; Yoshikawa, H.; Ito, M.

    1998-01-01

    The behaviors of 233 Pa, 237 Np and 239 Pu in high level radioactive wastes from nuclear fuel reprocessing were investigated by a laboratory experiment. Radioactive wastes are glassified and disposed of in geological repositories encased in bentonite as an additional artificial barrier to protect the environment. There is, however, the possibility that some anaerobic bacteria, especially sulfate-reducing bacteria, may flourish within the bentonite during the long disposal period (more than a century). The effects of sulfate-reducing bacteria on the behavior of the radionuclides within bentonite were investigated using the distribution coefficient (Kd) of 233 Pa, 237 Np and 239 Pu. The Kd was obtained with a 0.22 m membrane filter separating radionuclide contents in solid and liquid phases. The anaerobic bacteria, including sulfate-reducing bacteria, used for this investigation originated from the anaerobic treatment of pulp and paper waste and operated for more than one year at Eh around -85 mV. The bentonite used for this study was produced in Japan. The active anaerobic bacteria clearly accumulates considerable amounts of 233 Pa and 239 Pu by producing high Kd values of nearly 100,000, while Kds of 233 Pa and 239 Pu for the sterilized anaerobic bacteria were less than 10,000. In other words, live anaerobic bacteria can hold considerably higher amounts of the radionuclides compared to dead bacteria. Furthermore, high Kd values were obtained for anaerobic bacteria at pH 5-9. In contrast, Kd values for the radionuclide 237 Np were not influenced by the anaerobic bacteria but were controlled by chemical environmental conditions such as like pH. Another comparison was conducted for the radionuclides for mixtures of non-sterilized bacteria with bentonite. (author)

  4. Deposition of 239Pu in the skeleton and soft tissues of beagles: effect of age at time of injection

    International Nuclear Information System (INIS)

    Stevens, W.; Atherton, D.R.; Bates, D.; Bruenger, F.W.

    1976-01-01

    Previous reports from the laboratory have clearly defined the whole body deposition of 239 Pu in beagles injected as young adults (18 mo.). However, deposition has not been evaluated as a function of skeletal maturity at the time of injection. Juvenile beagles 3 months of age were injected with 0.1 μCi 239 Pu/kg in 0.08 M citrate buffer, pH 3.5. Six of these beagles have been sacrificed at short times after injection for distribution data. Another group receiving 3.0 μCi 239 Pu/kg was allowed to live until osteosarcoma developed and they were autopsied (1228 days average). Finally an aged beagle (81 mo.) was injected with 0.1 μCi/kg plutonium (P 2.0) and sacrificed 2 weeks later. Selected soft tissues, 1/2 of the symmetrical skeleton, and a known fraction of the asymmetrical skeleton were collected and analyzed for Pu content. Independent of the age at injection, a total of approximately 80 percent of the Pu was initially deposited in liver plus skeleton, however the age of the animal at time of injection altered the relative proportion in liver and skeleton in a reciprocal manner. The percent of the injected Pu found in the liver at 14 days P.I. increased with the increase in age at time of injection (13.2 percent at 3 months, 30.9 percent at 18 months and 36.9 percent at 81 months). The lower the age at injection, the larger was the fraction of 239 Pu deposited in the skeleton. The amounts ranged from an average of 69 percent in animals injected at 3 months to 49 percent in dogs injected at 18 months and 40 percent in the dog injected at 81 months of age. The difference in skeletal deposition reflects the different rates of bone growth and remodeling in juveniles, young adults and aged beagles

  5. Fission Product Yields for 14 MeV Neutrons on 235U, 238U and 239Pu

    International Nuclear Information System (INIS)

    Mac Innes, M.; Chadwick, M.B.; Kawano, T.

    2011-01-01

    We report cumulative fission product yields (FPY) measured at Los Alamos for 14 MeV neutrons on 235 U, 238 U and 239 Pu. The results are from historical measurements made in the 1950s–1970s, not previously available in the peer reviewed literature, although an early version of the data was reported in the Ford and Norris review. The results are compared with other measurements and with the ENDF/B-VI England and Rider evaluation. Compared to the Laurec (CEA) data and to ENDF/B-VI evaluation, good agreement is seen for 235 U and 238 U, but our FPYs are generally higher for 239 Pu. The reason for the higher plutonium FPYs compared to earlier Los Alamos assessments reported by Ford and Norris is that we update the measured values to use modern nuclear data, and in particular the 14 MeV 239 Pu fission cross section is now known to be 15–20% lower than the value assumed in the 1950s, and therefore our assessed number of fissions in the plutonium sample is correspondingly lower. Our results are in excellent agreement with absolute FPY measurements by Nethaway (1971), although Nethaway later renormalized his data down by 9% having hypothesized that he had a normalization error. The new ENDF/B-VII.1 14 MeV FPY evaluation is in good agreement with our data.

  6. Determination of 240Pu/239Pu isotope ratios in Kara Sea and Novaya Zemlya sediments using accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Oughton, D.H.; Skipperud, L.; Salbu, B.; Fifield, L.K.; Cresswell, R.C.; Day, J.P.

    1999-01-01

    Accelerator mass spectrometry (AMS) has been used to determine Pu activity concentrations and 240 Pu/ 239 Pu isotope ratios in sediments from the Kara Sea and radioactive waste dumping sites at Novaya Zemlya. Measured 239,240 Pu activities ranged from 0.06 - 9.8 Bq/kg dry weight, 240 Pu/ 239 Pu atom ratios ranged from 0.13 to 0.28, and 238 Pu/ 239,240 Pu activity ratios from 0.02 to 0.6. Perturbations from global fallout isotope ratios were evident at three sites: the Yenisey Estuary and Abrosimov Fjords where 240 Pu/ 239 Pu ratios were lower (0.13-0.14); and Stepovogo Fjord sediments where ratios were higher (up to 0.28) than fallout ratios. Based on procedural blanks, detection limits for AMS were below 1 fg Pu and the method showed good precision for isotope ratio measurements, minimal matrix, interference and memory effects. For high level samples, comparison between alpha spectrometry and AMS gave good agreement for measurement of 239,240 Pu activity concentrations. (author)

  7. Analysis of plutonium isotope ratios including 238Pu/239Pu in individual U-Pu mixed oxide particles by means of a combination of alpha spectrometry and ICP-MS.

    Science.gov (United States)

    Esaka, Fumitaka; Yasuda, Kenichiro; Suzuki, Daisuke; Miyamoto, Yutaka; Magara, Masaaki

    2017-04-01

    Isotope ratio analysis of individual uranium-plutonium (U-Pu) mixed oxide particles contained within environmental samples taken from nuclear facilities is proving to be increasingly important in the field of nuclear safeguards. However, isobaric interferences, such as 238 U with 238 Pu and 241 Am with 241 Pu, make it difficult to determine plutonium isotope ratios in mass spectrometric measurements. In the present study, the isotope ratios of 238 Pu/ 239 Pu, 240 Pu/ 239 Pu, 241 Pu/ 239 Pu, and 242 Pu/ 239 Pu were measured for individual Pu and U-Pu mixed oxide particles by a combination of alpha spectrometry and inductively coupled plasma mass spectrometry (ICP-MS). As a consequence, we were able to determine the 240 Pu/ 239 Pu, 241 Pu/ 239 Pu, and 242 Pu/ 239 Pu isotope ratios with ICP-MS after particle dissolution and chemical separation of plutonium with UTEVA resins. Furthermore, 238 Pu/ 239 Pu isotope ratios were able to be calculated by using both the 238 Pu/( 239 Pu+ 240 Pu) activity ratios that had been measured through alpha spectrometry and the 240 Pu/ 239 Pu isotope ratios determined through ICP-MS. Therefore, the combined use of alpha spectrometry and ICP-MS is useful in determining plutonium isotope ratios, including 238 Pu/ 239 Pu, in individual U-Pu mixed oxide particles. Copyright © 2016 Elsevier B.V. All rights reserved.

  8. Use of fission track analysis technique for the determination of MicroBequerel level of {sup 239}Pu in urine samples from radiation workers handling MOX fuel

    Energy Technology Data Exchange (ETDEWEB)

    Yadav, J.R., E-mail: yadav_jogendra@rediffmail.co [Health Physics Laboratory, Health Physics Division, BARC, Tarapur 401502 (India); Rao, D.D.; Kumar, Ranjeet [Health Physics Laboratory, Health Physics Division, BARC, Tarapur 401502 (India); Aggarwal, S.K. [Fuel chemistry Division, BARC, Trombay, Mumbai 400085 (India)

    2011-07-15

    Fission track analysis (FTA) technique for the determination of {sup 239}Pu excreted through urine has been standardized using blank samples, tracer and {sup 239}Pu spikes. Double stage anion exchange separation protocol has been applied and an average radiochemical recovery of {sup 239}Pu of 18% was obtained. An average track registration efficiency of 11 tracks per {mu}Bq of {sup 239}Pu, irradiated to 0.35x10{sup 17} neutron fluence was established. Reagent blank urine samples from 11 controlled subjects were analyzed by FTA and an average of 149{+-}14 tracks was obtained. Minimum detectable activity of 34 {mu}Bq L{sup -1} of urine sample was obtained and will be useful for monitoring chronic exposure cases handling MOX fuel.

  9. The biochemical mechanisms responsible for differences in the half-life of monomeric 239Pu in rat and Syrian hamster liver

    International Nuclear Information System (INIS)

    Seidel, A.; Winter, R.; Jentzsch, C.; Gruner, R.; Heumann, H.G.; Hanke, S.

    1979-01-01

    The subcellular distribution of 239 Pu citrate in rat and Syrian hamster liver was studied with the help of the non-ionic detergent Triton WR1339, used as method for separating lysosomes from other cell organelles. Triton WR1339 was injected six days after 239 Pu and the animals were sacrificed after Day 10. Liver homogenates were subjected to differential and isopycnic centrifugation in sucrose gradients. In both animal species 90% of 239 Pu of the post-nuclear supernatant was found in the fraction containing mitochondria, lysosomes, endoplasmatic reticulum and ferritin. Triton WR1339 injection caused a concomitant shift of the lysosomal marker acid phosphatase and of 239 Pu from high densities to rho approximately 1.10 in both animal species. According to our results, binding of 239 Pu to mitochondria and peroxisomes can be excluded, and association to endoplasmatic reticulum and plasma membranes is not very probable. We must consider the possibility that a part of the radioactivity occurring at rho approximately 1.10 can also be bound to ferritin. According to these findings, lysosomes could be one of the main storage sites for 239 Pu in both species. From studies on the pharmacokinetics of 3 H-labelled Triton WR1339 and on the behaviour of Triton-filled rat liver lysosomes, which are also presented in the paper, it is tentatively concluded that the rapid excretion of 239 Pu from rat liver is due to the normally rapid elimination of lysosomal material from hepatocytes into the bile in this species. In Syrian hamsters the fate of lysosomal material in liver may be different or redistribution of 239 Pu occurs at a later time. (author)

  10. Total and fission cross-sections of 239Pu - statistical study of resonance parameters

    International Nuclear Information System (INIS)

    Derrien, H.; Blons, J.; Eggermann, C.; Michaudon, A.; Paya, D.; Ribon, P.

    1967-01-01

    The authors measured the total and fission cross-sections of 239 Pu with the linear accelerator at Saclay as a pulsed source of neutrons. The total cross-section was measured in the range from 4 to 700 eV and the best resolution used was 1.5 ns/m; the fission cross-section was measured between 4 eV and 6 keV, the best resolution having been 6 ns/m. The transmission measurements on five samples were made at the temperature of liquid nitrogen, and comparisons made with supplementary experiments at ambient temperature made it possible to determine the Doppler broadening factor (Δ = η√E). The resonances were identified from 4 to 500 eV in the total cross-section; the average level spacing was of the order of 2.4 eV. It would appear that, in this energy range, nearly all the levels were identified. The resonance parameters were determined by analysis of shape in conjunction with a least-squares programme on an IBM-7094 computer. The existence of a large number of broad resonances corresponding to very large fission widths has been shown to exist. Statistical study of the fission widths actually shows the existence of two families of resonances, one corresponding to a mean Γ f of the order of 45 meV and the other to a mean Γ/f of about 750 meV. The authors were therefore able to postulate a classification of resonances in terms of two spin states, the level population ratio in each family being: (2J 1 +1)/(2J 2 +1) = 1/3; J 1 = 0 corresponds to the broad resonances and J 2 = 1 to the narrow ones. The partial widths for radiative capture fluctuate slightly around a mean value of 40 meV. By using a multilevel programme, the authors were able to investigate the extent to which the existence of large fission widths might give rise to fictitious resonances (quasi-resonances) and perturbations and also to make a statistical study of the resonance parameters. (author) [fr

  11. Modification of analytical method for measurement of 239Pu, 240Pu and 241Am in sediment and sea water

    International Nuclear Information System (INIS)

    Syarbaini; Tarigan, C.; Rustam, M.F.

    1997-01-01

    Modification of analytical method for measurement of 239 Pu, 240 Pu and 241 Am in sediment and sea water have been conducted. This study is to develop a method for separation of 239 Pu, 240 Pu and 241 Am from 100-300 g of sediment and 100-200 l of sea water samples. Most of the methods described in the literature are to separation of '2 39 Pu, '2 40 Pu and 241 Am from 20-50 g of sediment and 30-100 l of sea water samples. By this method, 239,240 Pu and 241 Am were concentrated using the coprecipitation of CaC 2 O 4 and Fe (OH) 3 . Plutonium-242 and Curium-244 were used as tracer to determine chemical recovery. The result of analysis of some sediment samples showed that the chemical recoveries were respectively obtained in the range of 59.7 to 72.6% with average of 66.2 % for 242 Pu and 72.0 % to 85.5 % with average 78.8 % for 244 Cm. Analysis of some sea water samples were obtained in the range of 67 % to 78 % with average 73.9 % for 242 Pu and 74.0 % to 90.0 % with average 84.2 % for '2 42 Cm. This method was tested by the IAEA marine sediment, the result was excellent agreement with the IAEA certified sediment. It could be suggested that the developed analytical method is suitable to analyze the low level 239 Pu, 240 Pu and 241 Am in sediment and sea water samples (author)

  12. 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)

  13. Determination of Plutonium Activity Concentrations and 240Pu/239Pu Atom Ratios in Brown Algae (Fucus distichus) Collected from Amchitka Island, Alaska

    International Nuclear Information System (INIS)

    Hamilton, T F; Brown, T A; Marchetti, A A; Martinelli, R E; Kehl, S R

    2005-01-01

    Plutonium-239 ( 239 Pu) and plutonium-240 ( 240 Pu) activity concentrations and 240 Pu/ 239 Pu atom ratios are reported for Brown Algae (Fucus distichus) collected from the littoral zone of Amchitka Island (Alaska) and at a control site on the Alaskan peninsula. Plutonium isotope measurements were performed in replicate using Accelerator Mass Spectrometry (AMS). The average 240 Pu/ 239 Pu atom ratio observed in dried Fucus d. collected from Amchitka Island was 0.227 ± 0.007 (n=5) and compares with the expected 240 Pu/ 239 Pu atom ratio in integrated worldwide fallout deposition in the Northern Hemisphere of 0.1805 ± 0.0057 (Cooper et al., 2000). In general, the characteristically high 240 Pu/ 239 Pu content of Fucus d. analyzed in this study appear to indicate the presence of a discernible basin-wide secondary source of plutonium entering the marine environment. Of interest to the study of plutonium source terms within the Pacific basin are reports of elevated 240 Pu/ 239 Pu atom ratios in fallout debris from high-yield atmospheric nuclear tests conducted in the Marshall Islands during the 1950s (Diamond et al., 1960), the wide range of 240 Pu/ 239 Pu atom ratio values (0.19 to 0.34) observed in sea water, sediments, coral and other environmental media from the North Pacific Ocean (Hirose et al., 1992; Buesseler, 1997) and updated estimates of the relative contributions of close-in and intermediate fallout deposition on oceanic inventories of radionuclidies, especially in the Northern Pacific Ocean (Hamilton, 2004)

  14. Rapid determination of 239Pu in urine samples using molecular recognition technology product AnaLigRPu-02 gel

    International Nuclear Information System (INIS)

    Silvia Dulanska; Boris Remenec; Jan Bilohuscin; Miroslav Labaska; Bianka Horvathova; Andrej Matel

    2013-01-01

    This paper describes the use of IBC's AnaLig R Pu-02 molecular recognition technology product to effectively and selectively pre-concentrate, separate and recover plutonium from urine samples. This method uses two-stage column separations consisting of two different commercial products, Eichrom's Pre-filter Material and AnaLig R Pu-02 resin from IBC Advanced Technologies. By eliminating the co-precipitation techniques and the ashing steps to remove residual organics, the analysis time was reduced significantly. The method was successfully tested by adding known activities of reference solutions of 242 Pu and 239 Pu to urine samples. (author)

  15. R matrix analysis of 239Pu neutron cross sections in the energy range up to 1000 eV

    International Nuclear Information System (INIS)

    de Saussure, G.; Perez, R.B.

    1990-01-01

    This paper reports on the results of an R matrix analysis of the 239 Pu neutron cross sections up to 1000-eV neutron energy. The analysis was performed with the multilevel multichannel Reich-Moore code SAMMY. The method of analysis is describe, and the selection of experimental data is discussed. Some tabular and graphical comparisons between calculated and measured cross sections and transmissions are presented. The statistical properties of the resonance parameters are examined. The resonance parameters are proposed for the new evaluated data files ENDF/B-VI and JEF2

  16. Surrogate 239Pu(n, fxn) and 241Pu(n, fxn) average fission-neutron-multiplicity measurements

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Alan, B. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Akindele, O. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Casperson, R. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hughes, R. O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Fisher, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-09-26

    We have constructed a new neutron-charged-particle detector array called NeutronSTARS. It has been described extensively in LLNL-TR-703909 [1] and Akindele et al [2]. We have used this new neutron-charged-particle array to measure the 241Pu and 239Pu fissionneutron multiplicity as a function of equivalent incident-neutron energy from 100 keV to 20 MeV. The experimental approach, detector array, data analysis, and results are summarized in the following sections.

  17. Commentary on inhaled {sup 239}PuO{sub 2} in dogs - a prophylaxis against lung cancer?

    Energy Technology Data Exchange (ETDEWEB)

    Cuttler, J.M., E-mail: jerrycuttler@rogers.com [Cuttler and Associates, Vaughan, ON (Canada); Feinendegen, L. [Brookhaven National Laboratories, Upton, NY (United States)

    2015-07-01

    Several studies on the effect of inhaled plutonium-dioxide particulates and the incidence of lung tumors in dogs reveal beneficial effects when the cumulative alpha-radiation dose is low. There is a threshold at an exposure level of about 100 cGy for excess tumor incidence and reduced lifespan. The observations conform to the expectations of the radiation hormesis dose-response model and contradict the predictions of the Linear No-Threshold (LNT) hypothesis. These studies suggest investigating the possibility of employing low-dose alpha-radiation, such as from {sup 239}PuO{sub 2} inhalation, as a prophylaxis against lung cancer. (author)

  18. Commentary on inhaled {sup 239}PuO{sub 2} in dogs - a prophylaxis against lung cancer?

    Energy Technology Data Exchange (ETDEWEB)

    Cuttler, J.M. [Cuttler and Assoc., Vaughan, Ontario (Canada); Feinendegen, L. [Brookhaven National Laboratories, Upton, New York (United States)

    2015-06-15

    Several studies on the effect of inhaled plutonium-dioxide particulates and the incidence of lung tumors in dogs reveal beneficial effects when the cumulative alpha-radiation dose is low. There is a threshold at an exposure level of about 100 cGy for excess tumor incidence and reduced lifespan. The observations conform to the expectations of the radiation hormesis dose-response model and contradict the predictions of the Linear No-Threshold (LNT) hypothesis. These studies suggest investigating the possibility of employing low-dose alpha-radiation, such as from {sup 239}PuO {sub 2} inhalation, as a prophylaxis against lung cancer. (author)

  19. Evaluation of covariances for resolved resonance parameters of 235U, 238U, and 239Pu in JENDL-3.2

    International Nuclear Information System (INIS)

    Kawano, Toshihiko; Shibata, Keiichi

    2003-02-01

    Evaluation of covariances for resolved resonance parameters of 235 U, 238 U, and 239 Pu was carried out. Although a large number of resolved resonances are observed for major actinides, uncertainties in averaged cross sections are more important than those in resonance parameters in reactor calculations. We developed a simple method which derives a covariance matrix for the resolved resonance parameters from uncertainties in the averaged cross sections. The method was adopted to evaluate the covariance data for some important actinides, and the results were compiled in the JENDL-3.2 covariance file. (author)

  20. Applicability of 239Pu as a tracer for soil erosion in the wet-dry tropics of northern Australia

    Science.gov (United States)

    Lal, R.; Tims, S. G.; Fifield, L. K.; Wasson, R. J.; Howe, D.

    2013-01-01

    The technique of accelerator mass spectroscopy (AMS) has been employed to determine modern soil loss rates through the analysis of 239Pu profiles in soil cores from the Daly basin in Northern Territory, Australia. In areas in which soil conservation banks were not present or were only added recently (banks in other parts of the catchment. High intensity seasonal rainfall combined with reduction in land cover due to grazing and episodic bush fires are primary factors influencing erosion although other impacts on the landscape such as tillage generated runoff and land clearing seem to be responsible for accelerated sediment production.

  1. Skeletal retention of 239Pu and 226Ra in beagles injected at ages ranging from 2 days to 5 years

    International Nuclear Information System (INIS)

    Bruenger, F.W.; Stevens, W.; Atherton, D.R.; Jee, W.S.S.; Smith, J.M.

    1982-01-01

    The age at exposure significantly affects the retention and distribution of 226 Ra and 239 Pu, both of which deposit in the skeleton, although in different patterns. Beagles aged 2 days (neonates), 90 days (juveniles), 18 months (young adults) or 5 years (old), received a single injection of one of these nuclides at a dosage level at which no significant acute effects have been observed. Nuclide concentrations in plasma and the skeleton were determined and retention equations were calculated. Initial deposition and retention of the two nuclides were age-dependent, but differences between the growing and young adult beagles were much greater than between the young adult and old beagles

  2. Modifying effects of pre-existing fibrosis in rats exposed to aerosols of {sup 239}PuO{sub 2}. II

    Energy Technology Data Exchange (ETDEWEB)

    Lundgren, D L; Mauderly, J L; Gillett, N A; Hahn, F F

    1988-12-01

    We have initiated a study using rats to determine the modifying effects of pre-existing pulmonary fibrosis on the retention and biological effects of inhaled {sup 239}PuO{sub 2}. Pulmonary fibrosis was induced by intratracheal instillation of 8.5 IU/kg body weight of bleomycin at 45 to 49 days before inhalation exposure to an aerosol of {sup 239}PuO{sub 2}. The clearance of {sup 239}Pu from the lungs of rats was decreased significantly (p < 0.01) in rats with pre-existing pulmonary fibrosis compared with controls. Respiratory function, lung morphometric measurements and histological evaluations were all consistent with the presence of mild pulmonary fibrosis in the rats treated with bleomycin. Pre-existing pulmonary fibrosis resulted in an increased retention of the initial lung burdens of {sup 239}Pu, apparently by entrapping the particles in fibrotic areas of the lung. The life span of the rats with pulmonary fibrosis was decreased by up to 25% compared with control rats having similar initial lung burdens of {sup 239}Pu. (author)

  3. Association of 239Pu with lysosomes in rat, Syrian hamster, and Chinese hamster liver as studied by carrier-free electrophoresis and electron microscopic autoradiography with 241Pu

    International Nuclear Information System (INIS)

    Seidel, A.; Krueger, E.W.; Wiener, M.; Hotz, G.; Balani, M.; Thies, W.G.

    1985-01-01

    The binding of injected monomeric plutonium in the liver of rats, Syrian hamsters, and Chinese hamsters (species which show profound differences in their ability to eliminate 239 Pu from the liver) was investigated by carrier-free electrophoresis using 239 Pu and electron microscopic autoradiography with 241 Pu. These studies are part of a program designed to obtain a better understanding of the mechanisms of the clearance of transuranium elements from liver of different mammals and man. Between 4 and 9 days after nuclide injection, a clear correlation between the majority of the 239 Pu and lysosomal enzymes was observed when the mitochondrial-lysosomal (ML) fraction of the livers was analyzed by carrier-free electrophoresis. In the two hamster species, a second 239 Pu peak exists from the beginning and increases with time to comprise 50% of the total radioactivity at later times. During electron microscopic examination 4 days after 241 Pu injection, beta tracks were frequently observed over globular structures resembling dense bodies in Chinese hamster liver. They were also observed frequently over chromatin-rich portions of the cell nuclei. These results, together with those from previous density gradient studies, show that lysosomes are the primary deposition site for 239 Pu in the liver cytoplasm of these three rodent species. The hypothesis of a morphologic transformation of these lysosomes with time in hamster liver and of rapid bulk exocytosis of the lysosomes in rats are still possible explanations for the extreme differences in the elimination among the three species

  4. Comparison of the subcellular distribution of monomeric 239Pu and 59Fe in the liver of rat, mouse, and Syrian and Chinese hamsters

    International Nuclear Information System (INIS)

    Winter, R.; Seidel, A.

    1982-01-01

    The subcellular distribution of 239 Pu and 59 Fe 10 days after intravenous injection as a citrate complex was investigated by sucrose density gradient centrifugation in the liver of rat, mouse, and Syrian and Chinese hamsters. Lysosomes were separated from other cell constituents by injection of the nonionic detergent Triton WR 1339 4 days before sacrifice. The Triton-induced decrease in the density of the lysosomes was very similar in all four animal species and was followed closely by a corresponding decrease of the median density of the 239 Pu profiles in rat, mouse, and, to a smaller extent, Syrian hamster. However, in Chinese hamster a clear correspondence between lysosomes and 239 Pu was not found 10 days after nuclide injection. It was concluded that lysosomes are the main storage organelles fo 239 Pu in the liver of rat and mouse and that in all four animal species mitochondria and endoplasmic reticulum do not play any significant role in binding the radionuclide. The relevance of pericellular membranes has to be checked. The distribution patterns of 59 Fe and 239 Pu were quite different

  5. Neutron and gamma-ray spectra of {sup 239}PuBe and {sup 241}AmBe

    Energy Technology Data Exchange (ETDEWEB)

    Vega-Carrillo, H.R. E-mail: rvega@cantera.reduaz.mx; Manzanares-Acuna, Eduardo; Becerra-Ferreiro, A.M.; Carrillo-Nunez, Aureliano

    2002-08-01

    Neutron and gamma-ray spectra of {sup 239}PuBe and {sup 241}AmBe were measured and their dosimetric features were calculated. Neutron spectra were measured using a multisphere neutron spectrometer with a {sup 6}LiI(Eu) scintillator. The {sup 239}PuBe neutron spectrum was measured in an open environment, while the {sup 241}AmBe neutron spectrum was measured in a closed environment. Gamma-ray spectra were measured using a NaI(Tl) scintillator using the same experimental conditions for both sources. The effect of measuring conditions for the {sup 241}AmBe neutron spectrum indicates the presence of epithermal and thermal neutrons. The low-resolution neutron spectra obtained with the multisphere spectrometer allows one to calculate the dosimetric features of neutron sources. At 100 cm both sources produce approximately the same count rate as that of the 4.4 MeV gamma-ray per unit of alpha emitter activity.

  6. Neutron induced fission cross sections for 232Th, 235,238U, 237Np, and 239Pu

    International Nuclear Information System (INIS)

    Lisowski, P.W.; Ullmann, J.L.; Balestrini, S.J.; Hill, N.W.; Carlson, A.D.; Wasson, O.A.

    1989-01-01

    Neutron-induced fission cross section ratios for samples of 232 Th, 235,238 U, 237 Np and 239 Pu have been measured from 1 to 400 MeV. The fission reaction rate was determined for all samples simultaneously using a fast parallel plate ionization chamber at a 20-m flight path. A well characterized annular proton recoil telescope was used to measure the neutron fluence from 3 to 30 MeV. Those data provided the shape of the 235 U(n,f) cross section relative to the hydrogen scattering cross section. That shape was then normalized to the very accurately known value for 235 U(n,f) at 14.178 MeV. From 30 to 400 MeV cross section values were determined using the neutron fluence measured with a plastic scintillator. Cross section values of 232 Th, 235,238 U, 237 Np and 239 Pu were computed from the ratio data using the authors' values for 235 U(n,f). In addition to providing new results at high neutron energies, these data highlight several areas of deficiency in the evaluated nuclear data files and provide new information for the 235 U(n,f) standard

  7. New data on the toxicity and translocation of inhaled /sup 239/PuO/sub 2/ in baboons

    Energy Technology Data Exchange (ETDEWEB)

    Metivier, H.; Masse, R.; Rateau, G.; Nolibe, D.; Lafuma, J. (CEA Centre d' Etudes de Bruyeres-le-Chatel, 91 (France))

    1989-01-01

    In 1973-1974, baboons were exposed to a polydispersed aerosol of /sup 239/PuO/sub 2/, prepared at 1000/sup 0/C, at the Commissariat a l'Energie Atomique in France. The data published in 1978 for these baboons were used by Bair et al (1980), for comparison with those obtained in beagles exposed to /sup 239/PuO/sub 2/ at the Pacific Northwest Laboratory, USA. Since our 1978 publication, 8 baboons have died or were killed by euthanasia when moribund, and 11 were still alive when the present report was drafted. Two of the eight baboons died of lung squamous cell carcinoma at 2171 and 2528 days respectively. The remaining 6 died of fibrosis, interstitial pneumonia or diseases unrelated to Pu toxicity. The relationship observed in the eight baboons between initial lung burden and survival time shows that their lifespan was longer than expected from the data curve based on the findings for the first 1000 days. However, this increased survival time was not observed if the lifespan was expressed as a function of the average lung burden. (author).

  8. Long-term consequences of 239PuO2 exposure in dogs: persistent T lymphocyte dysfunction

    International Nuclear Information System (INIS)

    Davila, D.R.; Guilmette, R.A.; Bice, D.E.; Muggenburg, B.A.; Swafford, D.S.; Haley, P.J.

    1992-01-01

    Young Beagle dogs were exposed by inhalation to aerosols of 239 PuO 2 and observed for their lifespans. The purpose was to compare certain immune responses of the 239 PuO 2 -exposed dogs at middle age (7-10 years old) and old age (12-14 years old), with those of unexposed, age-matched or young (3-4 years old) animals. Some of the aged, exposed dogs had developed lung tumours. Lymphocyte proliferative responses to phytohaemagglutinin (PHA) were lower in aged control dogs than in either young or middle-aged control dogs. Both aged and middle-aged, radiation-exposed dogs had decreased responses to PHA when compared to age-matched controls. Responses to concanavalin A (Con A) were not affected by age in control dogs, but tended to decrease in the oldest group of radiation-exposed dogs. Responses to both PHA and Con A were severely depressed in tumour-bearing dogs. The cytolytic activity of natural killer cells was not affected by age, radiation exposure, or tumour presence. (author)

  9. Measurement of 239Pu in urine samples at ultra-trace levels using a 1 MV compact AMS system

    International Nuclear Information System (INIS)

    Hernandez-Mendoza, H.; Chamizo, E.; Yllera, A.; Garcia-Leon, M.; Delgado, A.

    2010-01-01

    Routine bioassay monitoring of Pu intake in exposed workers of research and nuclear industry is usually performed by alpha spectrometry. This technique involves large sample volumes of urine and time-consuming preparative and counting protocols. Compact accelerator mass spectrometry (AMS) facilities make feasible the determination of ultra low-level Pu activity concentrations and Pu isotopic ratios in biological samples (blood, urine and feces), being a rapid and cost-effective measurement technique. The plutonium results in urine samples presented here have been obtained on the 1 MV compact AMS system sited at the Centro Nacional de Aceleradores (CNA), in Seville, Spain. In this work, a different methodological approach has been developed alternative to the 'classical' preparation of urine samples for alpha spectrometry. The procedure avoids the Pu precipitation step, and involves acid sample evaporation and acid digestion in a microwave oven. Finally, purification of plutonium was achieved by using chromatography columns filled up with BioRad AG1X2 anion exchange resin (Bio-Rad Laboratories Inc.). The total time needed for analysis is about 10 h, unlike the 'classical' methods based on alpha spectrometry which need about 1 week. At present, it has been demonstrated that this method allows quantifying 239 Pu activity concentrations in urine of, at least, 30 μBq (13 fg 239 Pu). We can conclude that the procedure would be suitable to perform in vitro routine bioassay measurements. Moreover, the innovative application of AMS opens new and interesting analytical alternatives in this field.

  10. Nuclear data evaluation for 239Pu in the energy region 100 075. ev - 15 MeV

    International Nuclear Information System (INIS)

    Antsipov, G.V.; Bakhanovich, L.A.; Zharkov, V.F.

    1981-06-01

    The present work incorporates the results of the new nuclear data evaluation for 239 Pu. The complete file compiled by the authors in 1974 was practically completely re-examined. The most substantial changes were made above 0.5 keV. In the region of unresolved resonances (0.3-100 keV), the channel contribution to the process widths for a given state and some other aspects were taken into account. The fission cross section and the α-value were evaluated with regard for the correlation of experimental errors. The non-spherical potential with optimized parameters was used to make calculations by the optical and statistical models. The contribution of pre-equilibrium emission was taken into account in calculations of secondary neutron spectra. The new standard anti nusub(sp)( 252 Csub(f)) was used to calculate anti nusub(p). The 26-group constants and g-Westcott factors were obtained from the evaluated data. The complete file of the evaluated data for 239 Pu is presented in the ENDF/B format and conveyed to the Nuclear Data Section of the IAEA. (author)

  11. Fission Product Yields of 233U, 235U, 238U and 239Pu in Fields of Thermal Neutrons, Fission Neutrons and 14.7-MeV Neutrons

    Science.gov (United States)

    Laurec, J.; Adam, A.; de Bruyne, T.; Bauge, E.; Granier, T.; Aupiais, J.; Bersillon, O.; Le Petit, G.; Authier, N.; Casoli, P.

    2010-12-01

    The yields of more than fifteen fission products have been carefully measured using radiochemical techniques, for 235U(n,f), 239Pu(n,f) in a thermal spectrum, for 233U(n,f), 235U(n,f), and 239Pu(n,f) reactions in a fission neutron spectrum, and for 233U(n,f), 235U(n,f), 238U(n,f), and 239Pu(n,f) for 14.7 MeV monoenergetic neutrons. Irradiations were performed at the EL3 reactor, at the Caliban and Prospero critical assemblies, and at the Lancelot electrostatic accelerator in CEA-Valduc. Fissions were counted in thin deposits using fission ionization chambers. The number of fission products of each species were measured by gamma spectrometry of co-located thick deposits.

  12. First measurements of (236)U concentrations and (236)U/(239)Pu isotopic ratios in a Southern Hemisphere soil far from nuclear test or reactor sites.

    Science.gov (United States)

    Srncik, M; Tims, S G; De Cesare, M; Fifield, L K

    2014-06-01

    The variation of the (236)U and (239)Pu concentrations as a function of depth has been studied in a soil profile at a site in the Southern Hemisphere well removed from nuclear weapon test sites. Total inventories of (236)U and (239)Pu as well as the (236)U/(239)Pu isotopic ratio were derived. For this investigation a soil core from an undisturbed forest area in the Herbert River catchment (17°30' - 19°S) which is located in north-eastern Queensland (Australia) was chosen. The chemical separation of U and Pu was carried out with a double column which has the advantage of the extraction of both elements from a relatively large soil sample (∼20 g) within a day. The samples were measured by Accelerator Mass Spectrometry using the 14UD pelletron accelerator at the Australian National University. The highest atom concentrations of both (236)U and (239)Pu were found at a depth of 2-3 cm. The (236)U/(239)Pu isotopic ratio in fallout at this site, as deduced from the ratio of the (236)U and (239)Pu inventories, is 0.085 ± 0.003 which is clearly lower than the Northern Hemisphere value of ∼0.2. The (236)U inventory of (8.4 ± 0.3) × 10(11) at/m(2) was more than an order of magnitude lower than values reported for the Northern Hemisphere. The (239)Pu activity concentrations are in excellent agreement with a previous study and the (239+240)Pu inventory was (13.85 ± 0.29) Bq/m(2). The weighted mean (240)Pu/(239)Pu isotopic ratio of 0.142 ± 0.005 is slightly lower than the value for global fallout, but our results are consistent with the average ratio of 0.173 ± 0.027 for the southern equatorial region (0-30°S). Copyright © 2014 Elsevier Ltd. All rights reserved.

  13. 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)

  14. Evaluating the 239Pu Prompt Fission Neutron Spectrum Induced by Thermal to 30 MeV Neutrons

    Directory of Open Access Journals (Sweden)

    Neudecker D.

    2016-01-01

    Full Text Available We present a new evaluation of the 239Pu prompt fission neutron spectrum (PFNS induced by thermal to 30 MeV neutrons. Compared to the ENDF/B-VII.1 evaluation, this one includes recently published experimental data as well as an improved and extended model description to predict PFNS. For instance, the pre-equilibrium neutron emission component to the PFNS is considered and the incident energy dependence of model parameters is parametrized more realistically. Experimental and model parameter uncertainties and covariances are estimated in detail. Also, evaluated covariances are provided between all PFNS at different incident neutron energies. Selected evaluation results and first benchmark calculations using this evaluation are briefly discussed.

  15. Applicability of 239Pu as a tracer for soil erosion in the wet-dry tropics of northern Australia

    International Nuclear Information System (INIS)

    Lal, R.; Tims, S.G.; Fifield, L.K.; Wasson, R.J.; Howe, D.

    2013-01-01

    The technique of accelerator mass spectroscopy (AMS) has been employed to determine modern soil loss rates through the analysis of 239 Pu profiles in soil cores from the Daly basin in Northern Territory, Australia. In areas in which soil conservation banks were not present or were only added recently ( −1 a −1 . The measured rates are up to 5 times higher compared to agricultural and uncultivated areas within soil conservation banks in other parts of the catchment. High intensity seasonal rainfall combined with reduction in land cover due to grazing and episodic bush fires are primary factors influencing erosion although other impacts on the landscape such as tillage generated runoff and land clearing seem to be responsible for accelerated sediment production.

  16. Applicability of {sup 239}Pu as a tracer for soil erosion in the wet-dry tropics of northern Australia

    Energy Technology Data Exchange (ETDEWEB)

    Lal, R., E-mail: rajeev.lal@anu.edu.au [Department of Nuclear Physics, Research School of Physics and Engineering, Australian National University, Canberra, ACT 0200 (Australia); Tims, S.G.; Fifield, L.K. [Department of Nuclear Physics, Research School of Physics and Engineering, Australian National University, Canberra, ACT 0200 (Australia); Wasson, R.J.; Howe, D. [Charles Darwin University, Darwin, NT 0810 (Australia)

    2013-01-15

    The technique of accelerator mass spectroscopy (AMS) has been employed to determine modern soil loss rates through the analysis of {sup 239}Pu profiles in soil cores from the Daly basin in Northern Territory, Australia. In areas in which soil conservation banks were not present or were only added recently (<25a) and which had a history of grazing and cultivation the measured soil loss rates over the past {approx}50 years were 7.5-19.5 t ha{sup -1} a{sup -1}. The measured rates are up to 5 times higher compared to agricultural and uncultivated areas within soil conservation banks in other parts of the catchment. High intensity seasonal rainfall combined with reduction in land cover due to grazing and episodic bush fires are primary factors influencing erosion although other impacts on the landscape such as tillage generated runoff and land clearing seem to be responsible for accelerated sediment production.

  17. Development of a rapid radiochemical procedure for the separation of /sup 235m/U from 239Pu

    International Nuclear Information System (INIS)

    Attrep, M. Jr.; Efurd, D.W.; Roensch, F.R.

    1987-01-01

    We have developed a rapid radiochemical procedure for the isolation and purification of /sup 235m/U (t/sub 1/2/ = 26 minutes) from 239 Pu samples up to 250 mg. Purpose of developing the procedure was to measure the thermal neutron fission cross section of the isomeric meta state of 235 U. We used rapid small-scale anion exchange columns that absorbed uranium in concentrated HBr but did not absorb plutonium. Uranium was easily eluted with very dilute HF. The separation time required 25 to 35 minutes. We were able to attain a separation factor of uranium from plutonium of approximately 1 x 10 10 with samples ranging from 1 x 10 10 to 3 x 10 11 . The ratio of the fission cross sections for the meta to ground state was measured to be 1.42. 4 figs., 1 tab

  18. Alpha and conversion electron spectroscopy of 238,239Pu and 241Am and alpha-conversion electron coincidence measurements

    Energy Technology Data Exchange (ETDEWEB)

    Dion, Michael P.; Miller, Brian W.; Warren, Glen A.

    2016-09-01

    A technique to determine the isotopics of a mixed actinide sample has been proposed by measuring the coincidence of the alpha particle during radioactive decay with the conversion electron (or Auger) emitted during the relaxation of the daughter isotope. This presents a unique signature to allow the deconvolution of isotopes that possess overlapping alpha particle energy. The work presented here are results of conversion electron spectroscopy of 241Am, 238Pu and 239Pu using a dual-stage peltier-cooled 25 mm2 silicon drift detector. A passivated ion implanted planar silicon detector provided measurements of alpha spectroscopy. The conversion electron spectra were evaluated from 20–55 keV based on fits to the dominant conversion electron emissions, which allowed the relative conversion electron emission intensities to be determined. These measurements provide crucial singles spectral information to aid in the coincident measurement approach.

  19. Distribution, retention and early cytogenetic damage in Cynomolgus monkeys following inhalation of 239Pu(NO3)4

    International Nuclear Information System (INIS)

    Brooks, A.L.; Mewhinney, J.A.; Redman, H.C.; Guilmette, R.A.; McClellan, R.O.

    1980-01-01

    Sixteen Cynomolgus monkeys were exposed by inhalation to an aerosol of 239 Pu(NO 3 ) 4 which resulted in calculated initial lung burdens of 1.0, 0.3 and 0.1 μCi. Four animals were exposed to the carrier aerosol and served as controls. Animals were sacrificed at 4 days and 45 days after exposure to determine the distribution and retention of the aerosol. The amount of plutonium in the liver, skeleton and testes increased as a function of time after exposure. Two monkeys died 155 and 188 days after inhalation exposure from radiation pneumonitis and fibrosis. There was a doubling of the total chromosome aberration frequency in the blood lymphocytes and a significant increase in dicentric chromosomes in the animals exposed for 6 months to initial lung burdens of 1.0 μCi

  20. 239Pu and 241Am contamination of small vertebrates in NAEG study areas of NTS and TTR

    International Nuclear Information System (INIS)

    Moor, K.S.; Naele, S.R.; Bradley, W.G.

    1977-01-01

    Ecological studies of small vertebrates in three plutonium (Pu) contaminated study areas of Nevada Test Site began in Spring, 1972, and were expanded to include four areas of Tonopah Test Range in Fall, 1973. This report consists primarily of presentation and analysis of radioanalytical data on rodents and lizards from Area 11-C, Nevada Test Site. In addition, methodology and preliminary results of initial hematologic studies are presented. Dipodomys microps is a dominant rodent species in all study areas. Concentrations of 239 Pu and 241 Am in pelt, GI tract, and carcass of 74 resident D. microps from five study areas were determined. The only consistent trend evident was that carcass burdens were lower than pelt or GI tract burdens by a factor of 10 2 . Mean ratios of Pu/Am in tissue aliquots were variable, and many were significantly different than ratios in soil or vegetation samples

  1. Measurement of 240Pu/239Pu isotopic ratios in soils from the Marshall Islands using ICP-MS.

    Science.gov (United States)

    Muramatsu, Y; Hamilton, T; Uchida, S; Tagami, K; Yoshida, S; Robison, W

    2001-10-20

    Nuclear weapons tests conducted by the United States in the Marshall Islands produced significant quantities of regional or tropospheric fallout contamination. Here we report on some preliminary inductively coupled plasma-mass spectrometry (ICP-MS) measurements of plutonium isolated from seven composite soil samples collected from Bikini, Enewetak and Rongelap Atolls in the northern Marshall Islands. These data show that 240Pu/239Pu isotopic signatures in surface soils from the Marshall Island vary significantly and could potentially be used to help quantify the range and extent of fallout deposition (and associated impacts) from specific weapons tests. 137Cs and 60Co were also determined on the same set of soil samples for comparative purposes.

  2. Critical mass analysis for 235U and 239Pu systems moderated and reflected by D2O

    International Nuclear Information System (INIS)

    Loaiza, D.; Stratton, W.

    1998-01-01

    Criticality dimensions for highly enriched 235 U (93.5) and 239 Pu (95.5) systems mixed with D 2 O were studied. The objective of this work is to investigate the minimum critical mass and concentration of uranium and plutonium systems in a reflector-moderated arrangement. The present work demonstrates the critical instability of some of these systems that are reflected by D 2 O and expands from previously published and unpublished work. These calculations were performed in a spherical geometry with the DANTSYS codes using the Hansen-Roach cross-section library. Densities examined ranged from normal to very small and are assumed to be uniform throughout the core. These spherical systems are reflected by 100 cm of D 2 O

  3. Measurement of 240Pu/239Pu isotopic ratios in soils from the Marshall Islands using ICP-MS

    Energy Technology Data Exchange (ETDEWEB)

    Muramatsu, Y.; Uchida, S.; Tagami, K.; Yoshida, S. [Environmental and Toxicological Researches Group, National Institute of Radiological Sciences, Anagawa 4-9-1, Inage-ku, 263-8555 Chiba (Japan); Hamilton, T.; Robison, W. [Health and Ecological Assessment Division, Lawrence Livermore National Laboratory, P.O. Box 808, L-453, 94551-0808 Livermore, CA (United States)

    2001-10-20

    Nuclear weapons tests conducted by the United States in the Marshall Islands produced significant quantities of regional or tropospheric fallout contamination. Here we report on some preliminary inductively coupled plasma-mass spectrometry (ICP-MS) measurements of plutonium isolated from seven composite soil samples collected from Bikini, Enewetak and Rongelap Atolls in the northern Marshall Islands. These data show that 240Pu/239Pu isotopic signatures in surface soils from the Marshall Island vary significantly and could potentially be used to help quantify the range and extent of fallout deposition (and associated impacts) from specific weapons tests. 137Cs and 60Co were also determined on the same set of soil samples for comparative purposes.

  4. Measurement of 240Pu/239Pu isotopic ratios in soils from the Marshall Islands using ICP-MS

    International Nuclear Information System (INIS)

    Muramatsu, Y.; Uchida, S.; Tagami, K.; Yoshida, S.; Hamilton, T.; Robison, W.

    2001-01-01

    Nuclear weapons tests conducted by the United States in the Marshall Islands produced significant quantities of regional or tropospheric fallout contamination. Here we report on some preliminary inductively coupled plasma-mass spectrometry (ICP-MS) measurements of plutonium isolated from seven composite soil samples collected from Bikini, Enewetak and Rongelap Atolls in the northern Marshall Islands. These data show that 240Pu/239Pu isotopic signatures in surface soils from the Marshall Island vary significantly and could potentially be used to help quantify the range and extent of fallout deposition (and associated impacts) from specific weapons tests. 137Cs and 60Co were also determined on the same set of soil samples for comparative purposes

  5. Study on transfer coefficients of 90Sr, 137Cs, natural U, 226Ra and 239Pu in terrestrial food chains

    International Nuclear Information System (INIS)

    Qin Suyun; Qi Yong; Li Shuqin; Zhou Caiyun; Zhang Jingjuan; Li Jikai; Li Xuequn

    1995-01-01

    The aim of study was to provide values of transfer parameter of 90 Sr, 137 Cs, Natural U, 226 Ra and 239 Pu in terrestrial food chains, more applicable for Chinese socio-natural conditions. Data of radionuclides contents in agricultural crops and in associated soils, in sheep tissues and in associated grasses were collected in couples. The transfer coefficients in terrestrial food chains (soil-crops, grasses-sheep tissues) were calculated. On basis of statistical analysis, the representative values and 95% ranges of transfer coefficient for 5 radionuclides in 7 kind of agricultural products for southern moist areas and north dry areas were given. Regression analysis showed that relation between the transfer coefficients and the radionuclide contents in their associated soils present a negative correlation, it could be described with a equation: Y = aX -b

  6. Evaluating and adjusting 239Pu, 56Fe, 28Si and 95Mo nuclear data with a Monte Carlo technique

    International Nuclear Information System (INIS)

    Rochman, D.; Koning, A. J.

    2012-01-01

    In this paper, Monte Carlo optimization and nuclear data evaluation are combined to produce optimal adjusted nuclear data files. The methodology is based on the so-called 'Total Monte Carlo' and the TALYS system. Not only a single nuclear data file is produced for a given isotope, but virtually an infinite number, defining probability distributions for each nuclear quantity. Then each of these random nuclear data libraries is used in a series of benchmark calculations. With a goodness-of-fit estimator, best 239 Pu, 56 Fe, 28 Si and 95 Mo evaluations for that benchmark set can be selected. A few thousands of random files are used and each of them is tested with a large number of fast, thermal and intermediate energy criticality benchmarks. From this, the best performing random file is chosen and proposed as the optimum choice among the studied random set. (authors)

  7. Fission Product Yield Study of 235U, 238U and 239Pu Using Dual-Fission Ionization Chambers

    Science.gov (United States)

    Bhatia, C.; Fallin, B.; Howell, C.; Tornow, W.; Gooden, M.; Kelley, J.; Arnold, C.; Bond, E.; Bredeweg, T.; Fowler, M.; Moody, W.; Rundberg, R.; Rusev, G.; Vieira, D.; Wilhelmy, J.; Becker, J.; Macri, R.; Ryan, C.; Sheets, S.; Stoyer, M.; Tonchev, A.

    2014-05-01

    To resolve long-standing differences between LANL and LLNL regarding the correct fission basis for analysis of nuclear test data [M.B. Chadwick et al., Nucl. Data Sheets 111, 2891 (2010); H. Selby et al., Nucl. Data Sheets 111, 2891 (2010)], a collaboration between TUNL/LANL/LLNL has been established to perform high-precision measurements of neutron induced fission product yields. The main goal is to make a definitive statement about the energy dependence of the fission yields to an accuracy better than 2-3% between 1 and 15 MeV, where experimental data are very scarce. At TUNL, we have completed the design, fabrication and testing of three dual-fission chambers dedicated to 235U, 238U, and 239Pu. The dual-fission chambers were used to make measurements of the fission product activity relative to the total fission rate, as well as for high-precision absolute fission yield measurements. The activation method was employed, utilizing the mono-energetic neutron beams available at TUNL. Neutrons of 4.6, 9.0, and 14.5 MeV were produced via the 2H(d,n)3He reaction, and for neutrons at 14.8 MeV, the 3H(d,n)4He reaction was used. After activation, the induced γ-ray activity of the fission products was measured for two months using high-resolution HPGe detectors in a low-background environment. Results for the yield of seven fission fragments of 235U, 238U, and 239Pu and a comparison to available data at other energies are reported. For the first time results are available for neutron energies between 2 and 14 MeV.

  8. The Transport of Close-In Fallout Plutonium in the Northwest Pacific Ocean: Tracing the Water Mass Movement Using {sup 240}Pu/{sup 239}Pu Atom Ratio

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Sang-Han [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of); Hong, Gi-Hoon; Suk, Moon-Sik [Korea Ocean Research and Development Institute, Seoul (Korea, Republic of); Gastaud, J. [International Atomic Energy Agency, Marine Environment Laboratory (Monaco); La Rosa, J. [National Institute of Standards and Technology, Ionizing Radiation Division, Gaithersburg, Maryland (United States); Kim, Chul-Soo [Environmental Laboratories, International Atomic Energy Agency, Seibersdorf (Austria); Wyse, E. [New Brunswick Laboratory Argonne, IL (United States); Povinec, P. P. [Comenius University, Faculty of Mathematics and Physics, Bratislava (Slovakia)

    2013-07-15

    {sup 240}Pu/{sup 239}Pu atom ratios in seawater and surface sediment collected from the northwest (NW) Pacific Ocean from 1992 to 1997 were determined using ICP-sector field mass spectrometry (ICP-MS). In whole water columns, the atom ratios of {sup 240}Pu/{sup 239}Pu were higher than the global fallout ratio (0.18). It is noted that the atom ratios of {sup 240}Pu/2{sup 39}Pu in the seawater increase with depth. Such elevated {sup 240}Pu/{sup 239}Pu atom ratios indicate that the close-in fallout plutonium isotopes originating from the Pacific Proving Grounds (PPGs) due to the U.S. tests are prevailing in the seawater in the NW Pacific Ocean. However, the {sup 240}Pu/{sup 239}Pu atom ratios in the surface sediment from the NW Pacific Ocean varied with the sampling locations. As a consequence, this study will provide the information that the water mass along with the current plays a key role in driving the distribution of Pu and in transporting Pu from the PPGs to the far eastern marginal sea in the NW Pacific Ocean. (author)

  9. Intercomparison study of inductively coupled plasma mass spectrometry, thermal ionization mass spectrometry and fission track analysis of μBq quantities of 239Pu in synthetic urine

    International Nuclear Information System (INIS)

    Inn, K.G.W.; McCurdy, D.; Kuruvilla, L.; Barss, N.M.; Bell III, R.T.; Pietrzak, R.; Kaplan, E.; Inkret, W.; Efurd, W.; Rokop, D.; Lewis, D.; Gautier, P.

    2001-01-01

    Even today, some Marshall Islanders are looking forward to permanently resettling their islands after five decades. The U.S. Department of Energy and the resettled residents require reasonable but cost-prudent assurance that the doses to resident from residual 239 Pu will not exceed recognized international standards or recommendations, as estimated from the excretion of 239 Pu in urine. The goal of this study was to evaluate the bias, uncertainty and sensitivity of analytical techniques that measure 3-56 μBq 239 Pu in synthetic urine. The analytical techniques studied in this work included inductively coupled plasma mass spectrometry, thermal ionization mass spectrometry and fission track analysis. The results of the intercomparison demonstrated that all three techniques were capable of marking the measurements, although not with equal degree of bias and uncertainty. The estimated minimum detectable activity was 1 μBq of 239 Pu per synthetic urine sample. This exercise is also the first effort to certify test materials of plutonium in the nBqxg -1 range. (author)

  10. Perturbation in the 240Pu/239Pu global fallout ratio in local sediment following the nuclear accidents at Thule (Greenland) and Palomares (Spain)

    International Nuclear Information System (INIS)

    Mitchell, P.I.; Vintro, L.L.; Gasco, C.; Sanchez-Cabeza, J.A.

    1995-01-01

    It is well established that the main source of the plutonium found in marine sediments throughout the Northern Hemisphere is global stratospheric fallout, characterized by a typical 240 Pu/ 239 Pu atom ratio of ∼0.18. Measurements of perturbations in this ratio at various sites which had been subjected to close-in fallout, mainly from surface-based testing, has confirmed the feasibility of using this ratio to distinguish plutonium from different fallout sources. In the present study, the 240 Pu/ 239 Pu ratio has been examined in samples of sediment collected at Thule (Greenland) and Palomares (Spain), where accidents involving the release and dispersion of plutonium from fractured nuclear weapons occurred in 1968 and 1966, respectively. The 240 Pu/ 239 Pu ratio was measured by high-resolution alpha spectrometry and spectral deconvolution. The analytical results showed that at Thule the mean 240 Pu/ 239 Pu atom ratio was 0.033±0.004, while at Palomares the equivalent ratio appeared to be significantly higher at 0.056±0.003. Both ratios are consistent with those reported for soils samples at the Nevada site and Nagasaki, and are clearly indicative of weapons-grade plutonium. 27 refs., 1 fig., 2 tabs

  11. Energy measurement of prompt fission neutrons in 239Pu(n,f) for incident neutron energies from 1 to 200 MeV

    CERN Document Server

    Chatillon, A; Granier, Th; Laurent, B; Taïeb, J; Noda, S; Haight, R C; Devlin, M; Nelson, R O; O’Donnell, J M

    2010-01-01

    Prompt fission neutron spectra in the neutron-induced fission of 239Pu have been measured for incident neutron energies from 1 to 200 MeV at the Los Alamos Neutron Science Center. Preliminary results are discussed and compared to theoretical model calculation.

  12. Energy dependence of the asymmetry-violated space parity of fragment emission from the 239PU fission by slow polarized neutrons

    International Nuclear Information System (INIS)

    Val'skij, G.V.; Zvezdkina, T.K.; Nikolaev, D.V.; Petrova, V.I.; Petrov, G.A.; Petukhov, A.K.; Pleva, Yu.S.; Tyukavin, V.A.

    1982-01-01

    Asymmetry violating parity in the fragment emission from fission of 239 Pu induced by polarized neutrons at six energy points in the interval 0.01 <= E <0.3 eV was measured. The results providing with an evidence in favour of the hypothesis that the asymmetry is independent on energy are discussed in view of the existing theoretical picture

  13. The influence of age at time of exposure to 226Ra or 239Pu on distribution, retention, postinjection survival, and tumor induction in beagle dogs

    International Nuclear Information System (INIS)

    Bruenger, F.W.; Lloyd, R.D.; Miller, S.C.

    1991-01-01

    The influence of age at injection of 226Ra or 239Pu on skeletal deposition and local distribution, the pattern of bone tumor formation, and postinjection survival was assessed in parallel short-term studies of mechanisms and lifetime toxicity. Beagles received a single intravenous injection of 226Ra or 239Pu at 3 months (juveniles), 17-19 months (young adults) or 60 months (mature). Data from short-term studies of mechanisms and dosimetry and from one dosage level of each of the toxicity experiments were compared. Skeletal growth and turnover produced differential initial deposition and distribution patterns typical for each age group. At 1 week after injection, skeletal retention of 226Ra or 239Pu was 68 and 68%, respectively, in the juveniles, 32 and 46% in the young adults, and 31 and 43% in the mature dogs. Comparing individual bones in the juveniles, gradients in the concentration of 239Pu were small since all bones were actively growing, but substantial gradients, corresponding to centers of ossification, were present within individual bones. In other age groups, local concentration gradients were less pronounced, but much larger differences were present among the various bones. In the toxicity study all animals injected with either 41 kBq 226Ra/kg or 11 kBq 239Pu/kg have died. The cumulative average skeletal doses to the presumed time of start of tumor growth (1 year before death) were 25 and 4 Gy, respectively, for the juveniles, 22 and 5 Gy for the young adults, and 15 and 4 Gy for the mature dogs. The highest bone tumor incidence was seen in the young adult groups. Differences were observed in location of bone tumors between dogs in the same age group given radium or plutonium and among age groups injected with either radionuclide, some of which could be explained by differences in local dose distributions

  14. Integral data evaluation of stainless steel, 239Pu, 240Pu, and H2O for homogeneous plutonium systems

    International Nuclear Information System (INIS)

    Jenquin, U.P.; Thompson, J.K.; Trapp, T.J.; Kottwitz, D.A.

    1979-08-01

    Theory-experiment correlations of plutonium-fueled systems using ENDF/B cross-section data have discrepancies which could be due to cross-section data, theoretical methods, and/or interpretation of the experiment. Analyses of homogeneous plutonium critical experiments were performed to determine where cross section deficiencies may exist. New thermal cross-section data (0.3 eV) were generated for 239 Pu and 240 Pu capture, fission, and neutrons per fission. Two scattering kernels for hydrogen bound in water were also generated. Calculated values of k/sub eff/ using these new data were compared with corresponding values using ENDF/B-IV data. The results indicate that the 240 Pu resonance data are sufficiently well known for hydrogen-moderated plutonium systems. In systems using stainless steel as structural and/or neutron control, a large fraction of the neutron absorptions occur in the stainless steel. Analyses of several systems containing stainless steel indicate that the uncertainty in calculated values of k/sub eff/ is small using current estimates of the uncertainties in the cross sections. 20 figures, 30 tables

  15. Decorporation effects of ethylenediamine-N, N-bis-(2-hydroxyphenylacetic acid) dihydrochloride (EDDHA) in 239Pu-contaminated mice

    International Nuclear Information System (INIS)

    Szot, Z.; Rochalska, M; Wojewodzka, M.; Chimiak, A.; Milewska, M.

    1986-01-01

    Male SAS/4 mice contaminated intravenously with 239 Pu 4 citrate were injected with EDDHA. The ligand was given as a single or repeated injection. The single injection in a dose ranging from 30 to 290 μmol.kg -1 was administered 1 h after Pu contamination. The Pu activity in liver, kidneys and femur was determined by the liquid scintillation method after 4 days. Repeated injections of EDDHA in the dose of 145 μmol.kg -1 each, were started 4 or 24 h after Pu contamination. After 3 or 4 daily injections the Pu content in liver, kidneys and femur was examined 7 or 11 days after Pu contamination. The decontaminating effects of EDDHA and Na 3 CaDTPA were compared at the level of a single dose of 30 μmol.kg -1 . EDDHA was less effective than Na 3 CaDTPA and 290 μmol.kg -1 of EDDHA. In kidneys the decontaminating effect of EDDHA is not proportional to the dose increment. 6 refs. (author)

  16. Comparison of Pu metabolism and pulmonary tumors in dogs and rats exposed to 239PuO2

    International Nuclear Information System (INIS)

    Mahaffey, J.A.; Sanders, C.L.; Dagle, G.E.; Park, J.F.

    The dose-effect relationships of dogs and rats exposed by inhalation to 239 PuO 2 were compared to evaluate parameters that may provide a better understanding for extrapolating these laboratory animal results to humans. Comparisons were made on animals with lifetime lung doses between 1400 and 11,000 rad. Parameters compared included survival; Pu clearance and translocation; and time of occurrence, incidence and histopathology of pulmonary tumors. The group means for lifetime dose to lung were not significantly different between dogs and rats, but when survival time was expressed as the percentage of maximum life expectancy (MLE), the mean survival time of dogs was 40% of MLE and of rats was 56% of MLE. Lung tumors were the causes of death in 84% of the dogs and 54% of the rats; the mean survival time to lung tumor was 44% of MLE for dogs, compared to 57% of MLE for rats. Whole-body clearance of plutonium was slower in dogs. More Pu translocated to the thoracic lymph nodes, liver, and skeleton in the dogs than in rats. Estimates of species differences in lung clearance were dependent on the methods of estimating initial lung burden. There were parameters with qualitative and quantitative similarities in dogs and rats. Quantitative differences between species, generally within a factor of two, suggested that more reliable dosimetry estimates are needed to make quantitative extrapolation between species

  17. Photo-fission Product Yield Measurements at Eγ=13 MeV on 235U, 238U, and 239Pu

    Science.gov (United States)

    Tornow, W.; Bhike, M.; Finch, S. W.; Krishichayan, Fnu; Tonchev, A. P.

    2016-09-01

    We have measured Fission Product Yields (FPYs) in photo-fission of 235U, 238U, and 239Pu at TUNL's High-Intensity Gamma-ray Source (HI γS) using mono-energetic photons of Eγ = 13 MeV. Details of the experimental setup and analysis procedures will be discussed. Yields for approximately 20 fission products were determined. They are compared to neutron-induced FPYs of the same actinides at the equivalent excitation energies of the compound nuclear systems. In the future photo-fission data will be taken at Eγ = 8 . 0 and 10.5 MeV to find out whether photo-fission exhibits the same so far unexplained dependence of certain FPYs on the energy of the incident probe, as recently observed in neutron-induced fission, for example, for the important fission product 147Nd. Work supported by the U. S. Dept. of Energy, under Grant No. DE-FG02-97ER41033, and by the NNSA, Stewardship Science Academic Alliances Program, Grant No. DE-NA0001838 and the Lawrence Livermore, National Security, LLC under Contract No. DE-AC52-07NA27344.

  18. Photofission product yields of {sup 238}U and {sup 239}Pu with 22-MeV bremsstrahlung

    Energy Technology Data Exchange (ETDEWEB)

    Wen, Xianfei; Yang, Haori, E-mail: haori.yang@oregonstate.edu

    2016-06-11

    In homeland security and nuclear safeguards applications, non-destructive techniques to identify and quantify special nuclear materials are in great demand. Although nuclear materials naturally emit characteristic radiation (e.g. neutrons, γ-rays), their intensity and energy are normally low. Furthermore, such radiation could be intentionally shielded with ease or buried in high-level background. Active interrogation techniques based on photofission have been identified as effective assay approaches to address this issue. In designing such assay systems, nuclear data, like photofission product yields, plays a crucial role. Although fission yields for neutron-induced reactions have been well studied and readily available in various nuclear databases, data on photofission product yields is rather scarce. This poses a great challenge to the application of photofission techniques. In this work, short-lived high-energy delayed γ-rays from photofission of {sup 238}U were measured in between linac pulses. In addition, a list-mode system was developed to measure relatively long-lived delayed γ-rays from photofission of {sup 238}U and {sup 239}Pu after the irradiation. Time and energy information of each γ-ray event were simultaneously recorded by this system. Cumulative photofission product yields were then determined using the measured delayed γ-ray spectra.

  19. A Study of the Resonance Interaction Effect between 238U and 239Pu in Lower Energy Region

    International Nuclear Information System (INIS)

    Haeggblom, H.

    1968-12-01

    An investigation has been made of the statistical frequency function for the distances between the 238 U and the 239 Pu resonances in the region 4-244 eV. It is concluded that the frequency function is probably constant but that the distances diverge appreciably from a constant function in the actual case, and that the divergence is such that the interaction effect on the resonance integral is smaller than would be expected from statistical considerations. This is also confirmed by calculations on the interaction effect. These have been performed using three different methods, namely: a) considering the actual positions and widths of the resonances, b) assuming a constant frequency function for the resonance. spacing and applying a theory developed by Rowlands and E A Fischer. c) applying a simplified, approximate method for calculations based on the statistical theory. The calculations are made for two temperatures and two values of the plutonium enrichment. It is shown that the average cross sections are considerably larger than the statistical calculations indicate

  20. A Study of the Resonance Interaction Effect between {sup 238}U and {sup 239}Pu in Lower Energy Region

    Energy Technology Data Exchange (ETDEWEB)

    Haeggblom, H

    1968-12-15

    An investigation has been made of the statistical frequency function for the distances between the {sup 238}U and the {sup 239}Pu resonances in the region 4-244 eV. It is concluded that the frequency function is probably constant but that the distances diverge appreciably from a constant function in the actual case, and that the divergence is such that the interaction effect on the resonance integral is smaller than would be expected from statistical considerations. This is also confirmed by calculations on the interaction effect. These have been performed using three different methods, namely: a) considering the actual positions and widths of the resonances, b) assuming a constant frequency function for the resonance. spacing and applying a theory developed by Rowlands and E A Fischer. c) applying a simplified, approximate method for calculations based on the statistical theory. The calculations are made for two temperatures and two values of the plutonium enrichment. It is shown that the average cross sections are considerably larger than the statistical calculations indicate.

  1. Distribution of 239Pu in the skeleton of the tree shrew (Tupaia belangeri) between 15 and 50 months after injection

    International Nuclear Information System (INIS)

    Sontag, W.; Seidel, A.

    1987-01-01

    The macroscopic and microscopic distribution of intramuscularly injected, essentially monomeric, 239 Pu was studied in the skeleton of the adult tree shrew (Tupaia belangeri). Data for between 15 and 50 months after injection are presented and compared with data from earlier time points. Between 83 and 500 days after injection nuclide content and wet weight of the skeleton decreased to a constant level at about 55% of maximum. The microscopic distribution was analysed in distal femora, proximal humerus, proximal tibia and lumbar vertebra over the whole time; additionally at some selected time points proximal femur, femur shaft, distal humerus and distal tibia were analysed. The initial endosteal surface activity ranged from 3.8 to 5.3 Bq/cm 2 , decreased to a minimum at about 1000 days after injection and increased thereafter. Similar behaviour was found for dose rate near bone surfaces (initially about 0.075 Gy/day on endosteal surfaces). In deep bone and deep marrow the dose rate was negligible, about 0.008 Gy/day and 0.001 Gy/day, respectively. The average cumulative dose 1500 days after injection was about 67 Gy on the endosteum; six times greater than the cumulative dose calculated from the mean concentration of plutonium in the whole skeleton. Tupaia data are compared to monkeys, dogs and rats. (author)

  2. Neutron emission effects on fragment mass and kinetic energy distribution from fission of 239Pu induced by thermal neutrons

    International Nuclear Information System (INIS)

    Montoya, M.; Rojas, J.; Lobato, I.

    2010-01-01

    The average of fragment kinetic energy (E-bar sign*) and the multiplicity of prompt neutrons (ν(bar sign)) as a function of fragment mass (m*), as well as the fragment mass yield (Y(m*)) from thermal neutron-induced fission of 239 Pu have been measured by Tsuchiya et al.. In that work the mass and kinetic energy are calculated from the measured kinetic energy of one fragment and the difference of time of flight of the two complementary fragments. However they do not present their results about the standard deviation σ E *(m*). In this work we have made a numerical simulation of that experiment which reproduces its results, assuming an initial distribution of the primary fragment kinetic energy (E(A)) with a constant value of the standard deviation as function of fragment mass (σ E (A)). As a result of the simulation we obtain the dependence σ E *(m*) which presents an enhancement between m* = 92 and m* = 110, and a peak at m* = 121.

  3. Toxicity of inhaled 239PuO2 in immature, young adult, and aged Syrian hamsters. II

    International Nuclear Information System (INIS)

    Hobbs, C.H.; Mewhinney, J.A.; Slauson, D.A.; McClellan, R.O.; Miglio, J.J.

    1974-01-01

    Syrian hamsters have been exposed at either 28 (immature), 84 (young adult), or 340 (aged) days of age to polydisperse aerosols of 239 PuO 2 to better define dose-response relationships for this radionuclide in a population with a wide range of ages such as would be the case with a human population following a catastrophic nuclear accident. Animals were exposed to obtain initial lung burdens of 240, 60, 15, 3.8, 0.95, 0.25, and 0.029 nCi for the immature and young adult animals and 240, 60, 15, and 3.8 nCi for the aged animals. Animals are being maintained both for serial sacrifice to determine the radiation dose pattern for lung and other tissues and for lifespan observation to determine dose-response relationships. At the present time, only animals with ILB of about 200 nCi or higher exposed as either immature, young adult, or aged animals have shown increased mortality as compared to controls. At this time, the young adult, immature, and aged animals are 68, 73, and 27 weeks post-inhalation exposure, respectively. The animals that died in the higher ILB groups had radiation pneumonitis and pulmonary fibrosis along with atypical pulmonary epithelial hyperplasia. Histopathological examination is not complete on all animals that have died, but no pulmonary neoplasms have been observed to date. (U.S.)

  4. Use of combined alpha-spectrometry and fission track analysis for the determination of 240Pu/239Pu ratios in human tissue

    International Nuclear Information System (INIS)

    Love, S.F.; Filby, R.H.; Glover, S.E.; Stuit, D.B.; Kathren, R.L.

    1998-01-01

    Plutonium and other actinides were determined in human autopsy tissues of occupationally exposed workers who were registrants of the United States Transuranium and Uranium Registries (USTUR). In this study, Pu was purified and isolated from Am, U and Th, after drying and wet-ashing of the tissues, and the addition of 238 Pu as a radiotracer. After electrodeposition onto vanadium planchets, the 239+240 Pu activity was determined by alpha-spectrometry. A fission track method was developed to determine 239 Pu in the presence of 238 Pu and 240 Pu, using Lexan TM polycarbonate detectors. Combining the two techniques allowed the determination of the 240 Pu/ 239 Pu activity and atom ratios. Data from selected USTUR cases are presented. (author)

  5. Assinatura da deposição atmosférica de testes nucleares em sedimentos da costa brasileira (240+239Pu e 137Cs

    Directory of Open Access Journals (Sweden)

    Christian J. Sanders

    2012-01-01

    Full Text Available The aim of this review is to take a look at Cold War era nuclear tests signatures found in Brazilian coastal sediments. Both137Cs and 240+239Pu signatures have been documented in mangrove, coastal mudflats and continental shelf sediments, associated with above ground nuclear tests beginning in the 1950's. The dates associated to the anthropogenic radionuclide signatures 137Cs and 240+239Pu along sediment columns are confirmed by 210Pb geochronology in many of the studies highlighted in this review. The results outlined in this review characterize the extent to which nuclear fallout products reach the Brazilian coast in quantities sufficient for detection, allowing the use of these radioisotopes as geochronometers.

  6. Coulomb effects in isobaric cold fission from reactions 233U(nth,f), 235U(nth,f),239Pu(nth,f) and 252Cf(sf)

    International Nuclear Information System (INIS)

    Montoya, Modesto

    2013-01-01

    The Coulomb effect hypothesis, formerly used to interpret fluctuations in the curve of maximal total kinetic energy as a function of light fragment mass in reactions 233 U(n th ,f), 235 U(n th ,f) and 239 Pu(n th ,f), is confirmed in high kinetic energy as well as in low excitation energy windows, respectively. Data from reactions 233 U(n th ,f), 235 U(n th ,f), 239 Pu(n th ,f) and 252 Cf(sf) show that, between two isobaric fragmentations with similar Q-values, the more asymmetric charge split reaches the higher value of total kinetic energy. Moreover, in isobaric charge splits with different Q-values, similar preference for asymmetrical fragmentations is observed in low excitation energy windows. (author).

  7. 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

  8. 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)

  9. The application of data derived from autoradiographic studies with 241Pu in the formulation of a bone dosimetric model for 239Pu

    International Nuclear Information System (INIS)

    Priest, N.D.; Hunt, B.W.

    1979-01-01

    Recently a dosimetric model for 239 Pu in bone has been published which in conjunction with the general ICRP dosimetric model for actinides is used to calculate annual limits of intake for 239 Pu. This model allows for the burial of plutonium in bone, for the recycling of plutonium within the skeleton and for the retention of plutonium in the bone marrow. The model was based upon published descriptions of the distribution and redistribution patterns of plutonium in bone and on evidence obtained from autoradiographic studies of bone from animals injected with 241 Pu. The experiments with 241 Pu demonstrated the initial uptake of plutonium by bone surfaces. As a result of the growth and drift processes much of this plutonium became either buried in the bone or was retained within macrophages in the bone marrow. (author)

  10. Study on the P-odd asymmetry of longitudinally polarized neutron transmission in 117Sn, 233Th, 239Pu isotopes and natural mixture of Cl and Pb isotopes

    International Nuclear Information System (INIS)

    Abov, Yu.G.; Ermakov, O.N.; Karpikhin, I.L.; Krupchitskij, P.A.; Kuznetsov, Yu.Eh.; Perepelitsa, V.F.; Petrushin, V.I.

    1983-01-01

    The results of measurements of P-odd helicity dependence of the total cross-section a=(σsub(tot)sup(+)-σsub(tot)sup(-))/(σsub(tot)sup(+)+σsub(tot)sup(-)) for thermal neutrons on several targets are presented. The result for 117 Sn is a=(11.2+-2.6)x10 -6 . The upper limits for a in the region of several units of 10 -6 are obtained for 232 Th, 239 Pu, Cl (natural) and Pb (natural)

  11. Comparison of the ENDF/B-V and SOKRATOR evaluations of 235U, 239Pu, 240Pu and 241Pu at low neutron energies

    International Nuclear Information System (INIS)

    de Saussure, G.; Wright, R.Q.

    1981-01-01

    The US and USSR's most recent evaluationsof 235 U, 239 Pu, 240 Pu and 241 Pu are compared over the thermal region and over the first few resonances. The two evaluations rest on essentially the same experimental data base and the differences reflect different approaches to the representation of the cross sections or different weightings of the experimental results. It is found that over the thermal and resolved ranges the two evaluations are very similar. Some differences in approaches are briefly discussed

  12. The influence of age at time of exposure to 239Pu or 226Ra on retention, distribution, survival and tumor induction in Beagles

    International Nuclear Information System (INIS)

    Bruenger, F.W.; Miller, S.C.; Lloyd, R.D.

    1991-01-01

    The influence of age at injection of 226 Ra or 239 Pu on skeletal deposition and local distribution, the pattern of bone tumor formation and post-injection survival were studied in parallel short-term mechanistic and lifetime toxicity experiments. Beagles received a single intravenous injection of 226 Ra or 239 Pu at age 3 months (juveniles), 17-19 months (young adults) or 60 months (mature). Data from short-term mechanistic-dosimetric studies and from one dosage level (41 kBq 226 Ra/kg or 11 kBq 239 Pu/kg body mass) of each of the toxicity experiments were compared. Skeletal growth and turnover produced differential initial deposition and distribution patterns typical for each age group. The highest bone tumor incidence was seen in the young adult groups. Differences were observed in bone tumor location between dogs in the same age group given radium or plutonium and among age groups injected with either radionuclide, and some of these could be explained by differences in local dose distributions (e.g., trabecular vs. cortical bone). Cox regression indicated no significant differences in post-injection survivals (uncorrected for the different pre-injection periods) of Ra-injected groups, but there was a statistically significant difference among the Pu-injected groups. Neutron-induced autoradiography showed that differences in the effects of Pu in the three age groups were due primarily to the age- and time-dependent local distribution of the nuclide

  13. Species comparison of liver cancers induced by internally deposited /sup 144/Ce or /sup 239/Pu in dogs and Chinese hamsters

    International Nuclear Information System (INIS)

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

    1984-01-01

    The risk of liver cancer from alpha-emitting radionuclides has been estimated for people from studies of patients injected with Thorotrast, which contains an alpha-emitting radionuclide. There is no corresponding estimation of the risk of liver cancers in people from internally-deposited beta-emitting radionuclides because of the lack of human data. Life-span studies in Beagle dogs exposed by inhalation to /sup 144/CeCl/sub 3/, a beta-emitting radionuclide, or by injection to /sup 239/Pu citrate, an alpha-emitting radionuclide, and in Chinese hamsters exposed by intravenous injections to /sup 144/Ce-/sup 144/Pr citrate or /sup 239/Pu citrate have provided information on liver cancers in these species. These radionuclides accumulated in the liver resulting in significant radiation exposure of the liver. Liver cancer occurred long after exposure. When the lifetime risks of liver cancer were calculated, /sup 239/Pu was found to be more effective than /sup 144/Ce in inducing liver cancers by factor of 10 to 12. The risk of liver cancer from internally-deposited beta emitters for people are estimated by assuming this relationship for people

  14. Multi-isotopic determination of plutonium (239Pu, 240Pu, 241Pu and 242Pu) in marine sediments using sector-field inductively coupled plasma mass spectrometry.

    Science.gov (United States)

    Donard, O F X; Bruneau, F; Moldovan, M; Garraud, H; Epov, V N; Boust, D

    2007-03-28

    Among the transuranic elements present in the environment, plutonium isotopes are mainly attached to particles, and therefore they present a great interest for the study and modelling of particle transport in the marine environment. Except in the close vicinity of industrial sources, plutonium concentration in marine sediments is very low (from 10(-4) ng kg(-1) for (241)Pu to 10 ng kg(-1) for (239)Pu), and therefore the measurement of (238)Pu, (239)Pu, (240)Pu, (241)Pu and (242)Pu in sediments at such concentration level requires the use of very sensitive techniques. Moreover, sediment matrix contains huge amounts of mineral species, uranium and organic substances that must be removed before the determination of plutonium isotopes. Hence, an efficient sample preparation step is necessary prior to analysis. Within this work, a chemical procedure for the extraction, purification and pre-concentration of plutonium from marine sediments prior to sector-field inductively coupled plasma mass spectrometry (SF-ICP-MS) analysis has been optimized. The analytical method developed yields a pre-concentrated solution of plutonium from which (238)U and (241)Am have been removed, and which is suitable for the direct and simultaneous measurement of (239)Pu, (240)Pu, (241)Pu and (242)Pu by SF-ICP-MS.

  15. Determination of plutonium isotopes (238Pu, 239Pu, 240Pu, 241Pu) in environmental samples using radiochemical separation combined with radiometric and mass spectrometric measurements.

    Science.gov (United States)

    Xu, Yihong; Qiao, Jixin; Hou, Xiaolin; Pan, Shaoming; Roos, Per

    2014-02-01

    This paper reports an analytical method for the determination of plutonium isotopes ((238)Pu, (239)Pu, (240)Pu, (241)Pu) in environmental samples using anion exchange chromatography in combination with extraction chromatography for chemical separation of Pu. Both radiometric methods (liquid scintillation counting and alpha spectrometry) and inductively coupled plasma mass spectrometry (ICP-MS) were applied for the measurement of plutonium isotopes. The decontamination factors for uranium were significantly improved up to 7.5 × 10(5) for 20 g soil compared to the level reported in the literature, this is critical for the measurement of plutonium isotopes using mass spectrometric technique. Although the chemical yield of Pu in the entire procedure is about 55%, the analytical results of IAEA soil 6 and IAEA-367 in this work are in a good agreement with the values reported in the literature or reference values, revealing that the developed method for plutonium determination in environmental samples is reliable. The measurement results of (239+240)Pu by alpha spectrometry agreed very well with the sum of (239)Pu and (240)Pu measured by ICP-MS. ICP-MS can not only measure (239)Pu and (240)Pu separately but also (241)Pu. However, it is impossible to measure (238)Pu using ICP-MS in environmental samples even a decontamination factor as high as 10(6) for uranium was obtained by chemical separation. © 2013 Elsevier B.V. All rights reserved.

  16. Reassessment of 239Pu on planchets from human urine samples at ultra-trace levels using Aridus-ICP-SFMS and AMS

    International Nuclear Information System (INIS)

    Hernandez-Mendoza, H.; Chamizo, E.; Delgado, A.; Garcia-Leon, M.; Yllera, A.

    2012-01-01

    New analytical methods developed at the facilities here, based on two ultra-sensitive mass spectrometry (MS) techniques, inductively coupled plasma sector field mass spectrometer with a desolvator system (Aridus-ICP-SFMS) and accelerator MS (AMS), have been applied in this work for the reassessment of 239 Pu in alpha spectrometry (AS) planchets corresponding to spiked human urine samples. The obtained 239 Pu minimum detectable activities (MDAs) values by Aridus-ICP-SFMS and AMS were 3 fg (∼6.92 μBq) and 0.4 fg (∼0.92 μBq), respectively, per sample, which are much better than those attainable by AS [50 fg (∼115.3 μBq) of 239 Pu per sample, approximately]. Therefore, it is demonstrated that the MS techniques employed in this work are very powerful tools for internal dosimetry studies in human urine samples, giving excellent results when the reassessment of AS planchets is needed (samples with a Pu concentration below or at the MDA levels measurable by AS). This work is the continuation of an article published in J. Anal. At. Spectrom. 25 (1410-1415) 2010. (authors)

  17. 239pu alpha spectrum analysis based on PIPS detector response function and variations with vacuum and distance

    Institute of Scientific and Technical Information of China (English)

    Rui Shi; Xian-Guo Tuo; Huai-Liang Li; Jian-Bo Yang; Yi Cheng; Hong-Long Zheng

    2017-01-01

    Effect factors of the absorption of the source,air,entrance window,and dead layer of a detector must be considered in the measurement of monoenergetic alpha particles,along with statsfical noise and other factors that collectively cause the alpha spectrum to exhibit a well-known low-energy tail.Therefore,the establishment of an alpha spectrum detector response function from the perspective of a signaling system must consider the various factors mentioned above.The detector response function is the convolution of an alphaparticle pulse function,two exponential functions,and a Gaussian function,followed by calculation of the parameters of the detector response function using the weighted leastsquares fitting method as proposed in this paper.In our experiment,239pu alpha spectra were measured by a highresolution,passivated implanted planar silicon (PIPS)detector at 10 levels of vacuum and 10 source-detector distances.The spectrum-fitting results were excellent as evaluated by reduced Chi-square (x2) and correlation coefficients.Finally,the variation of parameters with vacuum level and source-detector distance was studied.Results demonstrate that ο,τ1,and τ2 exhibit no obvious trend of variation with vacuum in the range 2000-20,000 mTorr,and at a confidence level of 95%,the values of τ1 and τ2 decline in a similar fashion with source-detector distance by the power exponential function,while the value of ο declines linearly.

  18. Plutonium activities and 240Pu/ 239Pu atom ratios in sediment cores from the east China sea and Okinawa Trough: Sources and inventories

    Science.gov (United States)

    Wang, Zhong-liang; Yamada, Masatoshi

    2005-05-01

    Plutonium concentrations and 240Pu/ 239Pu atom ratios in the East China Sea and Okinawa Trough sediment cores were determined by isotope dilution inductively coupled plasma mass spectrometry after separation using ion-exchange chromatography. The results showed that 240Pu/ 239Pu atom ratios in the East China Sea and Okinawa Trough sediments, ranging from 0.21 to 0.33, were much higher than the reported value of global fallout (0.18). The highest 240Pu/ 239Pu ratios (0.32-0.33) were observed in the deepest Okinawa Trough sediment samples. These ratios suggested the US nuclear weapons tests in the early 1950s at the Pacific Proving Grounds in the Marshall Islands were a major source of plutonium in the East China Sea and Okinawa Trough sediments, in addition to the global fallout source. It was proposed that close-in fallout plutonium was delivered from the Pacific Proving Grounds test sites via early direct tropospheric fallout and transportation by the North Pacific Equatorial Circulation system and Kuroshio Current into the Okinawa Trough and East China Sea. The total 239 + 240 Pu inventories in the cores were about 150-200% of that expected from direct global fallout; about 46-67% of the total inventories were delivered from the Pacific Proving Grounds. Much higher 239 + 240 Pu inventories were observed in the East China Sea sediments than in sediments of the Okinawa Trough, because in the open oceans, part of the 239 + 240 Pu was still retained in the water column, and continued Pu scavenging was higher over the margin than the trough. According to the vertical distributions of 239 + 240 Pu activities and 240Pu/ 239Pu atom ratios in these cores, it was concluded that sediment mixing was the dominant process in controlling profiles of plutonium in this area. Faster mixing in the coastal samples has homogenized the entire 240Pu/ 239Pu ratio record today; slightly slower mixing and less scavenging in the Okinawa Trough have left the surface sediment ratios closer

  19. Fission Product Data Measured at Los Alamos for Fission Spectrum and Thermal Neutrons on 239Pu, 235U, 238U

    International Nuclear Information System (INIS)

    Selby, H.D.; Mac Innes, M.R.; Barr, D.W.; Keksis, A.L.; Meade, R.A.; Burns, C.J.; Chadwick, M.B.; Wallstrom, T.C.

    2010-01-01

    for 99 Mo where the present results are about 4%-relative higher for neutrons incident on 239 Pu and 235 U. Additionally, our results illustrate the importance of representing the incident energy dependence of fission product yields over the fast neutron energy range for high-accuracy work, for example the 147 Nd from neutron reactions on plutonium. An upgrade to the ENDF library, for ENDF/B-VII.1, based on these and other data, is described in a companion paper to this work.

  20. Fission fragment charge and mass distributions in 239Pu(n ,f ) in the adiabatic nuclear energy density functional theory

    Science.gov (United States)

    Regnier, D.; Dubray, N.; Schunck, N.; Verrière, M.

    2016-05-01

    Background: Accurate knowledge of fission fragment yields is an essential ingredient of numerous applications ranging from the formation of elements in the r process to fuel cycle optimization for nuclear energy. The need for a predictive theory applicable where no data are available, together with the variety of potential applications, is an incentive to develop a fully microscopic approach to fission dynamics. Purpose: In this work, we calculate the pre-neutron emission charge and mass distributions of the fission fragments formed in the neutron-induced fission of 239Pu using a microscopic method based on nuclear density functional theory (DFT). Methods: Our theoretical framework is the nuclear energy density functional (EDF) method, where large-amplitude collective motion is treated adiabatically by using the time-dependent generator coordinate method (TDGCM) under the Gaussian overlap approximation (GOA). In practice, the TDGCM is implemented in two steps. First, a series of constrained EDF calculations map the configuration and potential-energy landscape of the fissioning system for a small set of collective variables (in this work, the axial quadrupole and octupole moments of the nucleus). Then, nuclear dynamics is modeled by propagating a collective wave packet on the potential-energy surface. Fission fragment distributions are extracted from the flux of the collective wave packet through the scission line. Results: We find that the main characteristics of the fission charge and mass distributions can be well reproduced by existing energy functionals even in two-dimensional collective spaces. Theory and experiment agree typically within two mass units for the position of the asymmetric peak. As expected, calculations are sensitive to the structure of the initial state and the prescription for the collective inertia. We emphasize that results are also sensitive to the continuity of the collective landscape near scission. Conclusions: Our analysis confirms

  1. Prompt fissionγ-ray characteristics from neutron-induced fission on 239Pu and the time-dependence of prompt-γray emission

    Science.gov (United States)

    Gatera, Angélique; Göök, Alf; Hambsch, Franz-Josef; Moens, André; Oberstedt, Andreas; Oberstedt, Stephan; Sibbens, Goedele; Vanleeuw, David; Vidali, Marzio

    2018-03-01

    Recent years have seen an increased interest in prompt fission γ-ray (PFG) measurements motivated by a high priority request of the OECD/NEA for high precision data, mainly for the nuclear fuel isotopes 235U and 239Pu. Our group has conducted a PFG measurement campaign using state-of-the-art lanthanum halide detectors for all the main actinides to a precision better than 3%. The experiments were performed in a coincidence setup between a fission trigger and γ-ray detectors. The time-of-flight technique was used to discriminate photons, traveling at the speed of light, and prompt fission neutrons. For a full rejection of all neutrons below 20 MeV, the PFG time window should not be wider than a few nanoseconds. This window includes most PFG, provided that no isomeric states were populated during the de-excitation process. When isomeric states are populated, PFGs can still be emitted up to 1 yus after the instant of fission or later. To study these γ-rays, the detector response to neutrons had to be determined and a correction had to be applied to the γ-ray spectra. The latest results for PFG characteristics from the reaction 239Pu(nth,f) will be presented, together with an analysis of PFGs emitted up to 200 ns after fission in the spontaneous fission of 252Cf as well as for thermal-neutron induced fission on 235U and 239Pu. The results are compared with calculations in the framework of the Hauser-Feshbach Monte Carlo code CGMF and FIFRELIN.

  2. Solubility of reactor fuels in the mouse lung with respect to their U/Pu and 238Pu/239Pu ratios

    International Nuclear Information System (INIS)

    Talbot, R.J.; Baker, S.T.

    1989-01-01

    The studies reported were designed to assess the comparative in vivo solubilities of a range of plutonium containing reactor fuels. To simulate these fuels, mixed U/Pu oxides were prepared and calcined at 1600 0 C. A plutonium content of 3% w/w was chosen as typical of water-cooled reactor fuel. Higher concentrations of plutonium (10, 20 and 30%) were included to simulate fast reactor fuel. As it is known that 238 PuO 2 , with high specific activity, is translocated more rapidly from lung than 239 PuO 2 , the effect of isotopic composition of plutonium in simulated reactor fuels was also investigated. For this purpose, both the water-cooled and fast-reactor fuels were prepared with plutonium containing 2% of 238 Pu by weight. The resulting oxides had about 6 times the specific activity of those prepared with 239 Pu. Groups of mice were killed at 1, 3, 6, 12 and 18 months after inhaling aerosols of the simulated reactor fuels. After 3 months, measurements of Pu retention in the lung showed no marked differences between materials. After 6 months, measurements of plutonium deposited in the liver and skeleton showed that mixed U/Pu oxides were more soluble in vivo than 239 PuO 2 . Their solubility was inversely related to their plutonium content. The addition of 238 Pu to the plutonium resulted in enhanced translocation of plutonium from the lung, in the cases of water-cooled reactor fuel by a factor of two. (author)

  3. Exploratory study of fission product yields of neutron-induced fission of 235U , 238U , and 239Pu at 8.9 MeV

    Science.gov (United States)

    Bhatia, C.; Fallin, B. F.; Gooden, M. E.; Howell, C. R.; Kelley, J. H.; Tornow, W.; Arnold, C. W.; Bond, E.; Bredeweg, T. A.; Fowler, M. M.; Moody, W.; Rundberg, R. S.; Rusev, G. Y.; Vieira, D. J.; Wilhelmy, J. B.; Becker, J. A.; Macri, R.; Ryan, C.; Sheets, S. A.; Stoyer, M. A.; Tonchev, A. P.

    2015-06-01

    Using dual-fission chambers each loaded with a thick (200 -400 -mg /c m2) actinide target of 235 ,238U or 239Pu and two thin (˜10 -100 -μ g /c m2) reference foils of the same actinide, the cumulative yields of fission products ranging from 92Sr to 147Nd have been measured at En= 8.9 MeV . The 2H(d ,n ) 3He reaction provided the quasimonoenergetic neutron beam. The experimental setup and methods used to determine the fission product yield (FPY) are described, and results for typically eight high-yield fission products are presented. Our FPYs for 235U(n ,f ) , 238U(n ,f ) , and 239Pu(n ,f ) at 8.9 MeV are compared with the existing data below 8 MeV from Glendenin et al. [Phys. Rev. C 24, 2600 (1981), 10.1103/PhysRevC.24.2600], Nagy et al. [Phys. Rev. C 17, 163 (1978), 10.1103/PhysRevC.17.163], Gindler et al. [Phys. Rev. C 27, 2058 (1983), 10.1103/PhysRevC.27.2058], and those of Mac Innes et al. [Nucl. Data Sheets 112, 3135 (2011), 10.1016/j.nds.2011.11.009] and Laurec et al. [Nucl. Data Sheets 111, 2965 (2010), 10.1016/j.nds.2010.11.004] at 14.5 and 14.7 MeV, respectively. This comparison indicates a negative slope for the energy dependence of most fission product yields obtained from 235U and 239Pu , whereas for 238U the slope issue remains unsettled.

  4. Feasibility study of {sup 235}U and {sup 239}Pu characterization in radioactive waste drums using neutron-induced fission delayed gamma rays

    Energy Technology Data Exchange (ETDEWEB)

    Nicol, T. [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France); FZJ, Institute of Energy and Climate Research – Nuclear Waste Management and Reactor Safety, Wilhelm-Johnen-Straße, d-52425 Jülich (Germany); Pérot, B., E-mail: bertrand.perot@cea.fr [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France); Carasco, C. [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France); Brackx, E. [CEA, DEN, Marcoule, Metallography and Chemical Analysis Laboratory, F-30207 Bagnols-sur-Cèze (France); Mariani, A.; Passard, C. [CEA, DEN, Cadarache, Nuclear Measurement Laboratory, F-13108 Saint-Paul-lez-Durance (France); Mauerhofer, E. [FZJ, Institute of Energy and Climate Research – Nuclear Waste Management and Reactor Safety, Wilhelm-Johnen-Straße, d-52425 Jülich (Germany); Collot, J. [Laboratoire de Physique Subatomique et de Cosmologie, Université Grenoble Alpes, CNRS/IN2P3 Grenoble (France)

    2016-10-01

    This paper reports a feasibility study of {sup 235}U and {sup 239}Pu characterization in 225 L bituminized waste drums or 200 L concrete waste drums, by detecting delayed fission gamma rays between the pulses of a deuterium-tritium neutron generator. The delayed gamma yields were first measured with bare samples of {sup 235}U and {sup 239}Pu in REGAIN, a facility dedicated to the assay of 118 L waste drums by Prompt Gamma Neutron Activation Analysis (PGNAA) at CEA Cadarache, France. Detectability in the waste drums is then assessed using the MCNPX model of MEDINA (Multi Element Detection based on Instrumental Neutron Activation), another PGNAA cell dedicated to 200 L drums at FZJ, Germany. For the bituminized waste drum, performances are severely hampered by the high gamma background due to {sup 137}Cs, which requires the use of collimator and shield to avoid electronics saturation, these elements being very penalizing for the detection of the weak delayed gamma signal. However, for lower activity concrete drums, detection limits range from 10 to 290 g of {sup 235}U or {sup 239}Pu, depending on the delayed gamma rays of interest. These detection limits have been determined by using MCNPX to calculate the delayed gamma useful signal, and by measuring the experimental gamma background in MEDINA with a 200 L concrete drum mock-up. The performances could be significantly improved by using a higher interrogating neutron emission and an optimized experimental setup, which would allow characterizing nuclear materials in a wide range of low and medium activity waste packages.

  5. Evaluation of fission cross sections and covariances for {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Matsunobu, Hiroyuki [Data Engineering, Inc. (Japan); Murata, Toru [AITEL Corporation, Tokyo (JP)] [and others

    2000-02-01

    A simultaneous evaluation code SOK (Simultaneous evaluation on KALMAN) has been developed, which is a least-squares fitting program to absolute and relative measurements. The SOK code was employed to evaluate the fission cross sections of {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu for the evaluated nuclear data library JENDL-3.3. Procedures of the simultaneous evaluation and the experimental database of the fission cross sections are described. The fission cross sections obtained were compared with evaluated values given in JENDL-3.2 and ENDF/B-VI. (author)

  6. Evaluation of fission cross sections and covariances for 233U, 235U, 238U, 239Pu, 240Pu, and 241Pu

    International Nuclear Information System (INIS)

    Kawano, Toshihiko; Matsunobu, Hiroyuki; Murata, Toru

    2000-02-01

    A simultaneous evaluation code SOK (Simultaneous evaluation on KALMAN) has been developed, which is a least-squares fitting program to absolute and relative measurements. The SOK code was employed to evaluate the fission cross sections of 233 U, 235 U, 238 U, 239 Pu, 240 Pu, and 241 Pu for the evaluated nuclear data library JENDL-3.3. Procedures of the simultaneous evaluation and the experimental database of the fission cross sections are described. The fission cross sections obtained were compared with evaluated values given in JENDL-3.2 and ENDF/B-VI. (author)

  7. Determination of /sup 240/Pu//sup 239/Pu ratio in the environmental samples based on the measurement of Lx/. cap alpha. -ray activity ratio

    Energy Technology Data Exchange (ETDEWEB)

    Komura, K.; Sakanoue, M.; Yamamoto, M.

    1984-06-01

    The determination of the /sup 240/Pu//sup 239/Pu isotopic ratio in environmental samples has been attempted by the measurement of the Lx/..cap alpha..-ray activity ratio using a Ge-LEPS (low-energy photon spectrometer) and a surface-barrier Si detector. By this method, interesting data were obtained for various samples collected from Thule, Greenland, Bikini Atoll and Nagasaki, as well as for some soils collected from near and off-site locations of atomic power stations.

  8. Speciation analysis of 129I, 137Cs, 232Th, 238U, 239Pu and 240Pu in environmental soil and sediment

    DEFF Research Database (Denmark)

    Qiao, Jixin; Hansen, Violeta; Hou, Xiaolin

    2012-01-01

    The environmental mobility and bioavailability of radionuclides are related to their physicochemical forms, namely species. We here present a speciation analysis of important radionuclides including 129I (also 127I), 137Cs, 232Th, 238U and plutonium isotopes (239Pu and 240Pu) in soil (IAEA-375......) and sediment (NIST-4354) standard reference materials and two fresh sediment samples from Øvre Heimdalsvatnet Lake, Norway. A modified sequential extraction protocol was used for the speciation analysis of these samples to obtain fractionation information of target radionuclides. Analytical results reveal...

  9. Transmutation of 239Pu and other nuclides using spallation neutrons produced by relativistic protons reacting with massive U- and Pb- targets

    International Nuclear Information System (INIS)

    Adam, J.; Balabekyan, A.; Bamblevskij, V.P.

    2001-01-01

    Experimental studies on the transmutation of some long-lived radioactive waste nuclei, such as 129 I, 237 Np, and 239 Pu, as well as on natural uranium and lanthanum (all of them used as sensors) were carried out at the Synchrophasotron of the Laboratory of High Energies (JINR, Dubna). Spallation neutrons were produced by relativistic protons with energies in the range of 0.5 GeV ≤ E(p) ≤ 1.5 GeV interacting with 20 cm long uranium or lead target stacks. The targets were surrounded by 6 cm paraffin moderators. The radioactive sensors mentioned above were positioned on the outside surface of the moderator and contained typically approximately 0.5 up to 1 gram of long-lived isotopes. The highly radioactive targets were produced perfectly well-sealed in aluminium containers by the Institute of Physics and Power Engineering, Obninsk, Russia. From the experimentally observed transmutation rates one can easily extrapolate, that in a subcritical nuclear power assembly (or 'energy amplifier') using a 10 mA proton beam of 1 GeV onto a Pb-target as used here, one can transmute in one gram samples of the isotope within one month about 3 mg 129 I, 21 mg 237 Np, 3.3 mg 238 U, and 200 mg 239 Pu under the same geometrical conditions. Our observations show, that the transmutation ability of our system increases linearly with the proton energy within the energy interval studied

  10. Criticality Data for Spherical 235U, 239Pu, and 237Np Systems Reflector-Moderated by Low Capturing-Moderator Materials

    International Nuclear Information System (INIS)

    Loaiza, David J.; Stratton, William

    2004-01-01

    The critical dimensions of spherical systems moderated and reflected by low-capturing materials such as D 2 O, BeO, Be, and C were investigated. A parametric study of the critical mass of enriched uranium, plutonium, and neptunium is examined and tabulated. The results obtained expand on the understanding of reflector-moderated critical systems, and they show regions of unstable criticality for 235 U and 239 Pu reflected cores at intermediate densities. This instability is illustrated by calculations of the positive reactivity coefficient of volume expansion. The coefficient is positive, not negative, in the intermediate density region for 235 U and 239 Pu systems. For 237 Np cores reflected by the same moderator, the effect is negligible. The critical dimensions were calculated with the DANTSYS codes using the Hansen-Roach cross-section libraries. This study is both a summary of mostly unpublished calculations and new calculations. Experimental data for these configurations are extremely limited. These are examined in the text when applicable

  11. Neutron induced fission cross sections for /sup 232/Th, /sup 235,238/U, /sup 237/Np and /sup 239/Pu from 1 to 400 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Lisowski, P.W.; Ullmann, J.L.; Balestrini, S.J.; Carlson, A.D.; Wasson, O.A.; Hill, N.W.

    1988-01-01

    Neutron-induced fission cross section ratios for samples of /sup 232/Th, /sup 235,238/U, /sup 237/Np and /sup 239/Pu have been measured from 1 to 400 MeV. The fission reaction rate was determined for all samples simultaneously using a fast parallel plate ionization chamber at a 20-m flight path. A well characterized annular proton recoil telescope was used to measure the neutron fluence up to 30 MeV. These data provided the shape of the /sup 235/U(n,f) cross section relative to the hydrogen scattering cross section. That shape was then normalized to the very accurately known values were determined using the neutron fluence measured with a second proton recoil telescope. Cross section values for /sup 232/Th, /sup 238/U, /sup 237/Np, and /sup 239/Pu were computed from the ratio data using our values for /sup 235/U(n,f). In addition to providing new results at high neutron energies, these data resolve long standing discrepancies among different data sets. 1 ref., 1 fig.

  12. New prompt fission gamma-ray spectral data from 239Pu(nth, f in response to a high priority request from OECD Nuclear Energy Agency

    Directory of Open Access Journals (Sweden)

    Gatera Angélique

    2017-01-01

    Full Text Available Benchmark reactor calculations have revealed an underestimation of γ-heat following fission of up to 28%. To improve the modelling of new nuclear reactors, the OECD/NEA initiated a nuclear data High Priority Request List (HPRL entry for the major isotopes (235U, 239Pu. In response to that HPRL entry, we executed a dedicated measurement program on prompt fission γ-rays employing state-of-the-art lanthanum bromide (LaBr3 detectors with superior timing and good energy resolution. Our new results from 252Cf(sf, 235U(nth,f and 241Pu(nth,f provide prompt fission γ-ray spectra characteristics : average number of photons per fission, average total energy per fission and mean photon energy; all within 2% of uncertainty. We present preliminary results on 239Pu(nth,f, recently measured at the Budapest Neutron Centre and supported by the CHANDA Trans-national Access Activity, as well as discussing our different published results in comparison to the historical data and what it says about the discrepancy observed in the benchmark calculations.

  13. Reexamining the role of the (n ,γ f ) process in the low-energy fission of 235U and 239Pu

    Science.gov (United States)

    Lynn, J. E.; Talou, P.; Bouland, O.

    2018-06-01

    The (n ,γ f ) process is reviewed in light of modern nuclear reaction calculations in both slow and fast neutron-induced fission reactions on 235U and 239Pu. Observed fluctuations of the average prompt fission neutron multiplicity and average total γ -ray energy below 100-eV incident neutron energy are interpreted in this framework. The surprisingly large contribution of the M 1 transitions to the prefission γ -ray spectrum of 239Pu is explained by the dominant fission probabilities of 0+ and 2+ transition states, which can only be accessed from compound nucleus states formed by the interaction of s -wave neutrons with the target nucleus in its ground state, and decaying through M 1 transitions. The impact of an additional low-lying M 1 scissors mode in the photon strength function is analyzed. We review experimental evidence for fission fragment mass and kinetic-energy fluctuations in the resonance region and their importance in the interpretation of experimental data on prompt neutron data in this region. Finally, calculations are extended to the fast energy range where (n ,γ f ) corrections can account for up to 3% of the total fission cross section and about 20% of the capture cross section.

  14. Relative radiosensitivity of bone tumor induction among beagles as a function of age at injection of 239Pu or 226Ra

    International Nuclear Information System (INIS)

    Lloyd, R.D.; Taylor, G.N.; Jee, W.S.S.; Miller, S.C.

    1999-01-01

    A comparison was made of the response to induction of skeletal malignancy from exposure of beagles to monomeric 239 Pu or to 226 Ra as juveniles (3 mo of age), young adults (1.5 y of age), or mature adults (5 y of age). This indicated that of these age groups, animals injected as young adults are most sensitive per Gy of average skeletal dose evaluated at 1 y before death. Dogs exposed either as juveniles or as mature adults appeared to be less sensitive. Relative radiosensitivities (RRS) of juvenile and mature beagles ranged between about 0.3 and 0.7 that of dogs injected as young adults. Mean values of RRS for both radionuclides were about 0.5, but RRS values derived from dogs given monomeric 239 Pu appeared to be most reliable and were 0.27 ± 0.09 for dogs injected as juveniles and 0.41 ± 0.13 for animals exposed as mature adults

  15. Determination of 239Pu and 240Pu isotope ratio for a nuclear bomb particle using X-ray spectrometry in conjunction with γ-ray spectrometry and non-destructive α-particle spectrometry

    International Nuclear Information System (INIS)

    Poellaenen, R.; Ruotsalainen, K.; Toivonen, H.

    2009-01-01

    A nuclear bomb particle from Thule containing Pu and U was analyzed using X-ray spectrometry in combination with γ-ray spectrometry and non-destructive α-spectrometry. The main objective was to investigate the possibility to determine the 239 Pu and 240 Pu isotope ratios. Previously, X-ray spectrometry together with the above-mentioned methods has been successfully applied for radiochemically processed samples, but not for individual particles. In the present paper we demonstrate the power of non-destructive analysis. The 239 Pu/( 239 Pu+ 240 Pu) atom ratio for the Thule particle was determined, using two different approaches, to be 0.93±0.07 and 0.91±0.05. These results are consistent with weapons-grade material and the results obtained by other investigators.

  16. Determination of 240Pu/239Pu isotopic ratios in human tissues collected from areas around the Semipalatinsk Nuclear Test Site by sector-field high resolution ICP-MS.

    Science.gov (United States)

    Yamamoto, M; Oikawa, S; Sakaguchi, A; Tomita, J; Hoshi, M; Apsalikov, K N

    2008-09-01

    Information on the 240Pu/239Pu isotope ratios in human tissues for people living around the Semipalatinsk Nuclear Test Site (SNTS) was deduced from 9 sets of soft tissues and bones, and 23 other bone samples obtained by autopsy. Plutonium was radiochemically separated and purified, and plutonium isotopes (239Pu and 240Pu) were determined by sector-field high resolution inductively coupled plasma-mass spectrometry. For most of the tissue samples from the former nine subjects, low 240Pu/239Pu isotope ratios were determined: bone, 0.125 +/- 0.018 (0.113-0.145, n = 4); lungs, 0.063 +/- 0.010 (0.051-0.078, n = 5); and liver, 0.148 +/- 0.026 (0.104-0.189, n = 9). Only 239Pu was detected in the kidney samples; the amount of 240Pu was too small to be measured, probably due to the small size of samples analyzed. The mean 240Pu/239Pu isotope ratio for bone samples from the latter 23 subjects was 0.152 +/- 0.034, ranging from 0.088 to 0.207. A significant difference (a two-tailed Student's t test; 95% significant level, alpha = 0.05) between mean 240Pu/239Pu isotope ratios for the tissue samples and for the global fallout value (0.178 +/- 0.014) indicated that weapons-grade plutonium from the atomic bombs has been incorporated into the human tissues, especially lungs, in the residents living around the SNTS. The present 239,240Pu concentrations in bone, lung, and liver samples were, however, not much different from ranges found for human tissues from other countries that were due solely to global fallout during the 1970's-1980's.

  17. Effect of microdose distribution on chromosome aberration frequency in liver cells of the Chinese hamster following exposure to 239PuO2 or 238PuO2 particles

    International Nuclear Information System (INIS)

    Brooks, A.L.; Peters, R.F.; Retherford, J.C.

    1974-01-01

    Chinese hamsters were injected intravenously with 239 PuO 2 or 238 PuO 2 particles of known size or with 238 Pu citrate to determine the effect of particle size and specific activity on the frequency and distribution of chromosome damage in the liver. Three particle sizes were used in the 239 PuO 2 experiment: 0.15, 0.44, and 0.89 μm, and all animals were injected with a constant activity, 5 x 10 -4 muCi 239 Pu/gm body weight. The 238 PuO 2 was injected in three particle sizes, 0.17, 0.41, and 1.1 μm and at three activity levels. The 238 Pu citrate was injected at 5 x 10 -3 muCi 238 Pu/gm body weight. Hamsters injected with 239 PuO 2 were sacrificed at 15, 42, and 122 days after injection and those injected with either 238 PuO 2 or 238 Pu citrate were sacrificed 12 days after injection. The number of alpha tracks/star increased as a function of the particle size injected. A change in particle size with time was noted as smaller particles were aggregated into larger ones by the phagocytic action of Kupffer cells. Injection of 239 PuO 2 and 238 PuO 2 produced a distribution of chromosome damage which was non-poison in nature. 239 PuO 2 produced increased damage with increasing average dose with some cells containing a large number of aberrations, but there was relatively little particle size effect. Conversely, aberration frequencies after 238 PuO 2 injection were inversely related to particle size and no cells were seen with large amounts of damage. The 238 Pu citrate produced 6 x 10 -3 aberrations/cell/rad which was a higher rate than observed for 238 Pu particles. Risk for the production of cellular damage in the liver was greater per μCi following injection of either 238 Pu or 239 Pu citrate than it was following deposition of the same amount of 239 PuO 2 or 238 PuO 2 particles. (U.S.)

  18. 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.

  19. Neutron induced fission cross section ratios for 232Th, 235,238U, 237Np and 239Pu from 1 to 400 MeV

    International Nuclear Information System (INIS)

    Lisowski, P.W.; Ullmann, J.L.; Balestrini, S.J.; Carlson, A.D.; Wasson, O.A.; Hill, N.W.

    1988-01-01

    Time-of-flight measurements of neutron induced fission cross section ratios for 232 Th, 235,238 U, 237 Np, and 239 Pu, were performed using the WNR high intensity spallation neutron source located at Los Alamos National Laboratory. A multiple-plate gas ionization chamber located at a 20-m flight path was used to simultaneously measure the fission rate for all samples over the energy range from 1 to 400 MeV. Because the measurements were made with nearly identical neutron fluxes, we were able to cancel many systematic uncertainties present in previous measurements. This allows us to resolve discrepancies among different data sets. In addition, these are the first neutron-induced fission cross section values for most of the nuclei at energies above 30 MeV. (author)

  20. Neutron induced fission cross section ratios for 232Th, /sup 235,238/U, 237Np, and 239Pu from 1 to 400 MeV

    International Nuclear Information System (INIS)

    Lisowski, P.W.; Ullmann, J.L.; Balestrini, S.J.; Carlson, A.D.; Wasson, O.A.; Hill, N.W.

    1988-01-01

    Time-of-flight measurements of neutron induced fission cross section ratios for 232 Th, /sup 235,238/U, 237 Np, and 239 Pu, were performed using the WNR high intensity spallation neutron source located at Los Alamos National Laboratory. A multiple-plate gas ionization chamber located at a 20-m flight path was used to simultaneously measure the fission rate for all samples over the energy range from 1 to 400 MeV. Because the measurements were made with nearly identical neutron fluxes, we were able to cancel many systematic uncertainties present in previous measurements. This allows us to resolve discrepancies among different data sets. In addition, these are the first neutron-induced fission cross section values for most of the nuclei at energies above 30 MeV. 8 refs., 3 figs

  1. Determination of 233U, 235U, 238U and 239Pu fission yields induced by fission and 14.7 MeV neutrons

    International Nuclear Information System (INIS)

    Laurec, Jean; Adam, Albert; Bruyne, Thierry de.

    1981-12-01

    The 233 U, 235 U, 238 U, 239 Pu fission yields have been determined by a radiochemical method. A target and a fission chamber made of same fissible material are irradied together. The total fission number is measured from the fission chamber. The fission product activities are directly measured on the target using calibrated Ge-Li detectors. The fissible material masses are determined by alpha and mass spectrometries. The irradiations were made on the critical assemblies PROSPERO and CALIBAN and on the 14 MeV neutron generator of C.E. VALDUC. 3 to 5% fission yield errors are got for the most measured nuclides: 95 Zr, 97 Zr, 99 Mo, 103 Ru, 131 I, 132 Te, 140 Ba, 141 Ce, 143 Ce, 144 Ce, 147 Nd [fr

  2. Simultaneous measurement of 239Pu, 240Pu, 241Pu, and 242Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments

    International Nuclear Information System (INIS)

    Bruneau, F.

    1999-01-01

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of 239 Pu, 240 Pu, 241 Pu, and 242 Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  3. Study of the variation with the energy of the fission cross-sections of 233U, 235U, 239Pu for the fast neutrons

    International Nuclear Information System (INIS)

    Szteinsznaider, D.; Naggiar, V.; Netter, F.

    1955-01-01

    This measurements have been done while taking the value of the fission cross-sections of 238 U as reference. The neutrons are produced by the reaction 7 Li(p,n) in the Van de Graaff generator of Saclay. The explored domain spreads from some tenths to 2000 keV. We find: for 239 Pu: σ f = 2,04 ± 0,12 barns, cross-section constant between 150 and 2000 keV, for 235 U: σ f = 1,15 ± 0,15 barns, cross-section constant between 700 and 1000 keV, for 233 U: σ f = 1,92 ± 0,25 barns, for neutrons of 850 keV. (authors) [fr

  4. Measurement of prompt neutron spectra from the "2"3"9Pu(n, f ) fission reaction for incident neutron energies from 1 to 200 MeV

    International Nuclear Information System (INIS)

    Chatillon, A.; Belier, G.; Granier, T.; Laurent, B.; Morillon, B.; Taieb, J.; Haight, R.C.; Devlin, M.; Nelson, R.O.; Noda, R.S.; O'Donnell, J.M.

    2014-01-01

    Prompt fission neutron spectra in the neutron-induced fission of "2"3"9Pu have been measured for incident neutron energies from 1 to 200 MeV at the Los Alamos Neutron Science Center. Mean energies deduced from the prompt fission neutron spectra (PFNS) lead to the observation of the opening of the second chance fission at 7 MeV and to indications for the openings of fission channels of third and fourth chances. Moreover, the general trend of the measured PFNS is well reproduced by the different models. The comparison between data and models presents, however, two discrepancies. First, the prompt neutron mean energy seems constant for neutron energy, at least up to 7 MeV, whereas in the theoretical calculations it is continuously increasing. Second, data disagree with models on the shape of the high energy part of the PFNS, where our data suggest a softer spectrum than the predictions. (authors)

  5. Integration of measurements with atmospheric dispersion models: Source term estimation for dispersal of (239)Pu due to non-nuclear detonation of high explosive

    Science.gov (United States)

    Edwards, L. L.; Harvey, T. F.; Freis, R. P.; Pitovranov, S. E.; Chernokozhin, E. V.

    1992-10-01

    The accuracy associated with assessing the environmental consequences of an accidental release of radioactivity is highly dependent on our knowledge of the source term characteristics and, in the case when the radioactivity is condensed on particles, the particle size distribution, all of which are generally poorly known. This paper reports on the development of a numerical technique that integrates the radiological measurements with atmospheric dispersion modeling. This results in a more accurate particle-size distribution and particle injection height estimation when compared with measurements of high explosive dispersal of (239)Pu. The estimation model is based on a non-linear least squares regression scheme coupled with the ARAC three-dimensional atmospheric dispersion models. The viability of the approach is evaluated by estimation of ADPIC model input parameters such as the ADPIC particle size mean aerodynamic diameter, the geometric standard deviation, and largest size. Additionally we estimate an optimal 'coupling coefficient' between the particles and an explosive cloud rise model. The experimental data are taken from the Clean Slate 1 field experiment conducted during 1963 at the Tonopah Test Range in Nevada. The regression technique optimizes the agreement between the measured and model predicted concentrations of (239)Pu by varying the model input parameters within their respective ranges of uncertainties. The technique generally estimated the measured concentrations within a factor of 1.5, with the worst estimate being within a factor of 5, very good in view of the complexity of the concentration measurements, the uncertainties associated with the meteorological data, and the limitations of the models. The best fit also suggest a smaller mean diameter and a smaller geometric standard deviation on the particle size as well as a slightly weaker particle to cloud coupling than previously reported.

  6. Integration of measurements with atmospheric dispersion models: Source term estimation for dispersal of 239Pu due to non- nuclear detonation of high explosive

    International Nuclear Information System (INIS)

    Edwards, L.L.; Harvey, T.F.; Freis, R.P.; Pitovranov, S.E.; Chernokozhin, E.V.

    1992-10-01

    The accuracy associated with assessing the environmental consequences of an accidental release of radioactivity is highly dependent on our knowledge of the source term characteristics and, in the case when the radioactivity is condensed on particles, the particle size distribution, all of which are generally poorly known. This paper reports on the development of a numerical technique that integrates the radiological measurements with atmospheric dispersion modeling. This results in a more accurate particle-size distribution and particle injection height estimation when compared with measurements of high explosive dispersal of 239 Pu. The estimation model is based on a non-linear least squares regression scheme coupled with the ARAC three-dimensional atmospheric dispersion models. The viability of the approach is evaluated by estimation of ADPIC model input parameters such as the ADPIC particle size mean aerodynamic diameter, the geometric standard deviation, and largest size. Additionally we estimate an optimal ''coupling coefficient'' between the particles and an explosive cloud rise model. The experimental data are taken from the Clean Slate 1 field experiment conducted during 1963 at the Tonopah Test Range in Nevada. The regression technique optimizes the agreement between the measured and model predicted concentrations of 239 Pu by varying the model input parameters within their respective ranges of uncertainties. The technique generally estimated the measured concentrations within a factor of 1.5, with the worst estimate being within a factor of 5, very good in view of the complexity of the concentration measurements, the uncertainties associated with the meteorological data, and the limitations of the models. The best fit also suggest a smaller mean diameter and a smaller geometric standard deviation on the particle size as well as a slightly weaker particle to cloud coupling than previously reported

  7. Radionuclide concentrations in soils and vegetation at Low-Level Radioactive Waste Disposal Area G during the 1998 growing season (with a cumulative summary of 3H and 239Pu over time)

    International Nuclear Information System (INIS)

    Fresquez, P.R.; Ebinger, M.H.; Wechsler, R.J.; Naranjo, L. Jr.

    1999-01-01

    Soils and unwashed overstory and understory vegetation were collected at eight locations within and around Area G, a disposal facility for low-level, radioactive solid waste at Los Alamos National Laboratory. The samples were analyzed for 3 H, 238 Pu, 239 Pu, 90 Sr, 241 Am, 137 Cs, tot U. Most of the radionuclide concentrations in soils and vegetation were within the upper 95% level of background concentrations except for 3 H and 239 Pu. Tritium concentrations in vegetation from most sites were greater than background concentrations of about 2 pCi mL -1 . The concentrations of 239 Pu in soils and understory vegetation were largest in samples collected several meters north of the transuranic waste pad area and were consistent with previous results. Based on 3 H and 239 Pu data through 1998, it was shown that concentrations were (1) significantly greater than background concentrations (p < 0.05) in soils and vegetation collected from most locations at Area G, and (2) there was no systematic increase or decrease in concentrations with time apparent in the data

  8. Radionuclide concentrations in soils and vegetation at Low-Level Radioactive Waste Disposal Area G during the 1998 growing season (with a cumulative summary of {sup 3}H and {sup 239}Pu over time)

    Energy Technology Data Exchange (ETDEWEB)

    P. R. Fresquez; M. H. Ebinger; R. J. Wechsler; L. Naranjo, Jr.

    1999-11-01

    Soils and unwashed overstory and understory vegetation were collected at eight locations within and around Area G, a disposal facility for low-level, radioactive solid waste at Los Alamos National Laboratory. The samples were analyzed for {sup 3}H, {sup 238}Pu, {sup 239}Pu, {sup 90}Sr, {sup 241}Am, {sup 137}Cs, {sup tot}U. Most of the radionuclide concentrations in soils and vegetation were within the upper 95% level of background concentrations except for {sup 3}H and {sup 239}Pu. Tritium concentrations in vegetation from most sites were greater than background concentrations of about 2 pCi mL{sup {minus}1}. The concentrations of {sup 239}Pu in soils and understory vegetation were largest in samples collected several meters north of the transuranic waste pad area and were consistent with previous results. Based on {sup 3}H and {sup 239}Pu data through 1998, it was shown that concentrations were (1) significantly greater than background concentrations (p < 0.05) in soils and vegetation collected from most locations at Area G, and (2) there was no systematic increase or decrease in concentrations with time apparent in the data.

  9. A comparison of the natural survival of beagle dogs injected intravenously with low levels of 239Pu, 226Ra, 228Ra, 228Th, or 90Sr

    International Nuclear Information System (INIS)

    Bruenger, F.W.; Miller, S.C.; Lloyd, R.D.

    1991-01-01

    The natural survival, relative to properly chosen controls, of 26 beagle dogs injected once intravenously with an average of 0.58 +/- 0.04 kBq 239 Pu/kg, 23 dogs injected with 2.31 +/- 0.43 kBq 226 Ra/kg, 13 dogs injected with 1.84 +/- 0.26 kBq 228 Ra/kg, 12 dogs injected with 0.56 +/- 0.030 kBq 228 Th/kg, and 12 dogs injected with 21.13 +/- 1.74 kBq 90 Sr/kg was evaluated statistically. The amounts of these radionuclides are related directly to the estimated maximum permissible body burdens for humans suggested in ICRP II (1959). They constitute a level of exposure that initially was assumed to cause no deleterious effects in dogs. This study had two objectives: (1) identification of homogeneous control groups against which to evaluate the survival of the irradiated groups and (2) comparison of the survival characteristics and estimation of mortality or hazard rate ratios for control dogs vs dogs injected with the baseline dosages given above. It was shown, by goodness-of-fit plots, that the Cox proportional hazards model was an appropriate method of analysis. Therefore, covariates that possibly could influence survival were tested for significance. Only the effects of grand mal seizure, which is caused in epileptic dogs by an external stimulus and can be fatal if untreated, were significant (P less than 0.0001). Consequently, in the final model, death from grand mal seizure was considered as accidental. After censoring the dogs dying from grand mal seizure, it was established that the data for the control groups from previous and contemporary experiments could be pooled. The change in hazard rates relative to controls resulting from exposure to the baseline radionuclide level was modest, 1.6 times for 239 Pu (P = 0.033), 1.0(4) for 226 Ra (P = 0.86), 1.9 for 228 Ra (P = 0.035), 2.5 for 228 Th (P less than 0.001), and 0.52 for 90 Sr (P = 0.041)

  10. Capture and Fission rate of 232-Th, 238-U, 237-Np and 239-Pu from spallation neutrons in a huge block of lead.

    CERN Document Server

    Vlachoudis, Vasilis

    2000-01-01

    The study is centered on the research of the incineration possibility of nuclear waste, by the association of a particle accelerator with a multiplying medium of neutrons, in the project "Energy Amplifier" of C. Rubbia. It consists of the experimental determination of the rates of capture and fission of certain elements (232-Th, 238-U, 237-Np and 239-Pu) subjected to a fluence of fast spallation neutrons. These neutrons are produced by the interaction of high kinetic energy protons (several GeV) provided by the CERN-PS accelerator, on a large lead solid volume. The measurement techniques used in this work, are based on the activation of elements in the lead volume and the subsequent gamma spectroscopy of the activated elements, and also by the detection of fission fragment traces. The development, of a Monte Carlo code makes it possible, on one hand, to better understand the relevant processes, and on the other hand, to validate the code, by comparison with measurements, for the design and the construction of...

  11. Inhaled /sup 239/PuO/sub 2/ and/or total-body gamma radiation: Early mortality and morbidity in rats and dogs

    Energy Technology Data Exchange (ETDEWEB)

    Filipy, R.E.; Decker, J.R.; Lai, Y.L.; Lauhala, K.E.; Buschbom, R.L.; Hiastala, M.P.; McGee, D.R.; Park, J.F.; Kuffel, E.G.; Ragan, H.A.; Cannon, W.C.; Yaniv, S.S.; Scott, B.R.

    1988-08-01

    Rats and beagle dogs were given doses of /sup 60/Co gamma radiation and/or body burdens of /sup 239/PuO/sub 2/ within lethal ranges in an experiment to determine and compare morbidity and mortality responses of both species within 1 year after exposure. Radiation-induced morbidity was assessed by measuring changes in body weights, hematologic parameters, and pulmonary-function parameters. Gamma radiation caused transient morbidity, reflected by immediately depressed blood cell concentrations and by long-term loss of body weight and diminished pulmonary function in animals of both species that survived the acute gamma radiation syndrome. Inhaled plutonium caused a loss of body weight and diminished pulmonary function in both species, but its only effect on blood cell concentrations was lymphocytopenia in dogs. Combined gamma irradiation and plutonium lung burdens were synergistic, in that animals receiving both radiation insults had higher morbidity and mortality rates than would be predicted based on the effect of either kind of radiation alone. Plutonium lung burdens enhanced the effect of gamma radiation in rats within the first 30 days of exposure, and gamma radiation enhanced the long-term effect of plutonium lung burdens in both species. Rats were less sensitive to both kinds of radiation, whether administered alone or in combination. 71 refs., 105 figs., 48 tabs.

  12. Inhaled 239PuO2 and/or total-body gamma radiation: Early mortality and morbidity in rats and dogs

    International Nuclear Information System (INIS)

    Filipy, R.E.; Decker, J.R.; Lai, Y.L.

    1988-08-01

    Rats and beagle dogs were given doses of 60 Co gamma radiation and/or body burdens of 239 PuO 2 within lethal ranges in an experiment to determine and compare morbidity and mortality responses of both species within 1 year after exposure. Radiation-induced morbidity was assessed by measuring changes in body weights, hematologic parameters, and pulmonary-function parameters. Gamma radiation caused transient morbidity, reflected by immediately depressed blood cell concentrations and by long-term loss of body weight and diminished pulmonary function in animals of both species that survived the acute gamma radiation syndrome. Inhaled plutonium caused a loss of body weight and diminished pulmonary function in both species, but its only effect on blood cell concentrations was lymphocytopenia in dogs. Combined gamma irradiation and plutonium lung burdens were synergistic, in that animals receiving both radiation insults had higher morbidity and mortality rates than would be predicted based on the effect of either kind of radiation alone. Plutonium lung burdens enhanced the effect of gamma radiation in rats within the first 30 days of exposure, and gamma radiation enhanced the long-term effect of plutonium lung burdens in both species. Rats were less sensitive to both kinds of radiation, whether administered alone or in combination. 71 refs., 105 figs., 48 tabs

  13. Estimation of covariances of 16O, 23Na, Fe, 235U, 238U and 239Pu neutron nuclear data in JENDL-3.2

    International Nuclear Information System (INIS)

    Shibata, Keiichi; Nakajima, Yutaka; Kawano, Toshihiko; Oh, Soo-Youl; Matsunobu, Hiroyuki; Murata, Toru.

    1997-10-01

    Covariances of nuclear data have been estimated for 6 nuclides contained in JENDL-3.2. The nuclides considered are 16 O, 23 Na, Fe, 235 U, 238 U, and 239 Pu, which are regarded as important for the nuclear design study of fast reactors. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, and the first order Legendre-polynomial coefficient for the angular distribution of elastically scattered neutrons. As for 235 U, covariances were obtained also for the average number of neutrons emitted in fission. The covariances were estimated by using the same methodology that had been used in the JENDL-3.2 evaluation in order to keep a consistency between mean values and their covariances. The least-squares fitting code GMA was used in estimating covariances for reactions of which JENDL-3.2 cross sections had been evaluated by taking account of measurements. In nuclear model calculations, the covariances were calculated by the KALMAN system. The covariance data obtained were compiled in the ENDF-6 format, and will be put into the JENDL-3.2 Covariance File which is one of JENDL special purpose files. (author). 193 refs

  14. Microdistribution and Long-Term Retention of 239Pu (NO3)4 in the Respiratory Tracts of an Acutely Exposed Plutonium Worker and Experimental Beagle Dogs

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, Christopher E.; Wilson, Dulaney A.; Brooks, Antone L.; McCord, Stacey; Dagle, Gerald E.; James, Anthony C.; Tolmachev, Sergei Y.; Thrall, Brian D.; Morgan, William F.

    2012-11-01

    The long-term retention of inhaled soluble forms of plutonium raises concerns as to the potential health effects in persons working in nuclear energy or the nuclear weapons program. The distributions of long-term retained inhaled plutonium-nitrate [239Pu (NO3)4] deposited in the lungs of an accidentally exposed nuclear worker (Human Case 0269) and in the lungs of experimentally exposed beagle dogs with varying initial lung depositions were determined via autoradiographs of selected histological lung, lymph node, trachea, and nasal turbinate tissue sections. These studies showed that both the human and dogs had a non-uniform distribution of plutonium throughout the lung tissue. Fibrotic scar tissue effectively encapsulated a portion of the plutonium and prevented its clearance from the body or translocation to other tissues and diminished dose to organ parenchyma. Alpha radiation activity from deposited plutonium in Human Case 0269 was observed primarily along the sub-pleural regions while no alpha activity was seen in the tracheobronchial lymph nodes of this individual. However, relatively high activity levels in the tracheobronchial lymph nodes of the beagles indicated the lymphatic system was effective in clearing deposited plutonium from the lung tissues. In both the human case and beagle dogs, the appearance of retained plutonium within the respiratory tract was inconsistent with current biokinetic models of clearance for soluble forms of plutonium. Bound plutonium can have a marked effect on the dose to the lungs and subsequent radiation exposure has the potential increase in cancer risk.

  15. Alpha and conversion electron spectroscopy of {sup 238,239}Pu and {sup 241}Am and alpha-conversion electron coincidence measurements

    Energy Technology Data Exchange (ETDEWEB)

    Dion, Michael P., E-mail: michael.dion@pnnl.gov; Miller, Brian W.; Warren, Glen A.

    2016-09-11

    A technique to determine the isotopic constituents of a mixed actinide sample has been proposed by a coincident alpha-conversion electron measurement. This presents a unique signature to allow the unfolding of isotopes that possess overlapping alpha particle energy and reduce backgrounds of an unseparated sample. The work presented here are results of conversion electron spectroscopy of {sup 241}Am, {sup 238}Pu and {sup 239}Pu using a dual-stage peltier-cooled 25 mm{sup 2} silicon drift detector and alpha spectroscopy with a passivated ion implanted planar silicon detector. The conversion electron spectra were evaluated from 20–55 keV based on fits to the dominant conversion electron emissions, which allowed the relative conversion electron emission intensities to be determined. These measurements provide crucial singles spectral information and calibration to aid in the coincident measurement approach. Furthermore, an alpha-conversion electron spectrometer was assembled using the silicon based detectors described and results of a coincident spectrum analysis is reported for {sup 241}Am.

  16. Transmutation of $^{239}$Pu and Other Nuclides Using Spallation Neutrons Produced by Relativistic Protons Reacting with Massive U- and Pb-Targets

    CERN Document Server

    Adam, J; Bamblevski, V P; Barabanov, M Yu; Bradnova, V; Chaloun, P; Hella, K M; Kalinnikov, V G; Krivopustov, M I; Kulakov, B A; Perelygin, V P; Pronskikh, V S; Pavliouk, A V; Solnyshkin, A A; Sosnin, A N; Stegailov, V I; Tsoupko-Sitnikov, V M; Zaverioukha, O S; Adloff, J C; Debeauvais, M; Brandt, R; Langrock, E J; Vater, P; Van, J S; Westmeier, W; Dwivedi, K K; Guo Shi Lun; Li Li Qiang; Hashemi-Nezhad, S R; Kievets, M K; Lomonosova, E M; Zhuk, I V; Modolo, G; Odoj, R; Zamani-Valassiadou, M

    2001-01-01

    Experimental studies on the transmutation of some long-lived radioactive waste nuclei, such as ^{129}I, ^{237}Np, and ^{239}Pu, as well as on natural uranium and lanthanum (all of them used as sensors) were carried out at the Synchrophasotron of the Laboratory for High Energies (JINR, Dubna). Spallation neutrons were produced by relativistic protons with energies in the range of 0.5 GeV\\le E(p)\\le 1.5 GeV interacting with 20 cm long uranium or lead target stacks. The targets were surrounded by 6 cm paraffin moderators. The radioactive sensors mentioned above were positioned on the outside surface of the moderator and contained typically approximately 0.5 up to 1 gram of long-lived isotopes. The highly radioactive targets were produced perfectly well-sealed in aluminum containers by the Institute of Physics and Power Engineering, Obninsk, Russia. From the experimentally observed transmutation rates one can easily extrapolate, that in a subcritical nuclear power assembly (or "energy amplifier") using a 10 mA pr...

  17. Study of High-Resolution Spectroscopy of Plutonium. Part I. Contribution to the Classification of the Arc Spectrum. Part II. Determination of the Magnetic Moment of 239Pu

    International Nuclear Information System (INIS)

    Gerstenkorn, S.

    1962-01-01

    The study of the hyperfine structure and isotope shift enabled the positions of the first five levels of the multiplet 7 F 0-6 belonging to the fundamental configuration 5f 6 7s 2 to be determined. The classification of the arc spectrum begun in this way led to 25 odd levels, the number of classified lines (70) representing about 30 p. 100 of the light emitted by this hollow cathode in the visible. In addition, the isotope shifts of many lines and the data given by the King furnace show that the first levels of the configuration 5f 5 6d7s 2 are also low less than 8000 cm -1 above the fundamental level 7 F 0 . The proximity of the configuration f 6 s 2 and f 5 ds 2 shows that the bonding energies of the 5f and 6d electrons are of the same order of magnitude and this fact must be responsible for the multiple valences belonging to plutonium. From the hyperfine structure of spark lines (Pu II) the interval factor a 7 for the electron was deduced giving for the calculated nuclear moment of 239 Pu a value of +0.21 ±0.06 μ N . The position of the hyperfine components show that the nuclear moment is positive, although the theoretical value given by B. R. Mottelson and S. Nillson is negative and equal to -0.1 μ N . (author) [fr

  18. Age-related effects on the disposition and dosimetry of inhaled 239Pu or 144Ce in immature or aged beagle dogs

    International Nuclear Information System (INIS)

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

    1987-01-01

    Immature (90 days of age), young adult (18 months of age), and aged (8-10.5 years of age) male and female beagle dogs received a single brief pernasal inhalation exposure to an aerosol of 144 Ce in an insoluble fused aluminosilicate matrix or 239 PuO 2 . These isotopes were selected to represent low- and high-LET emitters, respectively. No age-related differences in the retention of Pu in the lungs of dogs have been observed, nor have there been any detectable differences in the uptake and retention of Pu in the tracheobronchial lymph nodes. Age-related effects have been seen in the uptake of Pu in the skeleton, with the amount of Pu being greatest in the skeleton of immature dogs. For the dogs exposed to the 144 Ce aerosol, there was a statistically significant difference in the retention of 144 Ce in the lungs of immature dogs compared to young adults. Increased uptake of 144 Ce in the immature dog skeleton was also noted. 14 refs.; 4 figs

  19. Energy dependence of relative abundances and periods of delayed neutron separate groups from neutron induced fission of 239Pu in the virgin neutron energy range 0.37-4.97 MeV

    International Nuclear Information System (INIS)

    Piksajkin, V.M.; Kazakov, L.E.; Isaev, S.T.; Korolev, G.G.; Roshchenko, V.A.; Tertychnyj, R.G.

    2002-01-01

    Relative yield and group period of delayed neutrons induced by the 239 Pu fission in the 0.37-4.97 MeV range were measured. Comparative analysis of experimental data was conducted in terms of middle period of half-life of delayed neutron nuclei-precursors. Character and scale of changing values of delayed neutron group parameters as changing excitation energy of fission compound-nucleus have been demonstrated for the first time. Considerable energy dependence of group parameters under the neutron induced 239 Pu fission that was expressed by the decreasing middle period of half-life of nuclei-precursors by 10 % in the 2.85 eV - 5 MeV range of virgin neutrons was detected [ru

  20. Study of the variation with the energy of the fission cross-sections of {sup 233}U, {sup 235}U, {sup 239}Pu for the fast neutrons; Etude de la variation avec l'energie des sections efficaces de fission de {sup 233}U, {sup 235}U, {sup 239}Pu pour les neutrons rapides

    Energy Technology Data Exchange (ETDEWEB)

    Szteinsznaider, D; Naggiar, V; Netter, F [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1955-07-01

    This measurements have been done while taking the value of the fission cross-sections of {sup 238}U as reference. The neutrons are produced by the reaction {sup 7}Li(p,n) in the Van de Graaff generator of Saclay. The explored domain spreads from some tenths to 2000 keV. We find: for {sup 239}Pu: {sigma}{sub f} = 2,04 {+-} 0,12 barns, cross-section constant between 150 and 2000 keV, for {sup 235}U: {sigma}{sub f} = 1,15 {+-} 0,15 barns, cross-section constant between 700 and 1000 keV, for {sup 233}U: {sigma}{sub f} = 1,92 {+-} 0,25 barns, for neutrons of 850 keV. (authors) [French] Ces mesures ont ete effectuees en prenant la valeur de la section efficace de fission de {sup 238}U comme reference. Les neutrons sont produits par la reaction {sup 7}Li(p,n) au generateur Van de Graaff de Saclay. Le domaine explore s'etend de quelques dizaines de kev a 2000 kev. Nous trouvons: pour {sup 239}Pu: {sigma}{sub f} = 2,04 {+-} 0,12 barns, section efficace constante entre 150 et 2000 kev. pour {sup 235}U: {sigma}{sub f} = 1,15 {+-} 0,15 barns, section efficace constante entre 700 et 1000 kev. pour {sup 233}U: {sigma}{sub f} = 1,92 {+-} 0,25 barns, pour des neutrons de 850 kev. (auteurs)

  1. Separation of the rare earths by high pressure liquid chromatography and the fission yield on sup(148m)Pm and sup(148g)Pm using thermal neutron induced fission of 233U and 239Pu

    International Nuclear Information System (INIS)

    Zwicky, H.U.

    1979-03-01

    This report is in two parts: in the first part, the method of high pressure liquid chromatography is described with particular reference to rare earth nuclei produced in nuclear reactions; in the second part, the results of a study of the fission yield of sup(148m)Pm and sup(148g)Pm from the thermal fission of 233 U and 239 Pu are presented. (G.T.H.)

  2. Theoretical analyses of (n,xn) reactions on sup 235 U, sup 238 U, sup 237 Np, and sup 239 Pu for ENDF/B-VI

    Energy Technology Data Exchange (ETDEWEB)

    Young, P.G.; Arthur, E.D.

    1991-01-01

    Theoretical analyses were performed of neutron-induced reactions on {sup 235}U, {sup 238}U, {sup 237}Np, and {sup 239}Pu between 0.01 and 20 MeV in order to calculate neutron emission cross sections and spectra for ENDF/B-VI evaluations. Coupled-channel optical model potentials were obtained for each target nucleus by fitting total, elastic, and inelastic scattering cross section data, as well as low-energy average resonance data. The resulting deformed optical model potentials were used to calculate direct (n,n{prime}) cross sections and transmission coefficients for use in Hauser-Feshbach statistical theory analyses. A fission model with multiple barrier representation, width fluctuation corrections, and preequilibrium corrections were included in the analyses. Direct cross sections for higher-lying vibrational states were calculated using DWBA theory, normalized using B(E{ell}) values determined from (d,d{prime}) and Coulomb excitation data, where available, and from systematics otherwise. Initial fission barrier parameters and transition state density enhancements appropriate to the compound systems involved were obtained from previous analyses, especially fits to charged-particle fission probability data. The parameters for the fission model were adjusted for each target system to obtain optimum agreement with direct (n,f) cross section measurements, taking account of the various multichance fission channels, that is, the different compound systems involved. The results from these analyses were used to calculate most of the neutron (n,n), (n,n{prime}), and (n,xn) cross section data in the ENDF/B/VI evaluations for the above nuclei, and all of the energy-angle correlated spectra. The deformed optical model and fission model parameterizations are described. Comparisons are given between the results of these analyses and the previous ENDF/B-V evaluations as well as with the available experimental data. 14 refs., 3 figs., 1 tab.

  3. Evaluation of the {sup 239}Pu prompt fission neutron spectrum induced by neutrons of 500 keV and associated covariances

    Energy Technology Data Exchange (ETDEWEB)

    Neudecker, D., E-mail: dneudecker@lanl.gov [Theoretical Division, Los Alamos National Laboratory, P.O. Box 1663, MS-B283, NM 87545 (United States); Talou, P., E-mail: talou@lanl.gov [Theoretical Division, Los Alamos National Laboratory, P.O. Box 1663, MS-B283, NM 87545 (United States); Kawano, T., E-mail: kawano@lanl.gov [Theoretical Division, Los Alamos National Laboratory, P.O. Box 1663, MS-B283, NM 87545 (United States); Smith, D.L., E-mail: donaldlarnedsmith@gmail.com [Nuclear Engineering Division, Argonne National Laboratory, 1710 Avenida del Mundo #1506, Coronado, CA 92118 (United States); Capote, R., E-mail: r.capotenoy@iaea.org [Nuclear Data Section, International Atomic Energy Agency Vienna, Vienna International Centre, P.O. Box 100, A-1400 Vienna (Austria); Rising, M.E., E-mail: mrising@lanl.gov [X-Division, Los Alamos National Laboratory, P.O. Box 1663, MS-F663, NM 87545 (United States); Kahler, A.C., E-mail: akahler@lanl.gov [Theoretical Division, Los Alamos National Laboratory, P.O. Box 1663, MS-B283, NM 87545 (United States)

    2015-08-11

    We present evaluations of the prompt fission neutron spectrum (PFNS) of {sup 239}Pu induced by 500 keV neutrons, and associated covariances. In a previous evaluation by Talou et al. (2010), surprisingly low evaluated uncertainties were obtained, partly due to simplifying assumptions in the quantification of uncertainties from experiment and model. Therefore, special emphasis is placed here on a thorough uncertainty quantification of experimental data and of the Los Alamos model predicted values entering the evaluation. In addition, the Los Alamos model was extended and an evaluation technique was employed that takes into account the qualitative differences between normalized model predicted values and experimental shape data. These improvements lead to changes in the evaluated PFNS and overall larger evaluated uncertainties than in the previous work. However, these evaluated uncertainties are still smaller than those obtained in a statistical analysis using experimental information only, due to strong model correlations. Hence, suggestions to estimate model defect uncertainties are presented, which lead to more reasonable evaluated uncertainties. The calculated k{sub eff} of selected criticality benchmarks obtained with these new evaluations agree with each other within their uncertainties despite the different approaches to estimate model defect uncertainties. The k{sub eff} one standard deviations overlap with some of those obtained using ENDF/B-VII.1, albeit their mean values are further away from unity. Spectral indexes for the Jezebel critical assembly calculated with the newly evaluated PFNS agree with the experimental data for selected (n,γ) and (n,f) reactions, and show improvements for high-energy threshold (n,2n) reactions compared to ENDF/B-VII.1.

  4. Procedures for the use of Lexan and Makrofol SSNTDs in the detection of environmental concentrations of 235U and 239Pu

    International Nuclear Information System (INIS)

    Henderson, C.L.

    1993-03-01

    Solid State Nuclear Track Detectors are used to study a variety of atomic particles. Polycarbonate SSNTD is used to study environmental concentrations of 235 U and 239 Pu in human urine and feces through fission track analysis. The samples of interest are deposited upon a Lexan slide, covered with a piece of Makrofol and exposed to a neutron fluence of 1.1 X 10 17 . The fissile isotopes in the sample fission and the resulting fission fragments pass through either the surface of the Lexan or the surface of the Makrofol. The positive Coulombic attraction of the ionized fission fragments causes the electrons of the polycarbonate lattice to move towards the path of these particles, resulting in the breakage of chemical bonds in the lattice. The detector is then chemically etched in 6.5 N KOH that preferentially dissolves the damaged polycarbonate left in the path of the fission fragment. The chemically etched fission tracks are permanent records of the path of the fission fragment. The etched fission tracks in Lexan are optically counted using a microscope and the fission tracks in Makrofol are counted using a Spark Chamber. The amount of fissile material in the original sample can be calculated from the number of fission tracks. This paper presents further details of procedures for etching fission tracks in Lexan and Makrofol and for operating a Spark Chamber to count etched fission tracks in Makrofol. The physics of fission track formation in dielectric detectors is also discussed, as well as the physics of the Spark Chamber

  5. Energy dependence of fission product yields from 235U, 238U, and 239Pu with monoenergetic neutrons between thermal and 14.8 MeV

    Science.gov (United States)

    Gooden, Matthew; Arnold, Charles; Bhike, Megha; Bredeweg, Todd; Fowler, Malcolm; Krishichayan; Tonchev, Anton; Tornow, Werner; Stoyer, Mark; Vieira, David; Wilhelmy, Jerry

    2017-09-01

    Under a joint collaboration between TUNL-LANL-LLNL, a set of absolute fission product yield measurements has been performed. The energy dependence of a number of cumulative fission product yields (FPY) have been measured using quasi-monoenergetic neutron beams for three actinide targets, 235U, 238U and 239Pu, between 0.5 and 14.8 MeV. The FPYs were measured by a combination of fission counting using specially designed dual-fission chambers and γ-ray counting. Each dual-fission chamber is a back-to-back ionization chamber encasing an activation target in the center with thin deposits of the same target isotope in each chamber. This method allows for the direct measurement of the total number of fissions in the activation target with no reference to the fission cross-section, thus reducing uncertainties. γ-ray counting of the activation target was performed on well-shielded HPGe detectors over a period of two months post irradiation to properly identify fission products. Reported are absolute cumulative fission product yields for incident neutron energies of 0.5, 1.37, 2.4, 3.6, 4.6, 5.5, 7.5, 8.9 and 14.8 MeV. Preliminary results from thermal irradiations at the MIT research reactor will also be presented and compared to present data and evaluations. This work was performed under the auspices of the U.S. Department of Energy by Los Alamos National Security, LLC under contract DE-AC52-06NA25396, Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344 and by Duke University and Triangle Universities Nuclear Laboratory through NNSA Stewardship Science Academic Alliance grant No. DE-FG52-09NA29465, DE-FG52-09NA29448 and Office of Nuclear Physics Grant No. DE-FG02-97ER41033.

  6. Energy dependence of fission product yields from 235U, 238U, and 239Pu with monoenergetic neutrons between thermal and 14.8 MeV

    Directory of Open Access Journals (Sweden)

    Gooden Matthew

    2017-01-01

    Full Text Available Under a joint collaboration between TUNL-LANL-LLNL, a set of absolute fission product yield measurements has been performed. The energy dependence of a number of cumulative fission product yields (FPY have been measured using quasi-monoenergetic neutron beams for three actinide targets, 235U, 238U and 239Pu, between 0.5 and 14.8 MeV. The FPYs were measured by a combination of fission counting using specially designed dual-fission chambers and γ-ray counting. Each dual-fission chamber is a back-to-back ionization chamber encasing an activation target in the center with thin deposits of the same target isotope in each chamber. This method allows for the direct measurement of the total number of fissions in the activation target with no reference to the fission cross-section, thus reducing uncertainties. γ-ray counting of the activation target was performed on well-shielded HPGe detectors over a period of two months post irradiation to properly identify fission products. Reported are absolute cumulative fission product yields for incident neutron energies of 0.5, 1.37, 2.4, 3.6, 4.6, 5.5, 7.5, 8.9 and 14.8 MeV. Preliminary results from thermal irradiations at the MIT research reactor will also be presented and compared to present data and evaluations. This work was performed under the auspices of the U.S. Department of Energy by Los Alamos National Security, LLC under contract DE-AC52-06NA25396, Lawrence Livermore National Laboratory under contract DE-AC52-07NA27344 and by Duke University and Triangle Universities Nuclear Laboratory through NNSA Stewardship Science Academic Alliance grant No. DE-FG52-09NA29465, DE-FG52-09NA29448 and Office of Nuclear Physics Grant No. DE-FG02-97ER41033.

  7. Vertical distribution of 239+240Pu-concentration and 240Pu/239Pu isotope ratio in sediment cores. Implications for the sources of plutonium in the Japan Sea

    International Nuclear Information System (INIS)

    Yamada, Masatoshi; Jian, Zheng

    2005-01-01

    The main sources in the environmental plutonium is due to nuclear explosions held during 1945 - 1980. The global fallout of plutonium is estimated to amount to 10.9 PBq, of which 6.6 PBq entering into the ocean. The Japan Sea is reported to be concentrated in plutonium in excess according to previous measurements. The present report aims to clarify the origin and transport path of plutonium in Japan Sea by measuring 240 Pu/ 239 Pu ratio in sedimenta cores with ICP-MS (Inductively Coupled Plasma Mass Spectrometry) which depends on the types of the nuclear reactor, nuclear fuels, reacting time, or the types of nuclear weapons concerned. As an example the 240 Pu/ 239 Pu ratio from the nuclear explosions in early 1960's is known to be 0.18, while that of 0.34-0.36 Bikini experiments in the Marshall Islands in early 1950's. After a detailed examination, the present authors propose that the plutonium from the explosion sites around the Marshall Islands was carried with an oceanic current to be deposited in the bed of the East-China Sea, from which a part of the plutonium was transported with the Black Stream to enter Japan Sea. (S. Ohno)

  8. Prompt fission neutron spectra from fission induced by 1 to 8 MeV neutrons on 235U and 239Pu using the double time-of-flight technique

    International Nuclear Information System (INIS)

    Noda, S.; Haight, R. C.; Nelson, R. O.; Devlin, M.; O'Donnell, J. M.; Chatillon, A.; Granier, T.; Belier, G.; Taieb, J.; Kawano, T.; Talou, P.

    2011-01-01

    Prompt fission neutron spectra from 235 U and 239 Pu were measured for incident neutron energies from 1 to 200 MeV at the Weapons Neutron Research facility (WNR) of the Los Alamos Neutron Science Center, and the experimental data were analyzed with the Los Alamos model for the incident neutron energies of 1-8 MeV. A CEA multiple-foil fission chamber containing deposits of 100 mg 235 U and 90 mg 239 Pu detected fission events. Outgoing neutrons were detected by the Fast Neutron-Induced γ-Ray Observer array of 20 liquid organic scintillators. A double time-of-flight technique was used to deduce the neutron incident energies from the spallation target and the outgoing energies from the fission chamber. These data were used for testing the Los Alamos model, and the total kinetic energy parameters were optimized to obtain a best fit to the data. The prompt fission neutron spectra were also compared with the Evaluated Nuclear Data File (ENDF/B-VII.0). We calculate average energies from both experimental and calculated fission neutron spectra.

  9. 137Cs, 239+24Pu and 24Pu/239Pu atom ratios in the surface waters of the western North Pacific Ocean, eastern Indian Ocean and their adjacent seas

    International Nuclear Information System (INIS)

    Yamada, Masatoshi; Zheng Jian; Wang Zhongliang

    2006-01-01

    Surface seawater samples were collected along the track of the R/V Hakuho-Maru cruise (KH-96-5) from Tokyo to the Southern Ocean. The 137 Cs activities were determined for the surface waters in the western North Pacific Ocean, the Sulu and Indonesian Seas, the eastern Indian Ocean, the Bay of Bengal, the Andaman Sea, and the South China Sea. The 137 Cs activities showed a wide variation with values ranging from 1.1 Bq m -3 in the Antarctic Circumpolar Region of the Southern Ocean to 3 Bq m -3 in the western North Pacific Ocean and the South China Sea. The latitudinal distributions of 137 Cs activity were not reflective of that of the integrated deposition density of atmospheric global fallout. The removal rates of 137 Cs from the surface waters were roughly estimated from the two data sets of Miyake et al. [Miyake Y, Saruhashi K, Sugimura Y, Kanazawa T, Hirose K. Contents of 137 Cs, plutonium and americium isotopes in the Southern Ocean waters. Pap Meteorol Geophys 1988;39:95-113] and this study to be 0.016 yr -1 in the Sulu and Indonesian Seas, 0.033 yr -1 in the Bay of Bengal and Andaman Sea, and 0.029 yr -1 in the South China Sea. These values were much lower than that in the coastal surface water of the western Northwest Pacific Ocean. This was likely due to less horizontal and vertical mixing of water masses and less scavenging. 239+24 Pu activities and 24 Pu/ 239 Pu atom ratios were also determined for the surface waters in the western North Pacific Ocean, the Sulu and Indonesian Seas and the South China Sea. The 24 Pu / 239 Pu atom ratios ranged from 0.199 ± 0.026 to 0.248 ± 0.027 on average, and were significantly higher than the global stratospheric fallout ratio of 0.18. The contributions of the North Pacific Proving Grounds close-in fallout Pu were estimated to be 20% for the western North Pacific Ocean, 39% for the Sulu and Indonesian Seas and 42% for the South China Sea by using the two end-member mixing model. The higher 24 Pu / 239 Pu atom ratios

  10. {sup 137}Cs, {sup 239+240}Pu concentrations and the {sup 240}Pu/{sup 239}Pu atom ratio in a sediment core from the sub-aqueous delta of Yangtze River estuary

    Energy Technology Data Exchange (ETDEWEB)

    Pan, S.M., E-mail: span@nju.edu.cn [Key Lab of Ministry of Education of Coast and Island Development, Nanjing University, Nanjing 210093 (China); Tims, S.G. [Department of Nuclear Physics, Research School of Physics and Engineering, Australian National University, Canberra, ACT 0200 (Australia); Liu, X.Y. [Key Lab of Ministry of Education of Coast and Island Development, Nanjing University, Nanjing 210093 (China); Fifield, L.K. [Department of Nuclear Physics, Research School of Physics and Engineering, Australian National University, Canberra, ACT 0200 (Australia)

    2011-10-15

    A sediment core collected from the sub-aqueous delta of the Yangtze River estuary was subjected to analyses of {sup 137}Cs and plutonium (Pu) isotopes. The {sup 137}Cs was measured using {gamma}-spectrometry at the laboratories at the Nanjing University and Pu isotopes were determined with Accelerator Mass Spectrometry (AMS), measurements made at the Australian National University. The results show considerable structure in the depth concentration profiles of the {sup 137}Cs and {sup 239+240}Pu. The shape of the vertical {sup 137}Cs distribution in the sediment core was similar to that of the Pu. The maximum {sup 137}Cs and {sup 239+240}Pu concentrations were 16.21 {+-} 0.95 mBq/g and 0.716 {+-} 0.030 mBq/g, respectively, and appear at same depth. The average {sup 240}Pu/{sup 239}Pu atom ratio was 0.238 {+-} 0.007 in the sediment core, slightly higher than the average global fallout value. The changes in the {sup 240}Pu/{sup 239}Pu atom ratios in the sediment core indicate the presence of at least two different Pu sources, i.e., global fallout and another source, most likely close-in fallout from the Pacific Proving Grounds (PPG) in the Marshall Islands, and suggest the possibility that Pu isotopes are useful as a geochronological tool for coastal sediment studies. The {sup 137}Cs and {sup 239+240}Pu inventories were estimated to be 7100 {+-} 1200 Bq/m{sup 2} and 407 {+-} 27 Bq/m{sup 2}, respectively. Approximately 40% of the {sup 239+240}Pu inventory originated from the PPG close-in fallout and about 50% has derived from land-origin global fallout transported to the estuary by the river. This study confirms that AMS is a useful tool to measure {sup 240}Pu/{sup 239}Pu atom ratio and can provide valuable information on sedimentary processes in the coastal environment.

  11. The fission cross sections of 230Th, 232Th, 233U, 234U, 236U, 238U, 237Np, 239Pu and 242Pu relative 235U at 14.74 MeV neutron energy

    International Nuclear Information System (INIS)

    Meadows, J.W.

    1986-12-01

    The measurement of the fission cross section ratios of nine isotopes relative to 235 U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for 235 U are: 230 Th - 0.290 +- 1.9%; 232 Th - 0.191 +- 1.9%; 233 U - 1.132 +- 0.7%; 234 U - 0.998 +- 1.0%; 236 U - 0.791 +- 1.1%; 238 U - 0.587 +- 1.1%; 237 Np - 1.060 +- 1.4%; 239 Pu - 1.152 +- 1.1%; 242 Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs

  12. Neutron induced fission cross section ratios for /sup 232/Th, /sup 235,238/U, /sup 237/Np, and /sup 239/Pu from 1 to 400 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Lisowski, P.W.; Ullmann, J.L.; Balestrini, S.J.; Carlson, A.D.; Wasson, O.A.; Hill, N.W.

    1988-01-01

    Time-of-flight measurements of neutron induced fission cross section ratios for /sup 232/Th, /sup 235,238/U, /sup 237/Np, and /sup 239/Pu, were performed using the WNR high intensity spallation neutron source located at Los Alamos National Laboratory. A multiple-plate gas ionization chamber located at a 20-m flight path was used to simultaneously measure the fission rate for all samples over the energy range from 1 to 400 MeV. Because the measurements were made with nearly identical neutron fluxes, we were able to cancel many systematic uncertainties present in previous measurements. This allows us to resolve discrepancies among different data sets. In addition, these are the first neutron-induced fission cross section values for most of the nuclei at energies above 30 MeV. 8 refs., 3 figs.

  13. Beta and gamma decay heat measurements between 0.1s--50,000s for neutron fission of 235U, 238U and 239Pu. Final report, June 1, 1992--December 31, 1996

    International Nuclear Information System (INIS)

    Schier, W.A.; Couchell, G.P.

    1996-01-01

    This is a final reporting on the composition of separate beta and gamma decay heat measurements following neutron fission of 235 U and 238 U and 239 Pu and on cumulative and independent yield measurements of fission products of 235 U and 238 U. What made these studies unique was the very short time of 0.1 s after fission that could be achieved by incorporating the helium jet and tape transport system as the technique for transporting fission fragments from the neutron environment of the fission chamber to the low-background environment of the counting area. This capability allowed for the first time decay heat measurements to extend nearly two decades lower on the logarithmic delay time scale, a region where no comprehensive aggregate decay heat measurements had extended to. This short delay time capability also allowed the measurement of individual fission products with half lives as short as 0.2s. The purpose of such studies was to provide tests both at the aggregate level and at the individual nuclide level of the nation's evaluated nuclear data file associated with fission, ENDF/B-VI. The results of these tests are in general quite encouraging indicating this data base generally predicts correctly the aggregate beta and aggregate gamma decay heat as a function of delay time for 235 U, 238 U and 239 Pu. Agreement with the measured individual nuclide cumulative and independent yields for fission products of 235 U and 238 U was also quite good although the present measurements suggest needed improvements in several individual cases

  14. Toxicity of inhaled 239PuO2 in Beagle dogs. A. Monodisperse 0.75 μm AMAD particles. B. Monodisperse 1.5 μm AMAD particles. C. Monodisperse 3.0 μm AMAD particles. V

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Guilmette, R.A.; Hahn, F.F.; Boecker, B.B.; McClellan, R.O.; Mauderly, J.L.; Pickrell, J.A.

    1982-01-01

    Studies on the metabolism, dosimetry and biological effects of inhaled particles of 239 PuO 2 in Beagle dogs are in progress. To obtain information on the relative importance of homogeneity versus nonhomogeneity of radiation doses to the lung, dogs have been exposed to monodisperse aerosols of 239 PuO 2 of 0.75, 1.5 or 3.0 μm activity median aerodynamic diameter (AMAD). The exposures have resulted in graded initial lung burdens ranging from 0.0002 to 2.6 μCi 239 Pu per kilogram body weight. Other dogs were exposed to the aerosol diluent to serve as controls. Ten dogs have died in the study with 0.75 μm AMAD particles, 40 dogs have died in the study with 1.5 μm AMAD particles and 35 dogs have died in the study with 3.0 μm AMAD particles of 239 PuO 2 . Dogs have died with radiation pneumonitis and pulmonary fibrosis and carcinomas of the lung. The remaining dogs have survived up to 2100 days after inhalation exposure and are being observed for the remainder of their life span

  15. Study of High-Resolution Spectroscopy of Plutonium. Part I. Contribution to the Classification of the Arc Spectrum. Part II. Determination of the Magnetic Moment of {sup 239}Pu; Etude du plutonium par spectroscopie a haute resolution: contribution a la classification du spectre d'arc et determination du moment magnetique de {sup 239}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Gerstenkorn, S

    1962-07-01

    The study of the hyperfine structure and isotope shift enabled the positions of the first five levels of the multiplet {sup 7}F{sub 0-6} belonging to the fundamental configuration 5f{sup 6}7s{sup 2} to be determined. The classification of the arc spectrum begun in this way led to 25 odd levels, the number of classified lines (70) representing about 30 p. 100 of the light emitted by this hollow cathode in the visible. In addition, the isotope shifts of many lines and the data given by the King furnace show that the first levels of the configuration 5f{sup 5}6d7s{sup 2} are also low less than 8000 cm{sup -1} above the fundamental level {sup 7}F{sub 0}. The proximity of the configuration f{sup 6}s{sup 2} and f{sup 5}ds{sup 2} shows that the bonding energies of the 5f and 6d electrons are of the same order of magnitude and this fact must be responsible for the multiple valences belonging to plutonium. From the hyperfine structure of spark lines (Pu II) the interval factor a{sub 7} for the electron was deduced giving for the calculated nuclear moment of {sup 239}Pu a value of +0.21 {+-}0.06 {mu}{sub N}. The position of the hyperfine components show that the nuclear moment is positive, although the theoretical value given by B. R. Mottelson and S. Nillson is negative and equal to -0.1 {mu}{sub N}. (author) [French] Partie 1 - L'etude des structures hyperfines et du deplacement isotopique des raies du spectre d'arc du plutonium a permis de determiner la position des cinq premiers niveaux du multiplet {sup 7}F{sub 0-6} correspondant a la configuration fondamentale 5f{sup 6}7s{sup 2}. Des lors, la classification du spectre d'arc du plutonium pouvait etre amorcee: 25 niveaux impairs ont ete mis en evidence et le nombre de raies classees (70) represente environ 30 p. 100 de l'intensite totale du spectre d'arc emis par une cathode creuse dans le visible. D'autre part, le deplacement isotopique de certaines raies, joint aux renseignements donnes par le spectre emis par le four

  16. Energy dependence of relative abundances and periods of separate groups of delayed neutrons at neutron induced fission of 239Pu in a range of neutrons energies 0.37 - 5 MeV

    International Nuclear Information System (INIS)

    Roschenko, V.A.; Piksaikin, V.M.; Kazakov, L.E.; Isaev, S.G.; Korolev, G.G.; Tarasko, M.Z.; Tertychnyi, R.G.

    2001-01-01

    The fundamental role of delayed neutrons in behavior, control and safety of reactors is well known today. Delayed neutron data are of great interest not only for reactor physics but also for nuclear fission physics and astrophysics. The purpose of the present work was the measurement of energy dependence of delayed neutrons (DN) group parameters at fission of nuclei 239 Pu in a range of energies of primary neutrons from 0.37 up to 5 MeV. The measurements were executed on installation designed on the basis of the electrostatic accelerator of KG - 2.5 SSC RF IPPE. The data are obtained in 6-group representation. It is shown, that there is a significant energy dependence of DN group parameters in a range of primary neutrons energies from thermal meanings up to 5 MeV, which is expressed in reduction of the average half-life of nuclei of the DN precursors on 10 %. The data, received in the present work, can be used at creation of a set of group constants for reactors with an intermediate spectrum of neutrons. (authors)

  17. Estimation of covariances of {sup 16}O, {sup 23}Na, Fe, {sup 235}U, {sup 238}U and {sup 239}Pu neutron nuclear data in JENDL-3.2

    Energy Technology Data Exchange (ETDEWEB)

    Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Nakajima, Yutaka; Kawano, Toshihiko; Oh, Soo-Youl; Matsunobu, Hiroyuki; Murata, Toru

    1997-10-01

    Covariances of nuclear data have been estimated for 6 nuclides contained in JENDL-3.2. The nuclides considered are {sup 16}O, {sup 23}Na, Fe, {sup 235}U, {sup 238}U, and {sup 239}Pu, which are regarded as important for the nuclear design study of fast reactors. The physical quantities for which covariances are deduced are cross sections, resolved and unresolved resonance parameters, and the first order Legendre-polynomial coefficient for the angular distribution of elastically scattered neutrons. As for {sup 235}U, covariances were obtained also for the average number of neutrons emitted in fission. The covariances were estimated by using the same methodology that had been used in the JENDL-3.2 evaluation in order to keep a consistency between mean values and their covariances. The least-squares fitting code GMA was used in estimating covariances for reactions of which JENDL-3.2 cross sections had been evaluated by taking account of measurements. In nuclear model calculations, the covariances were calculated by the KALMAN system. The covariance data obtained were compiled in the ENDF-6 format, and will be put into the JENDL-3.2 Covariance File which is one of JENDL special purpose files. (author). 193 refs.

  18. About the first experiment on investigation of 129I, 237Np, 238Pu and 239Pu transmutation at the nuclotron 2.52 GeV deuteron beam in neutron field generated in U/Pb-assembly 'Energy plus transmutation'

    International Nuclear Information System (INIS)

    Krivopustov, M.I.; Pavliouk, A.V.; Malakhov, A.I.

    2008-01-01

    Preliminary results of the first experiment with energy 2.52 GeV at the electronuclear setup which consists of Pb-target (diameter 8.4 cm, length 45.6 cm) and nat U-blanket (206.4 kg), transmutation samples of 129 I, 237 Np, 238 Pu and 239 Pu (radioecological aspect) are described. Hermetically sealed samples in notable amounts are gathered in atomic reactors and setups of industries which use nuclear materials and nuclear technologies were irradiated in the field of neutrons produced in the Pb-target and propagated in the nat U-blanket. Estimates of transmutations were obtained as a result of measurements of gamma activities of the samples. The information about the space and energy distribution of neutrons in the volume of the lead target and the uranium blanket was obtained with the help of sets of activation threshold detectors (Al, Co, Y, I, Au, Bi and others), solid-state nuclear track detectors, 3 He neutron detectors and nuclear emulsion. Comparison of the experimental data with the results of simulation with the MCNPX program was performed

  19. Energy Dependence of Fission Product Yields from 235U, 238U and 239Pu for Incident Neutron Energies Between 0.5 and 14.8 MeV

    Science.gov (United States)

    Gooden, Matthew; Bredeweg, Todd; Fowler, Malcolm; Vieira, David; Wilhelmy, Jerry; Tonchev, Anton; Stoyer, Mark; Bhike, Megha; Finch, Sean; Krishichayan, Fnu; Tornow, Werner

    2017-09-01

    The energy dependence of a number of cumulative fission product yields (FPY) have been measured using quasi- monoenergetic neutron beams for three actinide targets, 235U, 238U and 239Pu, between 0.5 and 14.8 MeV. The FPYs were measured by a combi- nation of fission counting using specially designed dual-fission chambers and -ray counting. Each dual-fission chamber is a back-to-back ioniza- tion chamber encasing an activation target in the center with thin de- posits of the same target isotope in each chamber. This method allows for the direct measurement of the total number of fissions in the activa- tion target with no reference to the fission cross-section, thus reducing uncertainties. γ-ray counting of the activation target was performed on well-shielded HPGe detectors over a period of 2 months post irradiation to properly identify fission products. Reported are absolute cumulative fission product yields for incident neutron energies of 0.5, 1.37, 2.4, 3.6, 4.6 and 14.8 MeV. New data in the second chance fission region of 5.5 - 9 MeV are included. Work performed for the U.S. Department of Energy by Los Alamos National Security, LLC under Contract DE-AC52-06NA25396.

  20. Toxicity of inhaled 239PuO2 in Beagle dogs: A. Monodisperse 0.75-μm AMAD particles. B. Monodisperse 1.5-μm AMAD particles. C. Monodisperse 3.0--μm AMAD particles. XI

    International Nuclear Information System (INIS)

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

    1988-01-01

    Beagle dogs were exposed to monodisperse aerosols of 239 PuO 2 of 0.75, 1.5, or 30 μm activity median aerodynamic diameter (AMAD) to obtain information on the relative importance of homogeneity of alpha irradiation doses to the lung in producing biological effects. The dogs' initial pulmonary burdens (IPB) ranged from 0.0002-2.0 μCi (0.0074 to 74 kBq) 239 Pu/kg of body mass. Thirty-six dogs were exposed to the aerosol diluent as controls. Forty-two of 48 dogs exposed to 0.75 μm AMAD particles have died; 67 of 96 have died in the study involving 1.5 μm AMAD particles; and 62 of 72 have died in the study involving the 3.0 μm AMAD particles. Seven of 36 control dogs have died. Most dogs exposed to 239 Pu that have failed to survive have died with radiation pneumonitis and fibrosis and/or lung cancer. Surviving dogs have lived up to 4300 days after exposure. The data obtained to date indicate that the degree of uniformity of dose to the lung does not significantly modify the risk of lung cancer. (author)

  1. Measurements of the prompt neutron spectra in 233U, 235U, 239Pu thermal neutron fission in the energy range of 0.01-5 MeV and in 252Cf spontaneous fission in the energy range of 0.01-10 MeV

    International Nuclear Information System (INIS)

    Starostov, B.I.; Semenov, A.F.; Nefedov, V.N.

    1978-01-01

    The measurement results on the prompt neutron spectra in 233 U, 235 U, 239 Pu thermal neutron fission in the energy range of 0.01-5 MeV and in 252 Cf spontaneous fission in the energy range of 0.01-10 MeV are presented. The time-of-flight method was used. The exceeding of the spectra over the Maxwell distributions is observed at E 252 Cf neutron fission spectra. The spectra analysis was performed after normalization of the spectra and corresponding Maxwell distributions for one and the same area. In the range of 0.05-0.22 MeV the yield of 235 U + nsub(t) fission neutrons is approximately 8 and approximately 15 % greater than the yield of 252 Cf and 239 Pu + nsub(t) fission neutrons, respectively. In the range of 0.3-1.2 MeV the yield of 235 U + nsub(t) fission neutrons is 8 % greater than the fission neutron yield in case of 239 Pu + nsub(t) fission. The 235 U + nsub(t) and 233 U + nsub(t) fission neutron spectra do not differ from one another in the 0.05-0.6 MeV range

  2. Modelling of the radioactive daughter elements in soil to assess radiation impact due to contaminated irrigation water by parents of 231Pa, 226Ra, 238U, 237Np and 239Pu

    International Nuclear Information System (INIS)

    Bela Kanyar; Katalin Eged; Tunde Katona; Gerhard Proehl; Ulla Bergstroem; Bengt Hallberg; Shelly Mobbs; Geert Olyslaegers; Theo Zeevaert; Palome Pinedo; Inmaculade Simon

    2004-01-01

    Radioactive wastes may contain both parent and daughter radionuclides. In some cases the transfer parameters of the daughter radio-elements differ significantly from that of the parent ones and therefore the dose contributions in the different pathways might be important to assess separately. The present work has compared 5 different site specific models by a scenario, using contaminated water for drinking and irrigation. Altogether 5 radionuclides from the investigated 10 ones contained radioactive daughter elements. In general, for long term studies in biosphere the steady-state formulations of processes are adequate to assess the contamination, except the infiltration into the deeper soil and sediment layers. According to the results of the modelling and computer simulations, the following daughters are to be assessed separately from their parents with respect to the radiation impact: for parent 231 Pa the daughter 227 Ac, for parent 226 Ra the daughters 222 Rn, 210 Pb and 210 Po and for parent 237 Np the daughter 233 Pa. The dose contributions of the daughters from parents 238 U and 239 Pu are less significant during the considered 100-10000 years. In case of contamination of irrigation water with 1 Bq x m -3 of the parent radionuclide 231 Pa, more than 90% of the external dose from soil exposure comes from the daughter 227 Ac (annually 15 nSv). By a similar contamination with 226 Ra as a parent radionuclide, 60% of the ingestion dose is due to food contamination with the daughters 210 Pb and 210 Po (approximately 150 nSv x a -1 ). (author)

  3. Photonuclear data evaluation of 239Pu

    International Nuclear Information System (INIS)

    Raskinyte, I.; Dupont, E.; Ridikas, D.

    2006-01-01

    This document presents cross-section calculations up to 130 MeV for Pu 239 using the Talys-0.64 code. The photoabsorption process is described by the giant dipole resonance and quasi-deuteron mechanisms. Preequilibrium particle emission is treated with the classical exciton model. At equilibrium, the compound nucleus decay channels are handled within the Hauser-Feshbach statistical model. Neutron transmission coefficients are calculated with a double humped parabolic model. A few sensitive nuclear parameters were fine-tuned to better reproduce the experimental data available for (γ,n), (γ,2n) and (γ,f) partial cross-sections. In addition, the nuclear models provide predictions of the emitted neutron energy and angular distributions. (A.C.)

  4. Energy Dependence of Fission Product Yields from 235U, 238U and 239Pu for Incident Neutron Energies Between 0.5 and 14.8 MeV

    Science.gov (United States)

    Gooden, M. E.; Arnold, C. W.; Becker, J. A.; Bhatia, C.; Bhike, M.; Bond, E. M.; Bredeweg, T. A.; Fallin, B.; Fowler, M. M.; Howell, C. R.; Kelley, J. H.; Krishichayan; Macri, R.; Rusev, G.; Ryan, C.; Sheets, S. A.; Stoyer, M. A.; Tonchev, A. P.; Tornow, W.; Vieira, D. J.; Wilhelmy, J. B.

    2016-01-01

    Fission Product Yields (FPY) have historically been one of the most observable features of the fission process. They are known to have strong variations that are dependent on the fissioning species, the excitation energy, and the angular momentum of the compound system. However, consistent and systematic studies of the variation of these FPY with energy have proved challenging. This is caused primarily by the nature of the experiments that have traditionally relied on radiochemical procedures to isolate specific fission products. Although radiochemical procedures exist that can isolate all products, each element presents specific challenges and introduces varying degrees of systematic errors that can make inter-comparison of FPY uncertain. Although of high importance in fields such as nuclear forensics and Stockpile Stewardship, accurate information about the energy dependence of neutron induced FPY are sparse, due primarily to the lack of suitable monoenergetic neutron sources. There is a clear need for improved data, and to address this issue, a collaboration was formed between Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL) and the Triangle Universities Nuclear Laboratory (TUNL) to measure the energy dependence of FPY for 235U, 238U and 239Pu. The measurements have been performed at TUNL, using a 10 MV Tandem Van de Graaff accelerator to produce monoenergetic neutrons at energies between 0.6 MeV to 14.8 MeV through a variety of reactions. The measurements have utilized a dual-fission chamber, with thin (10-100 μg/cm2) reference foils of similar material to a thick (100-400 mg) activation target held in the center between the chambers. This method allows for the accurate determination of the number of fissions that occurred in the thick target without requiring knowledge of the fission cross section or neutron fluence on target. Following activation, the thick target was removed from the dual-fission chamber and gamma

  5. Energy Dependence of Fission Product Yields from {sup 235}U, {sup 238}U and {sup 239}Pu for Incident Neutron Energies Between 0.5 and 14.8 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Gooden, M.E., E-mail: m_gooden@lanl.gov [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Arnold, C.W. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Becker, J.A. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Bhatia, C. [McMaster University, Ontario (Canada); Bhike, M. [Department of Physics, Duke University,Durham, North Carolina 27708 (United States); Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); Bond, E.M.; Bredeweg, T.A. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Fallin, B. [Department of Physics, Duke University,Durham, North Carolina 27708 (United States); Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); Fowler, M.M. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Howell, C.R. [Department of Physics, Duke University,Durham, North Carolina 27708 (United States); Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); Kelley, J.H. [Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); Department of Physics, North Carolina State University, Raleigh, North Carolina 27605 (United States); Krishichayan [Department of Physics, Duke University,Durham, North Carolina 27708 (United States); Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); Macri, R. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Rusev, G. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Ryan, C.; Sheets, S.A.; Stoyer, M.A.; Tonchev, A.P. [Lawrence Livermore National Laboratory, Livermore, California 94550 (United States); Tornow, W. [Department of Physics, Duke University,Durham, North Carolina 27708 (United States); Triangle Universities Nuclear Laboratory, Durham, North Carolina 27708 (United States); and others

    2016-01-15

    Fission Product Yields (FPY) have historically been one of the most observable features of the fission process. They are known to have strong variations that are dependent on the fissioning species, the excitation energy, and the angular momentum of the compound system. However, consistent and systematic studies of the variation of these FPY with energy have proved challenging. This is caused primarily by the nature of the experiments that have traditionally relied on radiochemical procedures to isolate specific fission products. Although radiochemical procedures exist that can isolate all products, each element presents specific challenges and introduces varying degrees of systematic errors that can make inter-comparison of FPY uncertain. Although of high importance in fields such as nuclear forensics and Stockpile Stewardship, accurate information about the energy dependence of neutron induced FPY are sparse, due primarily to the lack of suitable monoenergetic neutron sources. There is a clear need for improved data, and to address this issue, a collaboration was formed between Los Alamos National Laboratory (LANL), Lawrence Livermore National Laboratory (LLNL) and the Triangle Universities Nuclear Laboratory (TUNL) to measure the energy dependence of FPY for {sup 235}U, {sup 238}U and {sup 239}Pu. The measurements have been performed at TUNL, using a 10 MV Tandem Van de Graaff accelerator to produce monoenergetic neutrons at energies between 0.6 MeV to 14.8 MeV through a variety of reactions. The measurements have utilized a dual-fission chamber, with thin (10-100 μg/cm2) reference foils of similar material to a thick (100-400 mg) activation target held in the center between the chambers. This method allows for the accurate determination of the number of fissions that occurred in the thick target without requiring knowledge of the fission cross section or neutron fluence on target. Following activation, the thick target was removed from the dual-fission chamber

  6. Toxicity of inhaled 239PuO2 in Beagle dogs. A. Monodisperse 0.75 μm AD particles. B. Monodisperse 1.5 μm AD particles. C. Monodisperse 3.0 μm AD particles. II

    International Nuclear Information System (INIS)

    Muggenburg, B.A.; Guilmette, R.A.; Hahn, F.F.; McClellan, R.O.; Mauderly, J.L.; Mewhinney, J.A.; Pickrell, J.A.; Boecker, B.B.

    1978-01-01

    Studies on the metabolism, dosimetry and biological effects of inhaled particles of 239 PuO 2 have been initiated in Beagle dogs. To obtain information on the relative importance of homogeneity of radiation doses to the lung, dogs have been exposed to particles of monodisperse aerosols (sigma/sub g/ 239 PuO 2 ; 40 dogs to the 0.75 μm AD particles, 72 dogs to the 1.5 μm AD particles and 60 dogs to the 3.0 μm AD particles. The exposures have resulted in graded ILB's, which range from 0.0002 to 2.6 μCi/kg body weight. Twenty-nine dogs were exposed to the aerosol diluent and serve as controls. Five dogs have died 336 to 561 days after exposure in the 1.5 μm AD study. Four dogs have died 116 to 589 days after exposure in the 3.0 μm AD study. These dogs had radiation pneumonitis and pulmonary fibrosis at death. The remaining dogs have survived up to 634 days after exposure. It is anticipated that the other dogs planned for these studies will be exposed over the next 12 months

  7. Simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments; Mesure des isotopes du plutonium des sediments marins par spectrometrie de masse a plasma couple inductivement haute resolution (HR ICP-MS)

    Energy Technology Data Exchange (ETDEWEB)

    Bruneau, F

    1999-07-01

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  8. The fission cross sections of /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu and /sup 242/Pu relative /sup 235/U at 14. 74 MeV neutron energy

    Energy Technology Data Exchange (ETDEWEB)

    Meadows, J.W.

    1986-12-01

    The measurement of the fission cross section ratios of nine isotopes relative to /sup 235/U at an average neutron energy of 14.74 MeV is described with particular attention to the determination of corrections and to sources of error. The results are compared to ENDF/B-V and to other measurements of the past decade. The ratio of the neutron induced fission cross section for these isotopes to the fission cross section for /sup 235/U are: /sup 230/Th - 0.290 +- 1.9%; /sup 232/Th - 0.191 +- 1.9%; /sup 233/U - 1.132 +- 0.7%; /sup 234/U - 0.998 +- 1.0%; /sup 236/U - 0.791 +- 1.1%; /sup 238/U - 0.587 +- 1.1%; /sup 237/Np - 1.060 +- 1.4%; /sup 239/Pu - 1.152 +- 1.1%; /sup 242/Pu - 0.967 +- 1.0%. 40 refs., 11 tabs., 9 figs.

  9. Some comments on the toxicity of 239Pu

    International Nuclear Information System (INIS)

    Rowland, R.E.

    1978-01-01

    There is no simple method of expressing a concept such as toxicity. The toxicity of a material depends upon its form (solid, liquid, or gas), the method of entry into the body (ingestion, inhalation, or abrasion), and the individual it enters (young, old, sick, well, heavy cigarette smoker, or consumer of alcohol). Thus, statements such as ''plutonium is the most toxic material known to man'' are not only incorrect; they are meaningless. By taking the one aspect of plutonium which can be quantitated in a meaningful manner, the induction of malignant bone sarcomas in humans, the incremental risk presented to those who have been exposed to this radioelement has been shown to be quite small. By means of a hypothetical exposure of radium dial workers to plutonium instead of radium, an industry-wide exposure to plutonium would have been less harmful than the actual exposure to radium, in spite of the fact that plutonium appears to be far more toxic than radium. Further, the observation that, after radium was recognized as a toxic material, it no longer was a hazard in the dial industry, clearly demonstrates that hazardous radioactive materials can be handled safely. This has been demonstrated again with plutonium, for even though much larger quantities have been handled by many more individuals, there are no demonstrable cases of malignancies induced by this hazardous material. The absence of clearly demonstrable excesses of lung cancer in the large group of long-term thorium workers is reassuring, for it may imply that low doses to the lung have a very low probability of inducing lung cancers. It is concluded that plutonium, a highly toxic material, can be handled safely, as are many other hazardous materials that play important roles in our daily lives

  10. Estimation of 239Pu in urine, influence of Sulkowich reagent

    International Nuclear Information System (INIS)

    Kalaiselvan, S.; Prasad, M.V.R.; Jeevanram, R.K.

    1988-01-01

    Plutonium is known to be co-precipitated with Sulkowich reagent as calcium ammonium oxalate. In adopting this technique for bio-assay of plutonium, its accuracy depends on the self-absorption of the resulting precipitate in each urine sample. Pu recovery experiments were carried out with varying concentration of Ca and Mg, using different volumes of Sulkowich reagent. When the sample volume is 500 ml, Pu in urine can be estimated with an accuracy and precision of 74.38%+-7.4%, with a detection limit of 0.06 Bq (1.6 pCi) per dm 3 . (author) 3 refs.; 2 figs.; 2 tabs

  11. 239Pu metabolism in the blood after its intratracheal administration

    International Nuclear Information System (INIS)

    Buldakov, L.A.; Khalturin, G.V.; Demina, G.A.

    1979-01-01

    The kinetics of the resorbed from the lungs plutonium metabolism and the forms of its presence in the blood as well as the dynamics of its deposit in the organs of secondary deposition (liver, skeleton) were studied in experiment with female rats. It was shown (gel-filtration method) that plutonium is present in blood serum in various physico-chemical forms: bound with macroglobulin, γ-globulin and albumin-transferrin fractions of proteins and not bound with proteins; this or that form of plutonium may dominate in time (4 min-64 days)

  12. Theory of isotope scanning; Theorie de l'Exploration par les Radioisotopes; Teoriya meditsinskikh issledovanij s primeneniem izotopov; Teoria de la exploracion mediante radioisotopos

    Energy Technology Data Exchange (ETDEWEB)

    Brownell, G L [Physics Research Laboratory, Massachusetts General Hospital, Boston, MA (United States)

    1959-07-01

    aspecto del empleo de los radioisotopos en la medicina. El autor compara los esquemas de sensibilidad de diversos sistemas de colimacion y calcula su eficacia y su poder de resolucion. Los sistemas de coliminacion de que se trata se componen de orificios cilindricos y cenicos, de colimadores de enfoque y de dispositivos que permitan detectar por coincidencia las radiaciones de aniquilacion. Formula una teoria general con miras a establecer la concentracion optima de isotopos para cada uno de los sistemas. El autor enuncia una teoria analoga con respecto a la camara de centelleo, y compara la concentracion optima de isotopos para este dispositivo en relacion con los resultados logrados con ayuda de los distintos metodos de exploracion. Estudia tambien la posibilidad de modificar el principio de la camara a fin de utilizarla en la deteccion de las radiaciones de aniquilacion. Para terminar, compara diversos sistemas de registre desde el punto de vista de su eficacia y de la presentacion de los datos. (author) [Russian] Vozmozhnost' tochno ustanovit' raspredelenie izotopov yavlyaetsya vazhnym aspektom ispol'zovaniya ikh v meditsine. Sravnivaetsya stepen' chuvstvitel'nosti razlichnykh sistem kollimirovaniya, ustanavlivaetsya ikh ehffektivnost' i razreshayushchaya sposobnost'. Rassmatrivaemye kollimiruyushchie sistemy sostoyat iz tsilindricheskikh i konusnykh otverstij, fokusiruyushchikh kollimatorov i prispo-soblenij dlya obnaruzheniya annigilyatsionnogo izlucheniya metodom sovpadenij. Vyrabatyvaetsya obshchaya teoriya s tsel'yu ustanovit' optimal'nuyu kontsentratsiyu izotopov dlya kazhdoj iz ehtikh sistem. Podobnaya zhe teoriya razrabatyvaetsya i dlya stsintillyatsionnoj kamery; pro voditsya sravnenie optimal'noj kontsentratsii izotopov ehtogo pribora v svyazi s primenyaemymi metodami issledovaniya. Obsuzhdaetsya vopros ob izmenenii printsipa dejstviya kamery v tselyakh ispol'zovaniya ee pri nalichii annigilya-tsionnogo izlucheniya. Sravnivayutsya razlichnye sistemy

  13. On the Behaviour of Radioisotopes Incorporated in Glass Blocks; Le Comportement des Radioisotopes Vitrifies; O Povedenii Radioaktivnyh Izotopov, Lokalizovannyh v Steklovidnyh Blokah; Comportamiento de los Radioisotopos Vitrificados

    Energy Technology Data Exchange (ETDEWEB)

    Zimakov, P. V.; Kulichenko, V. V.; Duhovich, F. S.; Salamatmn, B. A.

    1963-02-15

    mismos y, por consiguiente, en su capacidad de fijacion de los isotopos. Esas alteraciones son mas pronunciadas en la superficie, debido al contacto con los agentes externos (aire, agua). El riesgo-de lixiviacion aumenta, como es logico, con la irradiacion de los bloques. Los experimentos realizados por los autores demuestran que los radioisotopos de las capas superficiales acusan una fuerte tendencia a pasar al estado gaseoso. Teniendo en cuenta el efecto combinado de los factores que actuan sobre los bloques vitreos diurante un almacenamiento prolongado, es preciso, mediante una eleccion adecuada de su composicion quimica (tundente) y de. las condiciones de elaboracion, asegurar la fijacion deseada de los isotopos radiactivos en los bloques enterrados. Ofrece gran interes, en ese sentido, el empleo de compuestos de titanio para la preparacion del fundente. (author) [Russian] V svjazi s tem, chto nekotorye izotopy imejut bol'shie periody poluraspada, neobhodimo obespechit' ih nadezhnuju lokalizaciju ka dlitel'noe vremja, a jeto trebuet izuchenija povedenija takih izotopov v steklovidnyh blokah pod vlijaniem uslovij, kotorye sozdajutsja pri dlitel'nom hranenii: samorazogrev, samoobluchenie, vlijanie okruzhajushhej sredy. Stremlenie ogranichit ob'em blokov d. ja zahoronenija i letuchest' izotopov pri ih prigotovlenii (temperatura - ne vyshe 1200 Degree-Sign C) privodit k neodnorodnoj'strukture takih blokov- Oni javljajutsja ne istinnym steklom, a ''steklovidnymi'' soedinenijami. Svojstva takih blokov i prochnost' lokalizacii v nih oskolochnyh izotopov sil'no zavisjat ot ih himicheskogo sostava (kolichestvo i priroda fljusa), uslovij prigotovlenija i posledujushhego hranenija. Povyshennaja temperatura, razvivajushhajasja v rezul'tate teplovydelenija vysokoradioaktivnyh blokov v mogil'nike, vyzyvaet himicheskie i fizicheskie processy v ih strukturah i sil'no vlijaet na prochnost' lokalizacii v nih oskolkov, osobenno s poverhnosti blokov. Vyshhelachivaemoet' izotopov iz

  14. Matrix effects corrections in DDT assay of {sup 239}Pu with the CTEN instrument

    Energy Technology Data Exchange (ETDEWEB)

    Hollas, C.L.; Arnone, G.; Brunson, G.; Coop, K. [Los Alamos National Lab., NM (United States)

    1997-11-01

    The accuracy of transuranic (TRU) waste assay using the differential die-away technique depends upon significant corrections to compensate for the effects of the matrix material in which the TRU waste is located. We have used a new instrument, the combined thermal/epithermal neutron (CTEN) instrument for the assay of TRU waste, to develop methods to improve the accuracy of these corrections. Neutrons from a pulsed 14-MeV neutron generator are moderated in the walls of the CTEN cavity and induce fission in the TRU material. The prompt neutrons from these fission events are detected in cadmium-wrapped {sup 3}He neutron detectors. We have developed methods of data acquisition and analysis to extract correlation in the neutron signals resulting from fission during active interrogation. This correlation information, in conjunction with the total number of neutrons detected, is used to determine the fraction of fission neutrons transmitted through the matrix material into the {sup 3}He detectors. This determination allows us to cleanly separate the matrix effects into two processes: matrix modification upon the neutron interrogating flux and matrix modification upon the fraction of fission neutrons transmitted to the neutron detectors. Recent results indicate that for some matrix systems, corrections for position dependent effects within the matrix are possible. 7 refs., 7 figs., 1 tab.

  15. Late effects of 239Pu injection in adult, weanling, newborn, and fetal rats

    International Nuclear Information System (INIS)

    Sikov, M.R.; Mahlum, D.D.; Zwicker, G.M.; Hess, J.O.; Carr, D.B.

    1980-01-01

    Exposure to Pu decreased the latency of mammary tumor induction in all age groups; incidence varied with the age at injection, and with the dose. There were age-related differences in the effect of plutonium exposure on pituitary tumor incidence, as well as an association between the presence of both mammary and pituitary tumors. Prenatal exposure also increased the incidence of adrenal and pancreatic neoplasms in males

  16. Characteristics of monolayer culture of bone marrow cells of rats bearing 239Pu-induced osteosarcoma

    International Nuclear Information System (INIS)

    Bukhtoyarova, Z.M.; Lemberg, V.K.

    1984-01-01

    The report is concerned with a monolayer culture of bone marrow cells of rats in which optimal blastogenic dose (92.5 kBq/kg) induced osteosarcoma. The cell culture showed an enhanced rate of fibroblast-like cell proliferation (increased number of mitoses and symplasts and larger colonies of cells), apparent signs of radiation in ury (pathologic mitoses, chromosome aberrations and gaps) as well as an increase in ploidy. Diffusion chamber measurements demonstrated osteogenic precursor-cells in osteosarcoma-bearing rats to be highly capable of bone formation. This relatively high ability seems to occur outside bone marrow as well

  17. Transuranic and tracer simulant resuspension. [/sup 238/Pu, /sup 239/Pu, /sup 240/Pu

    Energy Technology Data Exchange (ETDEWEB)

    Sehmel, G. A.

    1977-07-01

    Plutonium resuspension results are summarized for experiments conducted at Rocky Flats, onsite on the Hanford reservation, and for winds blowing from offsite onto the Hanford reservation near the Prosser barricade boundary. In each case, plutonium resuspension was shown by increased airborne plutonium concentrations as a function of either wind speed or as compared to fallout levels. All measured airborne concentrations were below maximum permissible concentrations (MPC). Both plutonium and cesium concentrations on airborne soil were normalized by the quantity of airborne soil sampled. Airborne radionuclide concentrations in ..mu..Ci/g were related to published values for radionuclide concentrations on surface soils. For this ratio of radionuclide concentration per gram on airborne soil divided by that for ground surface soil, there are eight orders of magnitude uncertainty from 10/sup -4/ to 10/sup 4/. Horizontal plutonium fluxes on airborne nonrespirable soils at all three sites were bracketed within the same three to four orders of magnitude from 10/sup -7/ to 10/sup -3/ ..mu..Ci/(m/sup 2/ day) for plutonium-239 and 10/sup -8/ to 10/sup -5/ ..mu..Ci/(m/sup 2/ day) for plutonium-238. These are the entire experimental base for nonrespirable airborne plutonium transport. Airborne respirable plutonium-239 concentrations increased with wind speed for a southeast wind direction coming from offsite near the Hanford reservation Prosser barricade. Airborne plutonium fluxes on nonrespirable particles had isotopic ratios, /sup 240/Pu//sup 239 +240/Pu, similar to weapons grade plutonium rather than fallout plutonium. Resuspension rates were summarized for controlled inert particle tracer simulant experiments. Wind resuspension rates for tracers increased with wind speed to about the fifth power.

  18. Effectiveness of urgent DTPA therapeutic treatment following penetration of 239Pu via skin

    International Nuclear Information System (INIS)

    Khokhryakov, V.F.; Belyaev, A.P.; Kudryavtseva, T.I.; Moroz, G.S.; Shalaginov, V.A.

    2001-01-01

    Results of radiological examination and to evaluate therapeutic treatment with DTPA in a worker of the Mayak radiochemical plant, affected by a chemical burn of the skin caused by concentrated plutonium nitrate solutions are assessed. The plutonium content was specified by radiochemical techniques in samples of urine, blood, iliac bone biopsy, skin and bandage. The content in the skin lesion was determined by means of scintillation gamma-spectrometry. The treatment was performed through intravenous DTPA injection without surgical intervention. The urinary excretion dynamics correlated with changes of the nuclide content in blood plasma and in the injured area of the skin. The value of the kidney clearance of plutonium was falling from 110-190 ml/min in the first week down to 3-4 ml/min in the latest periods due to decontamination of the wound. Plutonium resorption into the blood from the injured skin area was 4.1%. As a result of the intensive chelatotherapy 98% of plutonium resorbed was intercepted and excreted [ru

  19. Initial synthesis of area 13 239Pu data and other statistical analyses

    International Nuclear Information System (INIS)

    Gilbert, R.O.; Eberhardt, L.L.

    1976-02-01

    An initial effort is made here to synthesize the 239-240 Pu data currently available from Area 13 (Project 57). Plutonium concentrations for soil, vegetation, small vertebrates, and various tissues in beef cattle (grazed on the Pu contaminated vegetation) are plotted on a single graph for visual comparison. Hypothetical 239-240 Pu concentrations for lungs, skeletal bone, and kidney of a Standard Man assumed to live in and obtain most of his food from the area are also plotted. These hypothetical values were obtained using results from the plutonium transport and dose estimation model of Martin and Bloom (1975)

  20. Relationship between blood flow, bone structure, and 239Pu deposition in the mouse skeleton

    International Nuclear Information System (INIS)

    Humphreys, E.R.; Green, D.; Howells, G.R.; Thorne, M.C.

    1982-01-01

    The rate at which blood is supplied to several bones in female CBA mice was calculated from 18 F measurements in bone and blood. Blood flow measurements were compared with plutonium uptake in whole bone and on endosteal and periosteal bone surfaces. The results showed that: the rate at which blood is supplied to bone determines the rate of deposition of plutonium; there is a threshold rate of blood supply below which plutonium is not deposited; and the rate of blood supply determines the density of plutonium deposition on endosteal but not on periosteal bone surfaces. These results are discussed in the light of the current bone blood supply hypotheses. (orig.)

  1. On the fission probability for 235U, 239Pu and 241Pu

    International Nuclear Information System (INIS)

    Benzi, V.; Maino, G.; Menapace, E.

    1978-01-01

    An evaluation of the GAMMAsub(n)/GAMMAsub(f) ratio for the 236 U, 240 Pu and 242 Pu compound nuclei is carried out. First chance and second chance fission cross sections are estimated from the ''evaporation'' model; particularly, a largely increasing trend was found for the first chance fission cross section above the (n,n'f) process threshold. The GAMMAsub(n)/GAMMAsub(f) ratios for the analyzed nuclei show a bump-like structure, that seems to be in agreement with the theoretical predictions reported in literature

  2. Metabolism of inhaled 239PuO2 particles in rat pulmonary

    International Nuclear Information System (INIS)

    Su Yuanfu; Guo Yao

    1986-01-01

    The changes in myocardial ultrastructure showed distinct dose-effect relation ship. Myocardial fibres maintained normal feature at doses below 150 Gy, even though small intestine epithelial lining was damaged and myocardial microvessels degenerated apparently. With the radiation dose increased to 250 Gy, degeneration and destruction of myocardial fibrils appeared. This events revealed the direct dependence of myocardial fibrillar changes to radiation doses but not to vascular lesion. Electrocardiography showed S-T segment in addition to the prolongation of Q-T intervals and T waves, while myocardial fibrils, myocardial mitochondria, T and L tubular systems and intercalate discs all underwent alterations. These abnormalities in dicated aberration of depolarization and repolarization in the animals heart. In parallel with the electrocardiographic changes, the level of plasma LDH 1 increased, which suggested cellular lesion and leakage of intracellular enzymes. All above changes supported the concept on presence of a 'cardio-vascular type' in acute radiation sickness

  3. Oncogene expression in primary lung tumors in dogs that inhaled 239PuO2

    International Nuclear Information System (INIS)

    Kelly, G.; Kerkof, P.R.; Haley, P.J.

    1988-01-01

    Ten radiation-induced and three spontaneous lung tumors were analyzed for aberrant expression of known oncogenes. In 12 of 13 tumors tested, sequences hybridizing to the c-myc oncogene were expressed at levels 1.5 times higher than sequences hybridizing to β-actin. This level of oncogene expression was also observed in 9 of 13 tumors for 1 or more members of the ras family of oncogenes. Seven of thirteen tumors examined express sequences that hybridize with clones of v-ros or c-met. The ros and met clones both code for oncogenes whose normal homologues are transmembrane proteins related to the insulin receptor. (author)

  4. Biological action of 239Pu during its administration to rats by inhalation and Zn- or CaDTPA- complexone therapy

    International Nuclear Information System (INIS)

    Sinyakov, E.G.; Nifatov, A.P.; Lyubchanskij, Eh.R.; Bazhin, A.G.

    1988-01-01

    The authors described the effect of substantial amounts of plutonium nitrate administered to rats by inhalation in the presence of Zn- or CaDTPA-complexone therapy for 2 months. A 2-fold decrease of absorbed doses in the lung, a 3-fold decrease in the skeleton and a 4-fold decrease in the liver were shown. The mean life span of the treated animals was considerably raised. A significant reduction of the frequency of development of severe pneumosclerosis and an increase in the frequency of lung tumor development were noted. In view of the above, complexone therapy should be necessarily recommended during inhalation of radionucleides in austantial ammounts

  5. Oncogene expression in primary lung tumors in dogs that inhaled {sup 239}PuO{sub 2}

    Energy Technology Data Exchange (ETDEWEB)

    Kelly, G; Kerkof, P R; Haley, P J

    1988-12-01

    Ten radiation-induced and three spontaneous lung tumors were analyzed for aberrant expression of known oncogenes. In 12 of 13 tumors tested, sequences hybridizing to the c-myc oncogene were expressed at levels 1.5 times higher than sequences hybridizing to {beta}-actin. This level of oncogene expression was also observed in 9 of 13 tumors for 1 or more members of the ras family of oncogenes. Seven of thirteen tumors examined express sequences that hybridize with clones of v-ros or c-met. The ros and met clones both code for oncogenes whose normal homologues are transmembrane proteins related to the insulin receptor. (author)

  6. Migration of plutonium from freshwater ecosystem at Hanford. [/sup 238/Pu, /sup 239/Pu, /sup 240/Pu

    Energy Technology Data Exchange (ETDEWEB)

    Emery, R. M.; Klopfer, D. C.; McShane, M. C.

    1977-09-01

    A reprocessing waste pond at Hanford has been inventoried to determine quantities of plutonium (Pu) that have been accumulated since its formation in 1944. Expressions of export were developed from these inventory data and from informed assumptions about the vectors which act to mobilize material containing Pu. This 14-acre pond provides a realistic illustration of the mobility of Pu in a lentic ecosystem. The ecological behavior of Pu in this pond is similar to that in other contaminated aquatic systems having widely differing limnological characteristics. Since its creation, this pond has received about one Ci of /sup 239/,/sup 240/Pu and /sup 238/Pu, most of which has been retained by its sediments. Submerged plants, mainly diatoms and Potamogeton, accumulate >95% of the Pu contained in biota. Emergent insects are the only direct biological route of export, mobilizing about 5 x 10/sup 3/ nCi of Pu annually, which is also the estimated maximum quantity of the Pu exported by waterfowl, birds and mammals collectively. There is no apparent significant export by wind, and it is not likely that Pu has migrated to the ground water below U-Pond via percolation. Although this pond has a rapid flushing rate, a eutrophic nutrient supply with a diverse biotic profile, and interacts with an active terrestrial environment, it appears to effectively bind Pu and prevent it from entering pathways to man and other life.

  7. The diffusion coefficient for 239Pu, 241Am, 99Tc and 137Cs in highly compacted buffer materials

    International Nuclear Information System (INIS)

    Zhou Kanghan; Li Guoding

    1998-01-01

    Based on one-dimension diffusion model, the diffusion coefficients of Pu, Am, Tc and Cs in highly compacted sodium-bentonite generally used as buffer materials in geologic disposal system for high-level radioactive waste have been determined at room temperature in the atmosphere of nitrogen. The results show that the diffusion coefficients of Am, Pu and Tc and about 10 -13 ∼10 -15 m 2 /s, and that of Cs about 10 -12 m 2 /s. The diffusion coefficients of these elements decrease with the increasing of the dry density of buffer materials. From the relationship of diffusion coefficient, retardation coefficient and dry density of bentonite, it has been concluded that Am and Pu transfer predominately by diffusion in solid phase, however, Cs and Tc by diffusion in pore water

  8. A comparison of the distribution of 239-Pu and calcein in the ilium of the female CBA mouse

    International Nuclear Information System (INIS)

    Howells, G.R.; Green, D.; Sontag, W.; Kernforschungszentrum Karlsruhe G.m.b.H.

    1984-01-01

    It is well recognised that plutonium 239 and certain vital stains such as calcein behave similarly when injected i.v. into experimental animals. Both are rapidly cleared from blood, and concentrate on bone surfaces. Certain differences of behaviour are also known, such as the competitive concentration of plutonium in liver and other soft tissues; and differences in the distribution of site of location of the substances on bone surface. Plutonium tends to concentrate evenly on all bone surfaces in proportion to the blood supply to that region, leading to higher concentrations on endosteal than periosteal surfaces. Calcein deposits at sites of mineralisation, which occur on both endosteum and periosteum in response to the demands of growth and remodelling. Subsequent behaviour of both substances would appear to depend entirely on the growth and remodelling activities of the bone, the deposits remaining fixed in position until the containing bone is resorbed or buried by freshly formed bone. Many studies of the distribution and dosimetry of plutonium in experimental animals, mainly dogs, and mice have been recorded. There is however, a lack of information concerning the behaviour of the radionuclide in man. More information is available on the behaviour in man and experimental animals of the vital stains, some of which are well known anti-biotics. Consequently, there is much to be gained if a knowledge of the behaviour of vital stains such as calcein can be used to predict the distribution of plutonium in the human skeleton. (orig.)

  9. Successful DTPA therapy in the case of 239Pu penetration via injured skin exposed to nitric acid

    International Nuclear Information System (INIS)

    Khokhryakov, V.F.; Belyaev, A.P.; Kidryavtseva, T.I.; Schadilov, A.E.; Moroz, G.S.; Shalaginov, V.A.

    2003-01-01

    This paper presents results of the radiological study and DTPA therapy for a worker exposed to a plutonium nitrate solution. Plutonium levels were measured in excreta, blood, plasma and wound for several weeks. Plutonium renal clearance ranged from 110-190 ml min -1 to 3-4 ml min -1 at different stages of chelation therapy. Plutonium absorption into blood from the injured skin amounted to 4.3%. As a result of intensive therapy, 96% of absorbed plutonium was successfully excreted. (author)

  10. Spatial statistical analysis of contamination level of 241Am and 239Pu Thule, North-West Greenland

    International Nuclear Information System (INIS)

    Strodl Andersen, J.

    2011-10-01

    A spatial analysis of data on radioactive pollution on land at Thule, North-West Greenland is presented. The data comprises levels of 241 Am and 239,240 Pu on land. Maximum observed level of 241 Am is 2.8x10 5 Bq m -2 . Highest levels were observed near Narsaarsuk. This area was also sampled most intensively. In Groennedal the maximum observed level of 241 Am is 1.9Oe10 4 Bq m -2 . Prediction of the overall amount of 241 Am and 239,240 Pu is based on grid points within the range from the nearest measurement location. The overall amount is therefore highly dependent on the model. Under the optimal spatial model for Narsaarsuk, within the area of prediction, the predicted total amount of 241 Am is 45 GBq and the predicted total amount of 239,240 Pu is 270 GBq. (Author)

  11. Transuranic concentrations in reef and pelagic fish from the Marshall Islands. [/sup 239/Pu, /sup 240/Pu

    Energy Technology Data Exchange (ETDEWEB)

    Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Jokela, T.A.

    1980-09-01

    Concentrations of /sup 239 + 240/Pu are reported in tissues of several species of reef and pelagic fish caught at 14 different atolls in the northern Marshall Islands. Several regularities that are species dependent are evident in the distribution of /sup 239 + 240/Pu among different body tissues. Concentrations in liver always exceeded those in bone and concentrations were lowest in the muscle of all fish analyzed. A progressive discrimination against /sup 239 + 240/Pu was observed at successive trophic levels at all atolls except Bikini and Enewetak, where it was difficult to conclude if any real difference exists between the average concentration factor for /sup 239 + 240/Pu among all fish, which include bottom feeding and grazing herbivores, bottom feeding carnivores, and pelagic carnivores from different atoll locations. The average concentration of /sup 239 + 240/Pu in the muscle of surgeonfish from Bikini and Enewetak was not significantly different from the average concentrations determined in these fish at the other, lesser contaminated atolls. Concentrations among all 3rd, 4th, and 5th trophic level species are highest at Bikini where higher environmental concentrations are found. The reasons for the anomalously low concentrations in herbivores from Bikini and Enewetak are not known.

  12. Neutron multiplicity for neutron induced fission of 235U, 238U, and 239Pu as a function of neutron energy

    International Nuclear Information System (INIS)

    Zucker, M.S.; Holden, N.E.

    1986-01-01

    Recent development in the theory and practice of neutron correlation (''coincidence'') counting require knowledge of the higher factorial moments of the P/sub ν/ distribution (the probability that (ν) neutrons are emitted in a fission) for the case where the fission is induced by bombarding neutrons of more than thermal energies. In contrast to the situation with spontaneous and thermal neutron induced fission, where with a few exceptions the P/sub ν/ is reasonably well known, in the fast neutron energy region, almost no information is available concerning the multiplicity beyond the average value, [ν], even for the most important nuclides. The reason for this is the difficulty of such experiments, with consequent statistically poor and physically inconsistent results

  13. Global determination of alpha emitters (241Am, 237Np, 239Pu, 232Th) in biological media (urine and feces)

    International Nuclear Information System (INIS)

    Bataller, Georges; Vasson, Olivier de; Bazin, Roger; Bonnard, Danielle; Morello, Marcel.

    1979-01-01

    A technique is described in this paper which permits the determination of the gross alpha activity emitted by a mixture of specially radiotoxic elements in urine and feces. After reduction and adjustment of the solution at pH 5,0, the radionuclides are adsorbed on glass marbles. The elution is made in acid medium (HCl 6N). Under these conditions the chemical yields are very satisfying: 96+-6% for urine and 68+-9% for feces. In case of significant results at the end of the manipulation, the radioactive source quality is sufficient to allow the identification of the contaminating radionuclide(s) by alpha spectrometry [fr

  14. Spatial statistical analysis of contamination level of 241Am and 239Pu, Thule, North-West Greenland

    Energy Technology Data Exchange (ETDEWEB)

    Strodl Andersen, J. (JSA EnviroStat (Denmark))

    2011-10-15

    A spatial analysis of data on radioactive pollution on land at Thule, North-West Greenland is presented. The data comprises levels of 241Am and 239,240Pu on land. Maximum observed level of 241Am is 2.8x105 Bq m-2. Highest levels were observed near Narsaarsuk. This area was also sampled most intensively. In Groennedal the maximum observed level of 241Am is 1.9-104 Bq m-2. Prediction of the overall amount of 241Am and 239,240Pu is based on grid points within the range from the nearest measurement location. The overall amount is therefore highly dependent on the model. Under the optimal spatial model for Narsaarsuk, within the area of prediction, the predicted total amount of 241Am is 45 GBq and the predicted total amount of 239,240Pu is 270 GBq. (Author)

  15. Radiolytic oxidation of UO{sub 2} pellets doped with alpha-emitters ({sup 238/239}Pu)

    Energy Technology Data Exchange (ETDEWEB)

    Muzeau, B. [Commissariat a l' Energie Atomique, Rhone Valley Research Center DTCD/SECM/LMPA, BP 17 171, 30207 Bagnols-sur-Ceze Cedex (France); Jegou, C. [Commissariat a l' Energie Atomique, Rhone Valley Research Center DTCD/SECM/LMPA, BP 17 171, 30207 Bagnols-sur-Ceze Cedex (France)], E-mail: christophe.jegou@cea.fr; Delaunay, F. [Commissariat a l' Energie Atomique, Valduc Research Center, 21120 Is-sur-Tille (France); Broudic, V. [Commissariat a l' Energie Atomique, Rhone Valley Research Center DTCD/SECM/LMPA, BP 17 171, 30207 Bagnols-sur-Ceze Cedex (France); Brevet, A. [Commissariat a l' Energie Atomique, Valduc Research Center, 21120 Is-sur-Tille (France); Catalette, H. [Electricite de France, Les Renardieres Research Center, Route de Sens Ecuelles, 77250 Moret-sur-Loing (France); Simoni, E. [Institut de Physique Nucleaire, Bat. 100, 91406 Orsay Cedex (France); Corbel, C. [Laboratoire des Solides Irradies, UMR 7642-CNRS-CEA-Ecole Polytechnique, Ecole Polytechnique, 91128 Palaiseau Cedex (France)

    2009-01-07

    To assess the impact of alpha radiolysis of water on the oxidative dissolution of UO{sub 2} under anoxic conditions, two series of plutonium-doped samples (specific alpha activity 385 and 18 MBqg{sub UO{sub 2}}{sup -1}) were fabricated, characterized and leached in water of varying complexity (pure water, carbonated water, dissolved hydrogen). Given the very high reactivity of these samples in the presence of air and in order to minimize any prior surface oxidation, a strict experimental protocol was developed based on high-temperature annealing in Ar + 4% H{sub 2} with preleaching cycles. Failure to follow this protocol prevents absolute quantification of oxidation of the UO{sub 2} surface by water radiolysis in solutions. Preoxidation of the pellet surface can lead to uranium release in solution that is dependent on the alpha particle flux, revealing initial oxidation by radiolysis in air including potential traces of water. This makes difficult the accurate quantification of the radiolytic oxidation in water solutions. Controlling the initial surface condition of the samples finally allowed us to demonstrate that radiolytic oxidation in water-saturated media is governed by several threshold effects for which the main parameters are the sample alpha activity and the hydrogen concentration.

  16. Basic methods of isotope analysis; Osnovnye metody analiza izotopov

    Energy Technology Data Exchange (ETDEWEB)

    Ochkin, A V; Rozenkevich, M B

    2000-07-01

    The bases of the most applied methods of the isotope analysis are briefly presented. The possibilities and analytical characteristics of the mass-spectrometric, spectral, radiochemical and special methods of the isotope analysis, including application of the magnetic resonance, chromatography and refractometry, are considered.

  17. Fission fragment yields and total kinetic energy release in neutron-induced fission of235,238U,and239Pu

    Science.gov (United States)

    Tovesson, F.; Duke, D.; Geppert-Kleinrath, V.; Manning, B.; Mayorov, D.; Mosby, S.; Schmitt, K.

    2018-03-01

    Different aspects of the nuclear fission process have been studied at Los Alamos Neutron Science Center (LANSCE) using various instruments and experimental techniques. Properties of the fragments emitted in fission have been investigated using Frisch-grid ionization chambers, a Time Projection Chamber (TPC), and the SPIDER instrument which employs the 2v-2E method. These instruments and experimental techniques have been used to determine fission product mass yields, the energy dependent total kinetic energy (TKE) release, and anisotropy in neutron-induced fission of U-235, U-238 and Pu-239.

  18. On uncertainties and fluctuations of averaged neutron cross sections in unresolved resonance energy region for 235U, 238U, 239Pu

    International Nuclear Information System (INIS)

    Van'kov, A.A.; Blokhin, A.I.; Manokhin, V.N.; Kravchenko, I.V.

    1985-01-01

    This paper analyses the reasons for the differences which exist between group-averaged evaluated cross-section data from different evaluated data files for U235, U238 and Pu239 in the unresolved resonance energy region. (author)

  19. 239Pu(n, 2n) and 241Pu(n, 2n) surrogate cross section measurements using NeutronSTARS

    Energy Technology Data Exchange (ETDEWEB)

    Burke, J. T. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Alan, B. S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Akindele, O. A. [Univ. of California, Berkeley, CA (United States); Casperson, R. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hughes, R. O. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Koglin, J. D. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Tamashiro, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Oregon State Univ., Corvallis, OR (United States); Kolos, K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Norman, E. B. [Univ. of California, Berkeley, CA (United States); Saastamoinen, A. [Univ. of California, Los Angeles, CA (United States); Padilla, A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Univ. of California, Los Angeles, CA (United States); Fisher, S. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2017-12-08

    The goal of this project was to develop a new approach to measuring (n,2n) reactions for isotopes of interest. We set out to measure the 239Pu(n,2n) and 241Pu(n,2n) cross sections by directly detecting the 2n neutrons that are emitted. With the goal of improving the 239Pu(n,2n) cross section and to measure the 241Pu(n,2n) cross section for the first time. To that end, we have constructed a new neutron-charged-particle detector array called NeutronSTARS. It has been described extensively in Casperson et al. [1] and in Akindele et al. [2]. We have used this new neutron-charged-particle array to measure the 241Pu and 239Pu fission neutron multiplicity as a function of equivalent incident-neutron energy from 100 keV to 20 MeV. We have made a preliminary determination of the 239Pu(n,2n) and 241Pu(n,2n) cross sections from the surrogate 240Pu(α,α’2n) and 242Pu(α,α’2n) reactions respectively. The experimental approach, detector array, data analysis, and results to date are summarized in the following sections.

  20. Beta and gamma decay heat measurements between 0.1s--50,000s for neutron fission of 235U, 238U and 239Pu

    International Nuclear Information System (INIS)

    Schier, W.A.; Couchell, G.P.

    1993-01-01

    A helium-jet/tape-transport system is employed in the study of beta-particle and gamma-ray energy spectra of aggregate fission products as a function of time after fission. During the initial nine months of this project we have investigated the following areas: Design, assembly and characterization of a beta-particle spectrometer; Measurement of 235 U(n th ff) beta spectra for delay times 0.2 s to 12,000 s; Assembly and characterization of a 5 x 5 Nal(Tl) gamma-ray spectrometer; Measurement of 235 U(n th ff) gamma-ray spectra for delay times 0.2s to 1 5,500s; Assembly and characterization of HPGe gamma-ray spectrometer with a Nal(Tl) Compton-and-background-suppression annulus; Measurement of 235 U(n th ,ff) high-resolution gamma-ray spectra for delay times 0.6 s to over 100,000 s; Comparison of individual gamma-line intensities with ENDF/B-VI; Adaptation to our computer of unfolding program FERDO for beta and gamma aggregate fission-product energy spectra and development of a spectrum-stripping program for analysis of HPGe gamma-ray spectra; Study of the helium-jet fission-fragment elemental transfer efficiency. This work has resulted in the publication of twelve BAPS abstracts of presentations at scientific meetings. There are currently four Ph.D. and two M.S. candidates working on dissertations associated with the project

  1. Transmutation of.pub.239 Pu and other nuclides using spallation neutrons produced by relativistic protons reacting with massive U- and Pb-targets

    Czech Academy of Sciences Publication Activity Database

    Adam, Jindřich; Adloff, J. C.; Balabekyan, A.; Bamblevski, V. P.; Barabanov, M. Y.; Brandt, R.; Bradnova, V.; Chaloun, P.; Debeauvais, M.; Dwivedi, K. K.; Guo, S. L.; Hashemi-Nezhad, R. S.; Hella, K. M.; Kalinnikov, V. G.; Kievets, M. K.; Krivopustov, M. I.; Kulakov, B. A.; Langrock, E. J.; Li, Li.; Lomonosova, E. M.; Modolo, G.; Odoj, R.; Perelygin, V. P.; Pronskikh, V. S.; Solnyshkin, A. A.; Sosnin, A. N.; Stegailov, V. I.; Tsoupko-Sitnikov, V. M.; Vater, P.; Wan, J. S.; Westmeier, W.; Zamani-Valasiadou, M.; Zhuk, I. V.

    2002-01-01

    Roč. 90, - (2002), s. 441-442 ISSN 0033-8230 R&D Projects: GA AV ČR KSK1048102 Keywords : relativistic protons * transmutation * subcritical nuclear systems * long-lived radiactive waste Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.809, year: 2002

  2. Energy dependence of the neutron multiplicity P/sub nu/ in fast neutron induced fission of /sup 235,238/U and 239Pu

    International Nuclear Information System (INIS)

    Zucker, M.S.; Holden, N.E.

    1986-01-01

    Certain applications require knowledge of the higher moments of the neutron multiplicity probability. It can be shown that the second factorial moment is proportional to the fission rate in the sample, and that the third factorial moment can be of use in disentangling spontaneous fission from induced fission. Using a source of unpublished work in which neutron multiplicities were derived for the fast neutron induced fission of U-235, U-238, and Pu-239, the multiplicity probability has been calculated as a function of neutron energy for the energy range 0 to 10 MeV

  3. Determination of the transfer coefficients between oyster's mushrooms and their cultivation media by using of isotopes 239Pu and 241Am

    International Nuclear Information System (INIS)

    Galanda, D.

    2003-01-01

    Mushrooms are unicellular or poly-cellular organisms, which are feed lateral or saprophytic. Mainly their cells have developed cellular sheet and definite form. Poly-cellular mushrooms generate the fibers, called hypes, which make twine, called mycelium, which side as feeding tissue. From mycelium grow fertile body, which have reproductive function. These fertile bodies with their speed and period of grow, as possible bio-indicators of contamination biosphere by heavy metals, present applicable matrix for analysis. In this work we try to find a way of using fungus to clean up soil contaminated with radioactive waste, especially plutonium and americium. The completely natural method, called myco-remediation or fungal remediation, which was successfully used for clean up soil contaminated with petroleum hydrocarbons and other toxic or hazardous waste, is expected to be faster and more cost-effective than other bioremediation techniques. The analyzed radionuclides were determined using by followed algorithm - the Pu was separated by liquid extraction with Aliquat-336 and for the determination of Am was used liquid extraction with TOPO. For the determination of chemical recovery was used tracer 242 Pu with activity 5,0.10 -2 Bq, respectively 243 Am with activity 1.28.10 -1 Bq. The samples after separation were precipitated, micro-filtrated and follow measured by α-spectrometer Ortec. (author)

  4. Comparison of in situ gamma soil analysis and soil sampling data for mapping 241Am and 239Pu soil concentrations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kirby, J.A.; Anspaugh, L.R.; Phelps, P.L.; Huckabay, G.W.; Markwell, F.; Barnes, M.

    1976-01-01

    Soil sampling and in situ 241 Am-gamma counting with an array of four high purity, planar, Ge detectors are compared as means of determining soil concentration contours of plutonium and their associated uncertainties. Results of this survey, which covered an area of approximately 300,000 m 2 , indicate that with one-third the number of sampling locations, the in situ gamma survey provided soil concentration contours with confidence intervals that were about one-third as wide as those obtained with soil sampling. The methods of the survey are described and a discussion of advantages and limitations of both methods is given

  5. A study of the effect of intermediate structure in the fission cross section of 239Pu on self-shielding factors

    International Nuclear Information System (INIS)

    Ganesan, S.

    1978-01-01

    A set of energy dependent fission widths of 1 + spin state corresponding to the recommended fission cross sections of Sowerby et al is evaluated by adjustment in the energy region 600 ev to 25 Kev. Corresponding to these mean fission widths of 1 + spin state, the intermediate resonance parameters based on Weigmann's formulation of Struitinsky's double humped fission barrier model are then obtained. Pseudorandom resonances are generated with and without the intermediate structure in the mean fission but leading to the same value of infinite dilution fission cross section. The effect of the intermediate structure on the self shielding factors was then investigated. (author)

  6. Artificial radioactivity and marine environment. Study of 238Pu, 239Pu+240Pu, 241Pu and 241Am in the Mediterranean sea

    International Nuclear Information System (INIS)

    Ballestra, Serge.

    1980-10-01

    This paper is in two parts. Part one is about the methods for analyzing transuranium elements particularly the development of an analytical process for plutonium and for perfecting an Americium analyzing method, capable of treating samples of 200 litres of sea water, 100 grams of sediment and 100 grams of biological matter. Part two concerns the in situ determinations carried out within the scope of the study on the distribution and behaviour of transuranium elements in the Mediterranean sea. The high sea studies concerned the effects of atmospheric fall out and the vertical distribution of Pu and Am. Studies along the coasts enabled a quantitative study to be made of the contribution of rivers to the Mediterranean and to study the distribution of Pu along the French Mediterranean coast line [fr

  7. Yields of some fragments on 235U, 238U and 239Pu fission due to the neutrons of the SBR-1 reactors

    International Nuclear Information System (INIS)

    Yurova, L.N.; Bushuev, A.V.; Ozerkov, V.N.; Chachin, V.V.; Zvonarev, A.V.; Liforov, Yu.G.; Koleganov, Yu.V.; Miller, V.V.; Gorbatyuk, O.V.

    1979-01-01

    Determined are the values of the yields of fission fragments in spectrum close to that of the neutron fission using the data on yields at fission by thermal neutrons. The relation between the activities of fragments in samples irradiated in the BR-1 center and in the thermal colomn of the same reactor was measured with the help of the Ge(Li). The relative rate of fissions in uranium and plutonium samples in the center or in thermal colomn were measured by track detectors. The comparison of the yields obtained and the data of other authors is being made

  8. Comparison of in situ gamma soil analysis and soil sampling data for mapping 241Am and 239Pu soil concentrations at the Nevada Test Site

    International Nuclear Information System (INIS)

    Kirby, J.A.; Anspaugh, L.R.; Phelps, P.L.; Huckabay, G.W.; Markwell, F.R.; Barnes, M.G.

    1977-01-01

    Soil sampling and in situ 241 Am-gamma counting with an array of four high-purity, planar, Ge detectors are compared as means of determining soil concentration contours of plutonium and their associated uncertainties. Results of this survey, which covered an area of approximately 300,000 m 2 , indicate that with one-third the number of sampling locations, the in situ gamma survey provided soil concentration contours with confidence intervals that were about one-third as wide as those obtained with soil sampling. The methods of the survey are described and a discussion of advantages and limitations of both methods is given

  9. Distribution of sup 137 Cs, sup 90 Sr, sup 238 Pu, sup 239 Pu, sup 241 Am and sup 244 Cm in Pond B, Savannah River Site

    Energy Technology Data Exchange (ETDEWEB)

    Whicker, F.W. (Colorado State Univ., Fort Collins, CO (USA)); Pinder, J.E. III; Bowling, J.W. (Savannah River Ecology Lab., Aiken, SC (USA)); Alberts, J.J. (Georgia Univ., Sapelo Island, GA (USA). Marine Inst.); Brisbin, I.L. Jr. (Savannah River Ecology Lab., Aiken, SC (USA))

    1989-05-01

    The gradual senescence of present-day operating nuclear facilities, and resultant contamination of aquatic and terrestrial ecosystems, emphasize the importance of understanding the behavior of radionuclides in the environment. Observations and deductions concerning mechanisms of radionuclide transport can contribute significantly to knowledge of fundamental ecological processes. This study emphasized the ecosystem-level distribution of several long-lived radionuclides in an abandoned reactor cooling impoundment after a twenty year period of chemical and biological equilibration. 90 refs., 14 figs., 5 tabs.

  10. A Scintillation Camera for Kinetic Studies of the Distribution of Radioactive Nuclides in the Brain; Chambre a Scintillation pour des Etudes sur la Cinetique de la Repartition des Radionucleides dans le Cerveau; Stsintillyatsionnaya kamera dlya kineticheskogo issledovaniya raspredeleniya radioaktivnykh izotopov v tkani mozga; Camara de Centelleo para Estudiar la Cinetica de la Distribucion de Radionuclidos en el Cerebro

    Energy Technology Data Exchange (ETDEWEB)

    Gross, W. [Radiological Research Laboratory, Department Of Radiology, Columbia University, New York, NY (United States); Schlesinger, E. B.; De Boves, S. [Department of Neurological Surgery, Columbia University, New York, NY (United States)

    1964-10-15

    corresponder a la situacion espacial de los contadores de centelleo. La modulacion de la intensidad del haz del osciloscopio y la supresion de la actividad de fondo facilitan la visualizacion de la distribucion de actividad. (author) [Russian] Razrabotana scintil- ljacionnaja kamera, special'no prednaznachennaja dlja izuchenija kinetiki raspredelenija radioaktivnyh izotopov v tkani mozga. Jetot pribor sostoit iz dvuh grupp, aktivirovannyh talliem kristallov NaJ razmerom 1,8 X 2,5 sm , prichem 63 kristalla kazhdoj gruppy soboany v porjadok 7 x 9 na 2 ,5 -sm centrah. Jeti gruppy m ogut byt' raspolozheny takim o'razom, chtoby odnovremenno poluchat' ob e bokovye proekcii ili odnu bokovuju i odnu za dne-perednjuju ili peredne-zadnjuju proekciju. Pole zrenija kazhdogo kristalla ogranicheno kollimatorom, so stojashhim iz 19 suzhivajushhihsja kanalov s parallel'nymi osjam i. Jeta konstrukcija imeet chuvstvitel'nost' pochti ravnuju polnoj shirote na polovine rasstojanija douslovnogo istochnika opuholi po vsem rasstojanijam do 10 cm ot perednej chasti kollimatora. Jeta chuvstvitel'nost' dostatochno shiroka, chtoby izbezhat' neradioaktivnyh zon , i v to zhe vremja dostatochno uzka , chtoby pozvolit' tochnoe nabljudenie raspredelenija aktivnosti v techenie neskol'kih minut, pri ispol'zovanii normal'nyh indikatornyh doz j o d a -131. Kazhdyj kristall opticheski s o edinen so svoim fotoumnozhitelem v obshhej upakovke. Vyhodnye impul'sy fotoumnozhitelej analizirujutsja s pomoshh'ju diskriminatorov i informacija hranitsja v cifrovoj forme v chetverti zapominajushhego ustrojstva 512-kanal'nogo analizatora vysokih impul'sov. Sovpadajushhie po vremeni impul'sy iz razlichnyh d e tektorov mogut prinimat'sja v jetoj ust anovke s neznachitel'nymi p ot er jam i . Schityvanie dannyh vozmozhno v neskol'kih formah. Mozhno poluchit' dannye v cifrovoj forme, v mashinopisnoj forme ili v vide perfokart. Poslednie mozhno vvesti obratno v pribor dlja povtornogo izuchenija. Analogichnoe schityvanie

  11. Dose-dependent analysis of acute medical effects of mixed neutron-gamma radiation from selected severe 235U or 239Pu criticality accidents in USSR, United States, and Argentina.

    Science.gov (United States)

    Barabanova, Tatyana; Wiley, Albert L; Bushmanov, Andrey

    2012-04-01

    Eight of the most severe cases of acute radiation disease (ARS) known to have occurred in humans (as the result of criticality accidents) had survival times less than 120 h (herein defined as "early death"). These accidents were analyzed and are discussed with respect to the specific accident scenarios and the resulting accident-specific, mixed neutron-gamma radiation clinical dose distributions. This analysis concludes that the cardiovascular system appears to be the most critical organ system failure for causing "early death" following approximate total body, mixed gamma-neutron radiation doses greater than 40-50 Gy. The clinical data also suggest that there was definite chest dose dependence in the resulting survival times for these eight workers, who unfortunately suffered profound radiation injury and unusual clinical effects from such high dose radiation exposures. In addition, "toxemic syndrome" is correlated with the irradiation of large volumes of soft tissues. Doses to the hands or legs greater than 80-100 Gy or radiation lung injury also play significant but secondary roles in causing "early death" in accidents delivering chest doses greater than 50 Gy.

  12. First results studying the transmutation of 129I, 237Np, 238Pu, and 239Pu in the irradiation of an extended natU/Pb-assembly with 2.52 GeV deuterons

    Czech Academy of Sciences Publication Activity Database

    Krivopustov, M. I.; Pavljuk, A. V.; Kovalenko, A.D.; Mariin, I.I.; Elishev, A.F.; Adam, Jindřich; Kovalík, Alojz; Batusov, Yu, A.; Kalinnikov, V. G.; Brudanin, V. B.; Čaloun, Pavel; Tsoupko-Sitnikov, V. M.; Solnyshkin, A. A.; Stegailov, V. I.; Gerbish, Sh.; Svoboda, Ondřej; Dubnická, Z.; Kala, M.; Kloc, M.; Krása, Antonín; Kugler, Andrej; Majerle, Mitja; Wagner, Vladimír; Brandt, R.; Westmeier, W.; Robotham, H.; Siemon, K.; Bielewicz, M.; Kilim, S.; Szuta, M.; Strugalska-Gola, E.; Wojeciechowski, A.; Hashemi-Nezhad, R. S.; Manolopoulou, M.; Fragopolou, M.; Stoulos, S.; Zamani-Valasiadou, M.; Jokic, S.; Katovsky, K.; Schastny, O.; Zhuk, I. V.; Potapenko, A.S.; Safronova, A.A.; Lukashevich, Zh.A.; Voronko, V.A.; Sotnikov, V.V.; Sidorenko, V.V.; Ensinger, W.; Severin, H.D.; Batsev, S.; Kostov, L.; Protokhristov, Kh.; Stoyanov, Ch,.; Yordanov, O.; Zhivkov, P.K.; Kumar, A.V.; Sharma, M.; Khilmanovich, A.M.; Marcinkevich, B.A.; Korneev, S.V.; Damdinsuren, Ts.; Togoo, Ts.; Kumawat, H.

    2009-01-01

    Roč. 279, č. 2 (2009), s. 567-584 ISSN 0236-5731 R&D Projects: GA AV ČR IAA100480803; GA MŠk LC07050 Institutional research plan: CEZ:AV0Z10480505 Keywords : MCNPX. * GeV Subject RIV: BG - Nuclear, Atomic and Molecular Physics, Colliders Impact factor: 0.631, year: 2009

  13. ADS-HE: Evaluated Nuclear Data Library up to 1 GeV for 202Hg, 208Pb, 209Bi, 232Th, 235U, 238U, 237Np, 239Pu, 242Am and 245Cm

    International Nuclear Information System (INIS)

    Lopez Aldama, Daniel

    2013-12-01

    Accelerator Driven Systems (ADS) are being developed for power generation and the transmutation of actinide and fission product waste, and well-defined cross-section libraries suitable for their transport calculations are required. Transport of high energy neutrons and protons near the target assembly requires an extension of the library for incident energies up to 1 GeV. An ADS-HE library for incident neutrons on selected target elements has been developed to meet this request, and assist benchmarking studies linked to ADS experiments and design concepts. New evaluations of high-energy data from 20 MeV up to 1 GeV have been carried out by S.G. Yavshits and O.T. Grudzevich (see INDC(NDS)-0615). The ADS- HE library has been prepared from these high-energy evaluations combined with evaluations below 20 MeV selected from the ENDF/B-VII.1, the JEFF-3.1.2 and the JENDL-4u2 libraries. The ADS-HE library was processed in suitable forms for Monte Carlo transport codes used in the analysis of ADS. ADS-HE is freely available from the IAEA Nuclear Data Section, and is readily accessible on the web site: http://www-nds.iaea.org/ads/adshe.html. (author)

  14. Histograms Constructed from the Data of 239-Pu Alpha-Activity Manifest a Tendency for Change in the Similar Way as at the Moments when the Sun, the Moon, Venus, Mars and Mercury Intersect the Celestial Equator

    Directory of Open Access Journals (Sweden)

    Kharakoz D. P.

    2011-04-01

    Full Text Available Earlier, the shape of histograms of the results of measurements obtained in processes of different physical nature had been shown to be determined by cosmophysical factors. Appearance of histograms of a similar shape is repeated periodically: these are the near-a-day, near-27-days and annual periods of increased probability of the similar shapes. There are two distinctly distinguished near-a-day periods: the sidereal-day (1,436 minutes and solar-day (1,440 minutes ones. The annual periods are represented by three sub-periods: the "calendar" (365 average solar days, "tropical" (365 days 5 hours and 48 minutes and "sidereal" (365 days 6 hours and 9 minutes ones. The tropical year period indicates that fact that histogram shape depends on the time elapsed since the spring equinox.The latter dependence is studied in more details in this work. We demonstrate that the appearance of similar histograms is highly probable at the same time count off from the moments of equinoxes, independent from the geographic location where the measurements had been performed: in Pushchino, Moscow Region (54 deg NL, 37 deg EL, and in Novolazarevskaya, Antarctic (70 deg SL, 11 deg EL. The sequence of the changed histogram shapes observed at the spring equinoxes was found to be opposite to that observed at the autumnal equinoxes. As the moments of equinoxes are defined by the cross of the celestial equator by Sun, we also studied that weather is not the same as observed at the moments when the celestial equator was crossed by other celestial bodies - the Moon, Venus, Mars and Mercury. Let us, for simplicity, refer to these moments as a similar term "planetary equinoxes". The regularities observed at these "planetary equinoxes" had been found to be the same as in the case of true solar equinoxes. In this article, we confine ourselves to considering the phenomenological observations only; their theoretical interpretation is supposed to be subject of further studies.

  15. The adsorption of hydrogen on a molecular sieve at -196{sup o}C and the observation of an isotope effect; Adsorption d'hydrogene sur un tamis moleculaire a -196{sup o}C et observation d'un effet isotopique; Absorbtsiya vodoroda na molekulyarnom fil'tre pri -196{sup o} i nablyudenie rezul'tatov dejstviya izotopov; Adsorcion de hidrogeno en un tamiz molecular a -196{sup o}C y observacion de un efecto isotopico

    Energy Technology Data Exchange (ETDEWEB)

    Duncombe, W G [Wellcome Research Laboratories, Beckenham, Kent (United Kingdom)

    1962-03-15

    adsorbio en el tamiz molecular cerca del 99 % del hidrogeno inicial antes de comenzar la desorcion por bombeo. Por lo tanto, parece probable que el considerable fraccionamiento observado tenga lugar principalmente durante la desorcion y que el efecto carezca de importancia cuando el tamiz se emplea para manipular pequenos volumenes de isotopos del hidrogeno ya que, por lo general, la desorcion total se efectuara por calentamiento. (author) [Russian] Ispytyvalsya molekulyarnyj fil'tr Linde 4 A v kachestve vozmozhnogo sredstva obrashcheniya s nebol'shimi ob{sup e}mami izotopov vodoroda v vakuume, vmesto primenyayushchegosya v nastoyashchee vremya nasosa Toiplera. Davlenie ravnovesiya (P) izmeryaetsya razlichnymi ob{sup e}mami (V) vodoroda, absorbiruemogo odnim grammom fil'tra pri temperature -196{sup o}. EHksperimenty s aktivirovannym drevesnym uglem pokazyvayut preimushchestvo fil'tra kak absorbenta vodoroda. Odin gramm fil'tra v sisteme s ob{sup e}mom v 500 ml absorbiruet okolo 97 % odnogo ml obraztsa vodoroda. Absorbtsiya neznachitel'na pri temperature -78{sup o}, i desorbtsiya yavlyaetsya kolichestvennoj i b'kpro protekaet pri komnatnoj temperature. Vozmozhnost' rezul'tatov dejstviya izotopa izuchalas' putem absorbirovaniya izmeryaemykh ob{sup e}mov tritiya (5 millikyuri/mol') pri ravnomernom davlenii okolo 5 mm, pri ehtom proiskhodilo vykachivanie sistemy v periode do 15 minut i izmerenie ob{sup e}ma ostatochnogo vodoroda. Poslednij prevrashchalsya kolichestvenno v vodu, zatem v butan i gaz. Udel'naya aktivnost' byla vsegda vyshe, chem aktivnost' tritiya, kotoryj prokhodil 10 tsiklov absorbtsii i desorbtsii bez promezhutochnogo vykachivaniya s tem, chtoby ne bylo nikakikh chistykh poter' gaza. EHto imelo takuyu zhe udel'nuyu aktivnost', kak u neobrabotannogo tritiya, vzyatogo iz rezervnoj kolby. Bylo obnaruzheno, chto logarifm (ostatochnyj ob{sup e}m/nachal'nyj ob{sup e}m) proportsionalen 1/logarifm (ostatochnaya udel'naya aktivnost'/ nachal'naya udel'naya aktivnost') v

  16. Plutonium uptake by Scenedesmus obliquus as a function of isotope and oxidation state

    International Nuclear Information System (INIS)

    Tkacik, M.F.; Giesy, J.P.; Wilhite, E.L.; Corey, J.C.

    1979-01-01

    Uptake of 238 Pu 4+ , 238 Pu 6+ , 239 Pu 4+ and 239 Pu 6+ by the green alga Scenedesmus obliquus (Turp) Kutz was studied to determine whether isotope or oxidation state differences affect Pu uptake from aqueous medium by algal cells. At equivalent 238 Pu and 239 PU concentrations, even when initial oxidation states differed, accumulations of these isotopes by S.obliquus were not significantly (p>0.05) different. Plutonium accumulation by S.obliquus was log-linear. (author)

  17. Skeletal lesions from inhaled plutonium in beagles

    International Nuclear Information System (INIS)

    Dagle, G.E.; Park, J.F.; Weller, R.E.; Ragan, H.A.; McClanahan, B.J.; Fisher, D.R.

    1984-10-01

    The report briefly reviews the skeletal effects observed in ongoing lifespan studies in beagle dogs at 13, 10, and 7 years, respectively, after inhalation exposure to 239 Pu oxide and nitrate or 238 Pu oxide. Plutonium nitrate was chosen to represent soluble material more readily translocated to bone and other tissues than the oxide. Bone lesions related to plutonium exposure were observed only in dogs exposed to 238 Pu oxide and 239 Pu nitrate. The skeleton accumulated approximately 2% ( 239 Pu oxide), 45% ( 238 Pu oxide) or 50% ( 239 Pu nitrate) of the final body burdens at 13, 10, and 7 years, respectively, after exposure. 11 references, 2 figures

  18. Analytical description of transfer of Pu-239 in undisturbed soil

    Energy Technology Data Exchange (ETDEWEB)

    Tianshan, Ren; Linsalata, P; Cohen, N

    1986-04-01

    The paper reports on an analytical model for describing the horizontal and down-ward transfer of /sup 239/Pu in undisturbed soil based on observed data. The model has been developed to predict how the depth distribution of /sup 239/Pu in soil would change with time. This information is essential for estimation of the quantities of /sup 239/Pu that have entered surface water body via erosion and runoff processes and for estimation of the long-term impact of /sup 239/Pu isice the commencement of nuclear fallout deposition.

  19. Influence of oxidation state on the absorption of plutonium from the gastrointestinal tract

    International Nuclear Information System (INIS)

    Sullivan, M.F.; Ryan, J.L.; Gorham, L.S.; McFadden, K.M.

    1979-01-01

    Rats and guinea pigs treated intragastrically with either IV- or VI-valent 238 Pu showed no appreciable difference in absorption. Nitric acid solutions of 239 Pu (pH 2) were also administered to fasted and fed rats. When an oxidant (K 2 Cr 2 O 7 ) was present in the solution gavaged to fasted rats, absorption increased 34-fold. However, when 239 Pu VI was administered to fed rats in the absence of dichromate, there was no appreciable difference between the absorption of 239 Pu VI and 239 Pu IV

  20. The isotope-dilution method of fluorine microestimation; Microdosage du fluor pur dilution isotopique; Mikroopredelenie ftora no metodu razbavleniya izotopov; Microvaloracion del fluor por dilucion isotopica

    Energy Technology Data Exchange (ETDEWEB)

    Kudahl, J N; Fremlin, J H; Hardwick, J L [Department of Physics, University of Birmingham (United Kingdom)

    1962-01-15

    Fluoride ions are adsorbed on glass from acid solution and, for solutions containing less than 100 ppm of fluorine, the amount adsorbed varies very regularly with concentration. A certain volume of a carrier-free solution of the unstable isotope F{sup 18} is added to each of a set of acid fluoride solutions which may be a few milligrams, or less, in size. If the solutions are applied to a defined area of glass, some of the F{sup 18} is adsorbed and this can be fixed by raising the pH when equilibrium has been reached. The radioactivity of the glass is a measure of the total amount of fluoride on the glass and can be used to draw an adsorption isotherm from which the fluorine content of an unknown solution in the set can be found. The effects of pH, and the presence of calcium and phosphate ions have been studied, and it has been shown that organic materials may be ashed safely if calcium or magnesium ions are present. The accuracy of the method is independent of the fluoride concentration down to concentrations of a fraction of a ppm. (author) [French] L'ion de fluorure d'une solution acide est adsorbe sur du verre; pour des solutions contenant moins de 100 ppm de fluor, la quantite adsorbee varie tres regulierement en fonction de la concentration. Un certain volume d'une solution, sans entraineur-, de l'isotope instable {sup 18}F est ajoute a une serie de solutions acides de fluorure; il peut s'agir de quantites de l'ordre de quelques milligrammes, ou meme moins. Si l'on applique les solutions sur une surface bien definie de verre, une partie du {sup 18}F est adsorbee; on peut la fixer en augmentant le pH des que l'equilibre a ete realise. La radioactivite du verre donne la mesure de la quantite totale de fluorure fixe sur le verre; elle peut servir a etablir l'isotherme d'adsorption, dont en peut deduire la teneur en fluor de toute solution de la serie. Les auteurs ont etudie les effets du pH et la presence d'ions de calcium et de magnesium; ils ont montre que des matieres organiques peuvent etre reduites en cendres en toute securite si des ions de calcium ou de magnesium sont presents. La precision de la methode ne depend pas de la concentration du fluorure jusqu'a concurrence de valeurs representant une fraction d'une ppm. (author) [Spanish] El vidrio adsorbe los iones fluoruro de las soluciones acidas, y si estas soluciones contienen menos de 100 ppm de fluor, la cantidad adsorbida varia muy regularmente en funcion de la concentracion. El metodo empleado por los autores consiste en anadir a cada uno de los integrantes ele una serie de soluciones acidas, que pueden contener unos miligramos, o menos, de fluoruro, un cierto volumen de una solucion del isotopo inestable {sup 18}F libre de portador. Si estas soluciones se aplican a un area determinada de vidrio, parte del {sup 18}F es adsorbida y puede ser fijada elevando el pH una vez alcanzado el equilibrio. La radiactividad del vidrio constituye una medida de la cantidad total de fluoruro presente sobre el vidrio, y puede utilizarse para trazar una isotermia de adsorcion de la cual se puede deducir el contenido en fluor de una solucion desconocida de la serie. Luego de estudiar los efectos del pH de la presencia de iones calcio y fosfato, los autores ban comprobado que las sustancias organicas pueden ser calcinadas sin peligro alguno siempre que se encuentreu presentes iones calcio o magnesio. La precision del metodo no depende de la concentracion de fluoruro siempre que esta sea inferior a 1 ppm. (author) [Russian] Ion ftora iz kislotnogo rastvora adsorbiruetsya na steklo, i dlya rastvorov, soderzhashchikh menee 100 chastej ftora na million, adsorbiruemoe kolichestvo izmenyaetsya ochen' regulyarno v zavisimosti ot kontsentratsii. K kazhdomu iz kislotnykh rastvorov ftora v dannoj serii, ne prevyshayushchikh po vesu neskol'kikh milligrammov, a to i men'she, dobavlyaetsya nekotoryj ob{sup e}m svobodnogo ot nositelej rastvora neustojchivogo izotopa F{sup 18}. Esli rastvory pomeshchayutsya na opredelennuyu ploshchad' stekla, to nekotoroe kolichestvo F{sup 18} adsorbiruetsya i po ustanovlenii sostoyaniya ravnovesiya mozhet byt' zakrepleno posredstvom uvelicheniya pH. Radioaktivnost' stekla mozhet sluzhit' meroj obshchego kolichestva ftora na stekle i ehta mera mozhet byt' ispol'zovana dlya postroeniya izotermy adsorbtsii, iz kotoroj mozhno vyvesti soderzhanie ftora v neizvestnom rastvore dannoj serii. Bylo izucheno vliyanie pokazatelya rN i prisutstvie ionov kal'tsiya i fosfata i pokazano, chto organicheskie materialy mozhno szhigat' bez kakoj-libo opasnosti, esli oni soderzhat iony kal'tsiya i magniya. Tochnost' ehtogo metoda ne zavisit ot kontsentratsii ftora v rastvorakh, krepost' kotorykh mozhet vyrazhat'sya menee, chem v odnu chast' na million. (author)

  1. Plutonium concentrations in arthropods at a nuclear facility

    Energy Technology Data Exchange (ETDEWEB)

    Bly, J A; Whicker, F W [Colorado State Univ., Fort Collins (USA). Dept. of Radiology and Radiation Biology

    1979-09-01

    Arthropods were collected for /sup 239/ /sup 240/Pu (/sup 239/Pu) and /sup 238/Pu analysis from three study plots in close proximity to the Rocky Flats nuclear weapons plant and from a site 110 km N-NE of the plant. Mean /sup 239/Pu concentrations in arthropods were 265, 16, 0.7 and 0.5 dis/min g/sup -1/ at the three Rocky Flats study plots and at the control site, respectively. Arthropod /sup 239/Pu concentration data were statistically analyzed by season of collection, taxonomic group, and sampling site. Only the collection site differences were significant (..cap alpha.. = 0.01) and these were correlated with /sup 239/Pu concentrations in soil. The mean activity ratio of /sup 239/Pu to /sup 238/Pu in arthropods was 52, similar to the value of 51 obtained for soil. The mean ratio of /sup 239/Pu in arthropods to /sup 239/Pu in 0-3 cm soil at Rocky Flats was 9 x 10/sup -3/. Arthropod biomass and Pu concentration data indicated that only about 10/sup -8/ of the total plutonium inventory is in the arthropod component of the ecosystem. Leafhoppers, grasshoppers and spiders accounted for roughly 80% of the arthropod inventory of /sup 239/Pu.

  2. Pacific Northwest Laboratory annual report for 1976 to the ERDA Assistant Administrator for Environment and Safety. Part 1. Biomedical Sciences

    Energy Technology Data Exchange (ETDEWEB)

    Thompson, R.C.

    1977-05-01

    Separate abstracts were prepared for individual sections of this publication. In addition to research reports the publication also contains organization charts, author index, and appendixes showing data on selected parameters relative to life-span dose-effect studies with inhaled /sup 239/PuO/sub 2/, /sup 238/PuO/sub 2/, and /sup 239/Pu in beagles. (HLW)

  3. Long-term effects of intratracheally instilled 253EsCl3 in rats

    International Nuclear Information System (INIS)

    Ballou, J.E.; Dagle, G.E.; Morrow, W.

    1975-01-01

    ts administered 253 EsCl 3 by intratracheal instillation developed more bone tumors and fewer lung tumors than similar rats administered 239 Pu(NO 3 ) 4 . In explanation, it is suggested that 253 Es may irradiatete bone surface cells more effectively while 239 Pu may irradiate a greater total number of cells in the lung. (U.S.)

  4. Non-destructive assay of EBR-II blanket elements using resonance transmission analysis

    International Nuclear Information System (INIS)

    Klann, R.T.; Poenitz, W.P.

    1998-01-01

    Resonance transmission analysis utilizing a faltered reactor beam was examined as a means of determining the 239 Pu content in Experimental Breeder Reactor-II depleted uranium blanket elements. The technique uses cadmium and gadolinium falters along with a 239 Pu fission chamber to isolate the 0.3 eV resonance in 239 Pu. In the energy range of this resonance (0.1 eV to 0.5 ev), the total microscopic cross-section of 239 Pu is significantly greater than the cross-sections of 238 U and 235 U. This large difference allows small changes in the 239 Pu content of a sample to result in large changes in the mass signal response. Tests with small stacks of depleted uranium and 239 Pu foils indicate a significant change in response based on the 239 Pu content of the foil stack. In addition, the tests indicate good agreement between the measured and predicted values of 239 Pu up to approximately two weight percent

  5. Neutron scattering studies in the actinide region

    International Nuclear Information System (INIS)

    Kegel, G.H.R.; Egan, J.J.

    1993-09-01

    This report discusses the following topics: Prompt fission neutron energy spectra for 235 U and 239 Pu; Two-parameter measurement of nuclear lifetimes; ''Black'' neutron detector; Data reduction techniques for neutron scattering experiments; Inelastic neutron scattering studies in 197 Au; Elastic and inelastic scattering studies in 239 Pu; and neutron induced defects in silicon dioxide MOS structures

  6. Plutonium concentrations in arthropods at a nuclear facility

    International Nuclear Information System (INIS)

    Bly, J.A.; Whicker, F.W.

    1979-01-01

    Arthropods were collected for 239 240 Pu ( 239 Pu) and 238 Pu analysis from three study plots in close proximity to the Rocky Flats nuclear weapons plant and from a site 110 km N-NE of the plant. Mean 239 Pu concentrations in arthropods were 265, 16, 0.7 and 0.5 dis/min g -1 at the three Rocky Flats study plots and at the control site, respectively. Arthropod 239 Pu concentration data were statistically analyzed by season of collection, taxonomic group, and sampling site. Only the collection site differences were significant (α = 0.01) and these were correlated with 239 Pu concentrations in soil. The mean activity ratio of 239 Pu to 238 Pu in arthropods was 52, similar to the value of 51 obtained for soil. The mean ratio of 239 Pu in arthropods to 239 Pu in 0-3 cm soil at Rocky Flats was 9 x 10 -3 . Arthropod biomass and Pu concentration data indicated that only about 10 -8 of the total plutonium inventory is in the arthropod component of the ecosystem. Leafhoppers, grasshoppers and spiders accounted for roughly 80% of the arthropod inventory of 239 Pu. (author)

  7. Mechanistic models of bone cancer induction by radium and plutonium in animals compared to humans

    International Nuclear Information System (INIS)

    Bijwaard, H.

    2006-01-01

    Two-mutation carcinogenesis models of mice and rats injected with 239 Pu and 226 Ra have been derived extending previous modellings of beagle dogs injected with 239 Pu and 226 Ra and radium dial painters. In all cases statistically significant parameters could be derived fitting data from several research groups jointly. This also lead to similarly parametrized models for 239 Pu and 226 Ra for all species. For each data set not more than five free model parameters were needed to fit the data adequately. From the toxicity ratios of the animal models for 239 Pu and 226 Ra, together with the human model for 226 Ra, an approximate model for the exposure of humans to 239 Pu has been derived. Relative risk calculations with this approximate model are in good agreement with epidemiological findings for the plutonium-exposed Mayak workers. This promising result may indicate new possibilities for estimating risks for humans from animal experiments. (authors)

  8. The effect of oxidation state on the absorption of ingested or inhaled plutonium

    International Nuclear Information System (INIS)

    Sullivan, M.F.; Gorham, L.S.; Ryan, J.L.

    1980-01-01

    Rats received plutonium nitrate (as 239 Pu(IV) or 239 Pu(VI) by gavage or nose-only exposure. Some of the animals were deprived of food before and/or after exposure. Results obtained indicate that there was increased retention of plutonium after exposure to 239 Pu(VI) in comparison with 239 Pu(IV). The absence of food either before and/or after inhalation exposure had no effect on the amount of 239 Pu retained by the liver and carcass. It was concluded that plutonium in its hexavalent state may under certain conditions be more readily absorbed from the GI tract, but that these conditions are unlikely to occur in human exposure. (H.K.)

  9. Experiments at the GELINA facility for the validation of the self-indication neutron resonance densitometry technique

    Directory of Open Access Journals (Sweden)

    Rossa Riccardo

    2017-01-01

    Full Text Available Self-Indication Neutron Resonance Densitometry (SINRD is a passive non-destructive method that is being investigated to quantify the 239Pu content in a spent fuel assembly. The technique relies on the energy dependence of total cross sections for neutron induced reaction. The cross sections show resonance structures that can be used to quantify the presence of materials in objects, e.g. the total cross-section of 239Pu shows a strong resonance close to 0.3 eV. This resonance will cause a reduction of the number of neutrons emitted from spent fuel when 239Pu is present. Hence such a reduction can be used to quantify the amount of 239Pu present in the fuel. A neutron detector with a high sensitivity to neutrons in this energy region is used to enhance the sensitivity to 239Pu. This principle is similar to self-indication cross section measurements. An appropriate detector can be realized by surrounding a 239Pu-loaded fission chamber with appropriate neutron absorbing material. In this contribution experiments performed at the GELINA time-of-flight facility of the JRC at Geel (Belgium to validate the simulations are discussed. The results confirm that the strongest sensitivity to the target material was achieved with the self-indication technique, highlighting the importance of using a 239Pu fission chamber for the SINRD measurements.

  10. Reversibility of sorption of plutonium-239 onto hematite and goethite colloids

    International Nuclear Information System (INIS)

    Lu, N.; Cotter, C.R.; Kitten, H.D.; Bentley, J.; Triay, I.R.

    1998-01-01

    Laboratory batch sorption experiments were conducted to evaluate: (1) sorption of plutonium-239 ( 239 Pu) on different iron oxide colloids (hematite and geothite), (2) sorption kinetics of colloidal Pu(IV) and soluble Pu(V) onto these two colloids, and (3) desorption of colloidal Pu(IV) and soluble Pu(V) from 239 Pu-loaded colloids as a function of time. Natural groundwater and carbonate-rich synthetic groundwater were used in this study. To examine the possible influence of bicarbonate on 239 Pu sorption, an additional set of experiments was conducted in sodium nitrate (NaNO 3 ) solutions under carbon dioxide free environments. Our results show that colloidal Pu(IV) as well as soluble Pu(V) was rapidly adsorbed by hematite and goethite colloids in both natural and synthetic groundwater. The amount of 239 Pu adsorbed by both iron oxide colloids in synthetic groundwater was higher than in natural groundwater. The presence of carbonate did not influence the sorption of 239 Pu. While sorption of soluble Pu(V) is a slow process, sorption of colloidal Pu(IV) occurs rapidly. Desorption of Pu from iron oxide colloids is much slower than the sorption processes. Our findings suggest that different sorption and desorption behaviors of 239 Pu by iron oxide colloids in groundwater may facilitate the transport of 239 Pu along potential flowpaths from the areas contaminated by radionuclide and release to the accessible environment. (orig.)

  11. Evaluation of permissible exposure to plutonium in occupational workers

    International Nuclear Information System (INIS)

    Jee, W.S.S.; Kimmel, D.B.

    1980-01-01

    No human toxicity data exist from which to evaluate the current MPBB for 239 Pu of 0.04 μCi. The current method of estimating MPBB for 239 Pu in humans uses 239 Pu: 226 Ra ratios in terms of an average skeletal dose in dogs, then compares them to the experience with 226 Ra and 228 Ra in humans. In this paper, a new approach is used that is based on data about 239 Pu toxicity in dogs and on the cellular distribution of the dose. This information has been assimilated in a computerized model of the skeleton which stimulates 239 Pu location as a function of the bone turnover rate; the model then calculates the total number of bone cell- 239 Pu disintegration interactions occurring after one intravenous injection. The number obtained is compared for beagles with a 12.5-year life span and humans with a 50-year life span. We conclude that the current human MPBB for 239 Pu from a single intravenous exposure is adequate for skeletal protection

  12. Plutonium-induced osteosarcomas in the St. Bernard

    International Nuclear Information System (INIS)

    Taylor, G.N.; Thurman, G.B.; Mays, C.W.; Shabestari, L.; Angus, W.; Atherton, D.R.

    1981-01-01

    Fourteen osteosarcomas were observed among the eight St. Bernards that died following the injection of 239 Pu. Early data tentatively indicate that the St. Bernard is about 5 times more sensitive than the beagle and about 130 times more sensitive than the average person is estimated to be to 239 Pu-induced bone sarcomas. Thus the St. Bernard may be an excellent model in which to study the pathogenesis of bone cancer induction, to evaluate the relationship between spontaneous susceptibility and radiosensitivity, and to determine whether radiosensitivity significantly affects the toxicity ration of 239 Pu/ 226 Ra

  13. Radionuclide ratios in wet and dry deposition samples from June 1976 through December 1977

    International Nuclear Information System (INIS)

    Gavini, M.B.

    1978-01-01

    238 Pu, 239 Pu and 137 Cs in rain and dry fallout and 90 Sr in rain samples were measured at Woods Hole, Massachusetts, from June 1976 through December 1977. The dry fallout was estimated to be about 7.8% of the total deposition of 239 Pu and 137 Cs. 239 Pu/ 137 Cs ratios, almost constant at about 0.011 in rain or dry fallout, February through December 1977, suggested that fractionation between the refractory and volatile radionuclides is insignificant in stratospheric fallout. This supports the idea of regional homogeneity of radionuclide ratios in fallout. (Auth.)

  14. Transport of plutonium across isolated segments of the intestine of neonatal swine

    International Nuclear Information System (INIS)

    Sullivan, M.F.; Gorham, L.S.

    1980-01-01

    Absorption of 239 Pu was measured in neonatal swine gavaged with either 239 Pu(IV) or 239 Pu(VI) niitrate 1 day after birth. When they were killed, 1 or 3 wk later, retention of the Pu(VI) was about 50% greater than retention of Pu(IV). Studies with isolated intestinal segments indicated no appreciable difference in 238 Pu transport by the duodenum, midgut or terminal ileum, and a substantial decrease in absorption between 2 and 19 days after birth

  15. Plutonium in Southern Hemisphere ocean Waters

    DEFF Research Database (Denmark)

    Hirose, K.; Aoyama, M.; Gastaud, J.

    2013-01-01

    Plutonium in seawater collected by the BEAGLE2003 cruise was determined using ICP- SF-MS and alpha spectrometry after Fe co-precipitation and radiochemical purification. Levels and distributions of dissolved plutonium activity concentrations in Southern Hemisphere ocean waters are summarized here......, including historical data. Pu-239 concentrations in surface water----of the central South Pacific (32.5 °S) in 2003 were around 1 mBq/m3. The 239Pu concentrations in the Indian Ocean surface waters (20°S) were similar to that in the South Pacific, whereas the 239Pu concentrations in the South Atlantic...... surface waters (30°S) were markedly lower than those in the South Pacific and Indian Oceans. The 239Pu vertical profile pattern was similar to that in the North Pacific subtropical gyre, although 239Pu concentrations in the deep South Pacific were significantly lower than those in the North Pacific. One...

  16. Analysis by {alpha} spectrometry (chamber with a grid). Proserpine (1960); Analyses par spectrometrie {alpha} (chambre a grille). Proserpine (1960)

    Energy Technology Data Exchange (ETDEWEB)

    Clouet d' Orval, C [Commissariat a l' Energie Atomique, Saclay (France).Centre d' Etudes Nucleaires

    1960-07-01

    The aim is to compare various substances in an electrolytic deposit by means of their {alpha} radiation. The energies are separated by counting in a chamber with a grid, specially designed for the analysis of plutonium. A resolution of 1.7 per cent is normally obtained for plutonium bands. {sup 239}Pu-{sup 233}Pu, {sup 239}Pu-{sup 238}Pu mixtures have been analysed by this method. (author) [French] Il s'agit de comparer, au moyen de leur rayonnement {alpha}, divers corps contenus dans un depot electrolytique. On separe les energies par comptage dans une chambre a grille, specialement concue pour analyser du plutonium. On obtient couramment une resolution de 1,7 pour cent, pour des raies du plutonium. On a pu faire, par cette methode, l'analyse de melanges {sup 239}Pu-{sup 233}Pu et {sup 239}Pu-{sup 238}Pu. (auteur)

  17. Fusion-breeder program

    International Nuclear Information System (INIS)

    Moir, R.W.

    1982-01-01

    The various approaches to a combined fusion-fission reactor for the purpose of breeding 239 Pu and 233 U are described. Design aspects and cost estimates for fuel production and electricity generation are discussed

  18. Alcohol and radionuclide metabolism

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Hess, J.O.

    1978-01-01

    The effect of ethanol administration on the deposition and retention of polymeric 239 Pu and 241 Am citrate was studied in the rat. Only in the case of polymeric Pu was there an effect of alcohol administration

  19. Influence of radiation and non-radiation factors on pancreatic cancer incidence among Mayak PA workers

    Energy Technology Data Exchange (ETDEWEB)

    Zhuntova, G.V.; Tokarskaya, Z.B.; Belyaeva, Z.D. [Southern Ural Biophysics Institute (SUBI), Ozyorsk (Russian Federation); Syrchikov, V.A.; Grigoryeva, E.S. [Mayak Production Association (Mayak PA), Ozyorsk (Russian Federation)

    2006-07-01

    The finding of this nested case-control study suggests that high levels of 239 Pu incorporation (239 Pu body burden > 3.7), alcohol abuse and smoking were associated with increasing the risk of pancreatic cancer among Mayak PA workers chronically exposed to ionizing radiation. The contribution of non radiation factors (alcohol abuse and smoking) to pancreatic tumor incidence is greater (AR=51%) than 239 Pu incorporation kBq; AR = 7%). No significant effect of external gamma rays ({<=} 6.8 Gy), prior exposure to chemical agents, or chronic digestive diseases was found on the incidence of pancreatic tumor. Evaluation of the absorbed alpha-radiation pancreatic dose will permit to make more exact the 239 Pu risk estimation in the further extended study.

  20. Lymphocyte mobilization by dextran sulfate in beagles

    International Nuclear Information System (INIS)

    Ragan, H.A.; Debban, K.H.

    1978-01-01

    Dogs manifesting 239 Pu-induced lymphopenia responded to the lymphocyte-mobilizing agent, dextran sulfate, to a degree similar to that observed in control dogs. No life-threatening increase in prothrombin times or hemorrhagic tendencies were observed

  1. Significantly improving nuclear resonance fluorescence non-destructive assay by using the integral resonance transmission method and photofission

    International Nuclear Information System (INIS)

    Angell, Christopher T.; Hayakawa, Takehito; Shizuma, Toshiyuki; Hajima, Ryoichi

    2013-01-01

    Non-destructive assay (NDA) of 239 Pu in spent nuclear fuel or melted fuel using a γ-ray beam is possible using self absorption and the integral resonance transmission method. The method uses nuclear resonance absorption where resonances in 239 Pu remove photons from the beam, and the selective absorption is detected by measuring the decrease in scattering in a witness target placed in the beam after the fuel, consisting of the isotope of interest, namely 239 Pu. The method is isotope specific, and can use photofission or scattered γ-rays to assay the 239 Pu. It overcomes several problems related to NDA of melted fuel, including the radioactivity of the fuel, and the unknown composition and geometry. This talk will explain the general method, and how photofission can be used to assay specific isotopes, and present example calculations. (author)

  2. Biological effect of plutonium 239 on Salmonella typhimurium

    International Nuclear Information System (INIS)

    Gafieva, Z.A.; Chudin, V.A.

    1988-01-01

    Salmonella typhimurium cells were exposed in a 239 Pu citrate solution. Cell death and induction of gene mutations were an exponential fucntion of γ-radiation dose. LD 37 was 34.8 Gy; mutation doubling dose, 19 Gy

  3. Behaviour of transuranic radionuclides in soils, plants and soil-plant system

    International Nuclear Information System (INIS)

    Vyas, B.N.; Mistry, K.B.

    1996-01-01

    The present paper reviews the investigations undertaken to elucidate the physicochemical, edaphic and physiological aspects of the behaviour of long-lived transuranic radionuclides 239 Pu and 241 Am in typical Indian soils and soil-plant systems. 23 refs

  4. Bulk monitoring of soil for low level transuranic contamination

    International Nuclear Information System (INIS)

    Mandler, J.W.; Randolph, P.D.

    1976-01-01

    A system using γ-ray analysis was developed to survey the soil surrounding retrieval barrels for liquid radioactive waste containing 239 Pu and 241 Am. The performance of scintillation detectors of various sizes for monitoring soil samples was evaluated

  5. Influence of radiation and non-radiation factors on pancreatic cancer incidence among Mayak PA workers

    International Nuclear Information System (INIS)

    Zhuntova, G.V.; Tokarskaya, Z.B.; Belyaeva, Z.D.; Syrchikov, V.A.; Grigoryeva, E.S.

    2006-01-01

    The finding of this nested case-control study suggests that high levels of 239 Pu incorporation (239 Pu body burden > 3.7), alcohol abuse and smoking were associated with increasing the risk of pancreatic cancer among Mayak PA workers chronically exposed to ionizing radiation. The contribution of non radiation factors (alcohol abuse and smoking) to pancreatic tumor incidence is greater (AR=51%) than 239 Pu incorporation kBq; AR = 7%). No significant effect of external gamma rays (≤ 6.8 Gy), prior exposure to chemical agents, or chronic digestive diseases was found on the incidence of pancreatic tumor. Evaluation of the absorbed alpha-radiation pancreatic dose will permit to make more exact the 239 Pu risk estimation in the further extended study

  6. Gamma-ray isotopic ratio measurements for the plutonium inventory verification program

    International Nuclear Information System (INIS)

    Lemming, J.F.; Haas, F.X.; Jarvis, J.Y.

    1976-01-01

    The Plutonium Inventory Verification Program at Mound Laboratory provides a nondestructive means of assaying bulk plutonium-bearing material. The assay is performed by combining the calorimetrically determined heat output of the sample and the relative abundances of the heat-producing isotopes. This report describes the method used for the nondestructive determination of plutonium-238, -240, -241 and americium-241 relative to plutonium-239 using gamma-ray spectroscopy for 93 percent plutonium-239 material. Comparison of chemical data on aliquots of samples to the nondestructive data shows accuracies of +-7 percent for 238 Pu/ 239 Pu, +-15 percent for 240 Pu/ 239 Pu, +- 3 percent for 241 Pu/ 239 Pu, and +-7 percent for 241 Am/ 239 Pu

  7. Inhaled plutonium oxide in dogs

    International Nuclear Information System (INIS)

    Park, J.F.

    1982-01-01

    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. Beagle dogs given a single exposure to 239 PuO 2 or 238 PuO 2 aerosols are being observed for lifespan dose-effect relationships. The 239 Pu body burden of the nine dogs that died of pulmonary-fibrosis-induced respiratory insufficiency during the first 3 yr after exposure was 1 to 12μCi. Nineteen of the dogs exposed to 238 Pu haved died during the first 7-1/2 yr after exposure due to bone and/or lung tumors; their body burdens at death ranged from 0.7 to 10μCi. Chronic lymphopenia was the earliest observed effect after inhalation of 239 PuO 2 or 238 PuO 2

  8. Opimization of fusion-driven fissioning systems

    International Nuclear Information System (INIS)

    Chapin, D.L.; Mills, R.G.

    1976-01-01

    Potential advantages of hybrid or fusion/fission systems can be exploited in different ways. With selection of the 238 U-- 239 Pu fuel cycle, we show that the system has greatest value as a power producer. Numerical examples of relative revenue from power production vs. 239 Pu production are discussed, and possible plant characteristics described. The analysis tends to show that the hybrid may be more economically attractive than pure fusion systems

  9. Subchronic inhalation of carbon tetrachloride alters the tissue retention of acutely inhaled plutonium-239 nitrate in F344 rats and syrian golden hamsters

    International Nuclear Information System (INIS)

    Benson, J.M.; Barr, E.B.; Lundgren, D.L.

    1995-01-01

    Carbon tetrachloride (CCl 4 ) has been used extensively in the nuclear weapons industry, so it is likely that nuclear plant workers have been exposed to both CCl 4 and plutonium compounds. Future exposures may occur during open-quotes cleanupclose quotes operations at weapons productions sites such as the Hanford, Washington, and Rocky Flats, Colorado, facilities. Inhalation of 20 and 100 ppm CCl 4 by hamsters reduces uptake of 239 Pu solubilized from lung, shunting the 239 Pu to the skeleton

  10. Neutron scattering studies in the actinide region

    International Nuclear Information System (INIS)

    Beghian, L.E.; Kegel, G.H.R.

    1991-08-01

    During the report period we have investigated the following areas: Neutron elastic and inelastic scattering measurements on 14 N, 181 Ta, 232 Th, 238 U and 239 Pu; Prompt fission spectra for 232 Th, 235 U, 238 U and 239 Pu; Theoretical studies of neutron scattering; Neutron filters; New detector systems; and Upgrading of neutron target assembly, data acquisition system, and accelerator/beam-line apparatus

  11. Nondestructive assay instrument for measurement of plutonium in solutions

    International Nuclear Information System (INIS)

    Shirk, D.G.; Hsue, F.; Li, T.K.; Canada, T.R.

    1979-01-01

    A nondestructive assay (NDA) instrument that measures the 239 Pu content in solutions, using a passive gamma-ray spectroscopy technique, has been developed and installed in the LASL Plutonium Processing Facility. A detailed evaluation of this instrument has been performed. The results show that the instrument can routinely determine 239 Pu concentrations of 1 to 500 g/l with accuracies of 1 to 5% and assay times of 1 to 2 x 10 3 s

  12. Biological behavior of mixed LMFBR-fuel-sodium aerosols

    International Nuclear Information System (INIS)

    Mahlum, D.D.; Hackett, P.L.; Hess, J.O.; Allen, M.D.

    1979-01-01

    Immediately after exposure of rats to mixed aerosols of sodium-LMFBR fuel, about 80 to 90% of the body burden of 239 Pu is in the gastrointestinal tract; 1.5 to 4% is in the lungs. With fuel-only aerosols, less of the body burden was in the GI tract and more in the lung and the head. Blood and urine values suggest an increased absorption of 239 Pu from sodium-fuel than from fuel-only aerosols

  13. Dose-effect studies with inhaled plutonium in beagles

    International Nuclear Information System (INIS)

    Anon.

    1982-01-01

    Data are presented for all dogs employed in current life-span dose effect studies with inhaled 239 PuO 2 , and 239 Pu nitrate. Information is presented on the estimated initial alveolar deposition, based on external thorax counts and on estimated lung weights at time of exposure. Information is also provided on the current interpretation of the most prominent clinical-pathological features associated with the death of animals

  14. Biological behaviour of plutonium given as a trilaurylamine complex. Comparison with plutonium-tributylphosphate

    International Nuclear Information System (INIS)

    Nolibe, D.; Duserre, C.; Gil, I.; Rateau, G.; Metivier, H.

    1989-01-01

    The biokinetics of plutonium (Pu) were compared in rats after its administration by inhalation or intramuscular injection as Pu-trilaurylamine (Pu-TLA) or Pu-tri-n-butylphosphate (Pu-TBP). To study the mass effect, 238 Pu and 239 Pu were used. Translocation from the lungs and injection site was faster for 238 Pu than 239 Pu, and faster for Pu-TLA than Pu-TBP. The skeleton was always the main organ of deposition of the transferable Pu fraction. At 50 days after inhalation, the skeletal content, in per cent of the body content at death was 10% for 239 Pu-TBP, 54% for 238 Pu-TBP, 24% for 239 Pu-TLA and 62% for 238 Pu-TLA. The amounts in the liver were respectively 2, 6, 3, and 10% of the body content. Thirty days after intramuscular injection of 239 Pu-TLA, more Pu was translocated than after 239 Pu-TBP (26% versus 16%) and the skeletal deposit was 10 times the deposit in the liver. DTPA therapy after inhalation or injection of 238 Pu-TLA reduced the skeletal content by 35-58% with a corresponding increase in urinary excretion. (author)

  15. Toxicity ratios: Their use and abuse in predicting the risk from induced cancer

    International Nuclear Information System (INIS)

    Mays, C.W.; Taylor, G.N.; Lloyd, R.D.

    1986-01-01

    The toxicity ratio concept assumes the validity of certain relationships. In some examples for bone sarcoma induction, the approximate toxicity of 239 Pu in man can be calculated algebraically from the observed toxicity in the radium-dial painters and the ratio of 239 Pu/ 226 Ra toxicities in suitable laboratory mammals. In a species highly susceptible to bone sarcoma induction, the risk coefficients for both 239 Pu and 226 Ra are elevated, but the toxicity ratio of 239 Pu to 226 Ra tends to be similar to the ratio in resistant species. Among the tested species the toxicity ratio of 239 Pu to 226 Ra ranged from 6 to 22 (a fourfold range), whereas their relative sensitivities to 239 Pu varied by a factor of 150. The toxicity ratio approach can also be used to estimate the actinide risk to man from liver cancer, by comparing to the Thorotrast patients; from lung cancer, by comparing to the uranium miners and the atomic-bomb survivors; and from neutron-induced cancers, by comparing to cancers induced by gamma rays. The toxicity ratio can be used to predict the risk to man from a specific type of cancer that has been reliably induced by a reference radiation in humans and that can be induced by both the reference and the investigated radiation in suitable laboratory animals. 26 refs., 3 figs., 1 tab

  16. Hematologic effects of inhaled plutonium in beagles

    International Nuclear Information System (INIS)

    Ragan, H.A.; Buschbom, R.L.; Park, J.F.; Dagle, G.E.; Weller, R.E.

    1986-01-01

    Beagle dogs were exposed, by inhalation, 5 to 11 years ago, to aerosols of 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 , at six dose levels resulting in initial lung burdens ranging from ∼2 to ∼5500 nCi. Translocation of the plutonium to extrapulmonary sites was related to the physical-chemical characteristics of the plutonium compound. The highly insoluble 239 PuO 2 was retained primarily in the lung and associated lymph nodes, whereas 239 Pu(NO 3 ) 4 was much more soluble and translocated relatively rapidly to the skeleton and other extrapulmonary tissues. The 238 PuO 2 was intermediate in solubility and translocation characteristics. The hematologic effects of plutonium inhalation were most pronounced on lymphocyte populations. Evidence suggests that these effects result from irradiation of lymphocytes via the pulmonary lymph nodes with insoluble 239 PuO 2 , and via these same lymph nodes, extrapulmonary lymph nodes, and bone marrow lymphocytes with the more soluble forms, i.e., 238 PuO 2 and 239 Pu(NO 3 ) 4 . There is no evidence suggesting that these exposures increase the risk of developing myeloid or lymphoid neoplasia. 8 refs., 4 figs., 3 tabs

  17. Izotopová frakcionace vody v systému půda-rostlina-atmosféra a její využití ve fyziologii a ekologii rostlin

    Czech Academy of Sciences Publication Activity Database

    Šantrůček, Jiří

    2007-01-01

    Roč. 7, č. 2 (2007), s. 24 [Konference experimentální biologie rostlin, 11. dny fyziologie rostlin. 09.07.2007-12.07.2007, Olomouc] R&D Projects: GA AV ČR(CZ) IAA601410505 Institutional research plan: CEZ:AV0Z50510513 Keywords : plant physiology * Isotope fractionation Subject RIV: ED - Physiology

  18. The analysis study of plutonium in the environmental sample by mass spectrum combined with isotopic dilution

    International Nuclear Information System (INIS)

    Han Jun; Fu Zhonghua; Mao Xingen; Meng Fanben

    2004-01-01

    The technology of the rhenium filament carbonization was used to increase the ionization efficiency in this paper. The plutonium in the environmental sample was analyzed by Mass Spectrum combined with isotope dilution. Analysis of the 239 Pu blank in the process: The analysis of 239 Pu from the chemical process was carried out in order to establish the influence of the 239 Pu introduced from the process. The analysis results were shown in Table 1 sample 1 was not gone through the process, sample 2 and sample 3 were gone through the process. It was clear that there was no influence of the 239 Pu from the process within the deviation. Results and Discussions: The environmental samples which were dealed with the chemical method were prepared the sample of mass spectrum, The atomic ratio of the 239 Pu and 242 Pu in the environmental samples was measured by Mass Spectrum. The atomic ratio in the tracer 242 Pu was 0.01476±0.00007.The results for nuclide content in environment were given in Table 2. The content of 239 Pu in the tracer was high, so the existing of 239 Pu in the environmental samples can be determined by the changing of the atomic ratio of 242 Pu to 239 Pu. It was clear that there was 239 Pu in the environmental samples except the cypress leaves-2 and the pine leaves-3 within the deviation, and the content of 239 Pu were given in Table 2. Conclusion: a. Plutonium was separated and purified from the impurity by the anion-exchange and the electrodeposition, it was possible to provide the eligible mass spectrum sample. b. The measurement of plutonium in the environmental samples was not influenced by the flow of the background in the experiment. c. As the technology of the rhenium carbonization was used to increase the ionization efficiency, the content of plutonium which was about 10 -13 g in the environmental sample could be quantitatively analyzed by Mass Spectrum combined with isotope dilution. (authors)

  19. Influence of fuel composition on the spent fuel verification by Self‑Interrogation Neutron Resonance Densitometry

    International Nuclear Information System (INIS)

    Rossa, Riccardo; Borella, Alessandro; Van der Meer, Klaas; Labeau, Pierre‑Etienne; Pauly, Nicolas

    2015-01-01

    The Self‑Interrogation Neutron Resonance Densitometry (SINRD) is a passive Non‑Destructive Assay (NDA) that is developed for the safeguards verification of spent nuclear fuel. The main goal of SINRD is the direct quantification of 239Pu by estimating the SINRD signature, which is the ratio between the neutron flux in the fast energy region and in the region close to the 0.3 eV resonance of 239 Pu. The resonance region was chosen because the reduction of the neutron flux within 0.2-0.4 eV is due mainly to neutron absorption from 239 Pu, and therefore the SINRD signature can be correlated to the 239Pu mass in the fuel assembly. This work provides an estimate of the influence of 239 Pu and other nuclides on the SINRD signature. This assessment is performed by Monte Carlo simulations by introducing several nuclides in the fuel material composition and by calculating the SINRD signature for each case. The reference spent fuel library developed by SCK CEN was used for the detailed fuel compositions of PWR 17x17 fuel assemblies with different initial enrichments, burnup, and cooling times. The results from the simulations show that the SINRD signature is mainly correlated to the 239 Pu mass, with significant influence by 235 U. Moreover, the SINRD technique is largely insensitive to the cooling time of the assembly, while it is affected by the burnup and initial enrichment of the fuel. Apart from 239 Pu and 235 U, many other nuclides give minor contributions to the SINRD signature, especially at burnup higher than 20 GWd/tHM.

  20. Multimedia contaminant environmental exposure assessment methodology as applied to Los Alamos, New Mexico

    International Nuclear Information System (INIS)

    Whelan, G.; Thompson, F.L.; Yabusaki, S.B.

    1983-02-01

    The MCEA (Multimedia Contaminant Environmental Exposure Assessment) methodology assesses exposures to air, water, soil, and plants from contaminants released into the environment by simulating dominant mechanisms of contaminant migration and fate. The methodology encompasses five different pathways (i.e., atmospheric, terrestrial, overland, subsurface, and surface water) and combines them into a highly flexible tool. The flexibility of the MCEA methodology is demonstrated by encompassing two of the pathways (i.e., overland and surface water) into an effective tool for simulating the migration and fate of radionuclides released into the Los Alamos, New Mexico region. The study revealed that: (a) the 239 Pu inventory in lower Los Alamos Canyon increased by approximately 1.1 times for the 50-y flood event; (b) the average contaminant 239 Pu concentrations (i.e., weighted according to the depth of the respective bed layer) in lower Los Alamos Canyon for the 50-y flood event decreased by 5.4%; (c) approx. 27% of the total 239 Pu contamination resuspended from the entire bed (based on the assumed cross sections) for the 50-y flood event originated from lower Pueblo Canyon; (d) an increase in the 239 Pu contamination of the bed followed the general deposition patterns experienced by the sediment in Pueblo-lower Los Alamos Canyon; likewise, a decrease in the 239 Pu contamination of the bed followed general sediment resuspension patterns in the canyon; (e) 55% of the 239 Pu reaching the San Ildefonso Pueblo in lower Los Alamos Canyon originated from lower Los Alamos Canyon; and (f) 56% of the 239 Pu contamination reaching the San Ildefonso Pueblo in lower Los Alamos Canyon was carried through towards the Rio Grande. 47 references, 41 figures, 29 tables

  1. Distribution and removal of transuranic elements and cerium deposited by the inhalation route; Distribution et elimination des transuraniens et du cerium deposes par l'intermediaire des voies respiratoires; Raspredelenie transuranovykh ehlementov i tseriya, otkladyvayushchikhsya v rezul'tate vdykhaniya i ikh udalenie; Distribucion y eliminacion de elementos transuranicos y de cerio depositados por inhalacion

    Energy Technology Data Exchange (ETDEWEB)

    Bair, W. J.; Tombropoulos, E. G.; Park, J. F. [Hanford Atomic Products Operation, General Electric Company, Richland, WA (United States)

    1963-02-15

    forme chimique et les dimensions des particules des aerosols. Chez les chiens, 30 jours apres inhalation de nitrate de plutonium, 70% de la charge corporelle se trouvaient dans les poumons, 10% dans le foie et 15% dans le squelette. Apres inhalation d'aerosols de {sup 239}PuO{sub 2} ayant un diametre moyen de 0,12 {mu}, 71% de la charge corporelle se trouvaient dans les poumons, 3% dans les ganglions lymphatiques des bronches, 4,4% dans les muscles et 1,3% dans le squelette, tandis que 20% etaient distribues d'une maniere uniforme dans tous les autres tissus. Apres inhalation d'aerosols de {sup 239}PuO{sub 2} ayant un diametre moyen compris entre 0,3 et 0,6 {mu}, 98% etaient contenus dans les poumons, 1% environ dans les ganglions lymphatiques des bronches et 1% dans tous les autres tissus. Ces donnees ainsi que l'analyse de l'urine et des feces ont permis de definir l'importance relative des trois voies par lesquelles les radioisotopes inhales etaient evacues des poumons : mouvement ascendant dans la trachee par action ciliaire suivie d'excretion dans les feces, transporta travers la membrane alveolaire avec redistribution dans d'autres tissus et excretion graduelle dans l'urine, transfert aux ganglions lymphatiques des bronches ou sont accumulees les matieres insolubles inhalees. On a etudie divers agents therapeutiques qui pourraient favoriser l'evacuation des radioisotopes contenus dans les poumons par des voies qui eviteraient leur accumulation dans d'autres tissus, peut-etre plus radiosensibles. Parmi ces agents, il convient de citer les agents de chelation et d' humidification, les irritants, les sympathicomimetiques, les parasympathicomimetiques, les parasympathicolytiques et les antihistamines. L'acide diethylene-triamine penta-acetique (agent de chelation) administre en aerosols ou par voie intraperitoneale a rapidement elim ine, par excretion urinaire, le {sup 144}Ce-{sup 144}Pr des poumons et de l'organisme tout entier. Un mois apres avoir ete exposes a {sup

  2. Life-span studies of inhaled plutonium in beagle dogs

    International Nuclear Information System (INIS)

    Bair, W.J.

    1991-01-01

    In 1970 a life-span study with over 300 beagle dogs was begun. Groups of beagle dogs were given single exposures to 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 to obtain graded levels of initial lung burdens ranging from 1 to 1800 Bq lung. After 16 years, the lungs contained about 2% of the initial lung burden of 239 PuO 2 , the thoracic lymph nodes 20%, skeleton 1% and liver 10%. After 15 years the lungs contained about 0.2% of the initial lung burden of 238 PuO 2 , thoracic lymph nodes 5%, skeleton 10%, and liver 10%. After 10 years the lungs contained about 0.29% of the initial lung burden of 239 Pu(NO 3 ) 4 , thoracic lymph nodes 0.17%, skeleton 18% and liver 13%. Chronic lymphopenia has been one of the earliest biological effects observed. Other effects associated with plutonium exposure included sclerosis of the tracheobronchial lymph nodes, focal radiation pneumonitis, adenomatous hyperplasia of the liver and dystrophic osteolytic lesions in the skeleton. In 16 years, mortality due to radiation pneumonitis and/or lung tumor increased with deposition of 24 Bq of 239 PuO 2 . In 15 years, mortality due to lung and/or bone tumors increased with deposition of 96 Bq of 238 PuO 2 . In 11 years, after exposure, mortality due to lung and/or bone tumors increased with deposition of 18 Bq of 239 Pu(NO 3 ) 4 . Lung cancers appeared to originate in the parenchymal regions of the lungs and were of several types; bronchiolar alveolar carcinoma, papillary adenocarcinomas, adenosquamous carcinoma, and epidermoid carcinoma. Metastases were primarily to the thoracic lymph nodes. Sites of osteosarcomas in the 238 PuO 2 and 239 Pu(NO 3 ) 4 dogs were in the lumbar cervical and thoracic vertebrae, humerus, pelvis, facial bones, ribs and nasal turbinates. The risk of lung cancer, based on cumulative dose to the lungs, was about 12 times higher for 239 Pu(NO 3 ) 4 than from inhaled 239 PuO 2 , and 50 times higher than for inhaled 238 PuO 2 . (J.P.N.)

  3. Plutonium and cesium radionuclides in the Hudson River estuary. Annual technical progress report, December 1, 1976--November 30, 1977

    International Nuclear Information System (INIS)

    Simpson, H.J.; Trier, R.M.

    1977-01-01

    We have obtained a large set of sediment cores from the Hudson estuary through much of the ambient salinity range. A number of core sections and samples of suspended particles have been analyzed for 137 Cs, 134 Cs and 60 Co by direct gamma counting, and 239 Pu, 240 Pu, and 238 Pu by alpha spectrometry. The distribution of both 137 Cs and 239 Pu, 240 Pu indicates rapid accumulation in marginal cover areas, and especially in the harbor region adjacent to New York City. The distributions of both 137 Cs and 239 Pu, 240 Pu are similar in surface sediments and with depth in cores, but there are deviations from the fallout ratio due to addition of reactor 137 Cs and loss of 137 Cs from the particle phases at higher salinities. Measureable amounts of reactor-derived 134 Cs and 60 Co are found in nearly all sediment samples containing appreciable 137 Cs, between 15 km upstream of Indian Point and the downstream extent of our sampling, 70 km south of the reactor. Accumulations of 239 Pu, 240 Pu in New York harbor sediments are more than an order of magnitude greater than the fallout delivery rate. The most likely explanation is accumulation of fine particles in the harbor which have been transported from upstream areas of the Hudson. Our evidence so far indicates that Indian Point is probably not a significant source of 239 Pu, 240 Pu or 238 Pu compared with the fallout burden of these nuclides already in the sediments

  4. Plutonium measurements in Hanford DOE site waste samples

    International Nuclear Information System (INIS)

    Dewberry, R.A.; Boyce, W.T.

    1999-01-01

    Development work to prepare a method to measure absolute 239 Pu content and Pu-isotopics by ICP-MS in acidified Hanford DOE-site samples which are very high in 90 Sr, 99 Tc, and 137 Cs radioactivity and which are frequently high in organic carbon content is described. Samples with very large 90 Sr and 137 Cs contents have historically been difficult to analyze for Pu content by each of three alpha-counting techniques in use at SRS, and analysis by ICP-MS in these samples is complicated by the high organics content. An ion exchange chemical preparation is reported to obtain fraction of Pu that does not contain any fission product contribution and no interfering organics to allow measure of absolute 239 Pu and of 239 Pu through 241 Pu isotopics by ICP-MS. The method uses a 242 Pu spike to measure Pu recovery and is demonstrated in this paper with three distinct commercially available resins and with over 300 samples. Measured absolute 239 Pu contents in sixty-three spiked/unspiked duplicates have agreed within 15% precision. Overall 242 Pu recoveries were near 90% with 25% precision. Comparisons of absolute 239 Pu contents measured directly on three samples agreed within the quoted 25% uncertainty. (author)

  5. An intercomparison experiment on isotope dilution thermal ionisation mass spectrometry using plutonium-239 spike for the determination of plutonium concentration in dissolver solution of irradiated fuel

    International Nuclear Information System (INIS)

    Aggarwal, S.K.; Shah, P.M.; Saxena, M.K.; Jain, H.C.; Gurba, P.B.; Babbar, R.K.; Udagatti, S.V.; Moorthy, A.D.; Singh, R.K.; Bajpai, D.D.

    1996-01-01

    Determination of plutonium concentration in the dissolver solution of irradiated fuel is one of the key measurements in the nuclear fuel cycle. This report presents the results of an intercomparison experiment performed between Fuel Chemistry Division (FCD) at BARC and PREFRE, Tarapur for determining plutonium concentration in dissolver solution of irradiated fuel using 239 Pu spike in isotope dilution thermal ionisation mass spectrometry (ID-TIMS). The 239 Pu spike method was previously established at FCD as viable alternative to the imported enriched 242 Pu or 244 Pu; the spike used internationally for plutonium concentration determination by IDMS in dissolver solution of irradiated fuel. Precision and accuracy achievable for determining plutonium concentration are compared under the laboratory and the plant conditions using 239 Pu spike in IDMS. For this purpose, two different dissolver solutions with 240 Pu/ 239 Pu atom ratios of about 0.3 and 0.07 corresponding, respectively, to high and low burn-up fuels, were used. The results of the intercomparison experiment demonstrate that there is no difference in the precision values obtained under the laboratory and the plant conditions; with mean precision values of better than 0.2%. Further, the plutonium concentration values determined by the two laboratories agreed within 0.3%. This exercise, therefore, demonstrates that ID-TIMS method using 239 Pu spike can be used for determining plutonium concentration in dissolver solution of irradiated fuel, under the plant conditions. 7 refs., 8 tabs

  6. Possible differences in biological availability of isotopes of plutonium: Report of a workshop

    International Nuclear Information System (INIS)

    Kercher, J.R.; Gallegos, G.M.

    1993-09-01

    This paper presents the results of a workshop conducted on the apparent different bioavailability of isotopes 238 Pu and 239 Pu. There is a substantial body of evidence that 238 Pu as commonly found in the environment is more biologically available than 239 Pu. Studies of the Trinity Site, Nevada Test Site from nonnuclear and nuclear events, Rocky Flats, Enewetak and Bikini, and the arctic tundra support this conclusion and indicate that the bioavailability of 238 Pu is more than an order of magnitude greater than that of 239 Pu. Plant and soil studies from controlled environments and from Savannah River indicate no isotopic difference in availability of Pu to plants; whereas studies at the Trinity Site do suggest a difference. While it is possible that these observations can be explained by problems in the experimental procedure and analytical techniques, this possibility is remote given the ubiquitous nature of the observations. Studies of solubility of Pu in the stomach contents of cattle grazing at the Nevada Test Site and from fish from Bikini Atoll both found that 238 Pu was more soluble than 239 Pu. Studies of the Los Alamos effluent stream indicate that as particle size decreases, the content of 238 Pu relative to 239 Pu increases

  7. Possible differences in biological availability of isotopes of plutonium: Report of a workshop

    Energy Technology Data Exchange (ETDEWEB)

    Kercher, J.R.; Gallegos, G.M. [eds.

    1993-09-01

    This paper presents the results of a workshop conducted on the apparent different bioavailability of isotopes {sup 238}Pu and {sup 239}Pu. There is a substantial body of evidence that {sup 238}Pu as commonly found in the environment is more biologically available than {sup 239}Pu. Studies of the Trinity Site, Nevada Test Site from nonnuclear and nuclear events, Rocky Flats, Enewetak and Bikini, and the arctic tundra support this conclusion and indicate that the bioavailability of {sup 238}Pu is more than an order of magnitude greater than that of {sup 239}Pu. Plant and soil studies from controlled environments and from Savannah River indicate no isotopic difference in availability of Pu to plants; whereas studies at the Trinity Site do suggest a difference. While it is possible that these observations can be explained by problems in the experimental procedure and analytical techniques, this possibility is remote given the ubiquitous nature of the observations. Studies of solubility of Pu in the stomach contents of cattle grazing at the Nevada Test Site and from fish from Bikini Atoll both found that {sup 238}Pu was more soluble than {sup 239}Pu. Studies of the Los Alamos effluent stream indicate that as particle size decreases, the content of {sup 238}Pu relative to {sup 239}Pu increases.

  8. NKS-Norcmass reference material for analysis of Pu-isotopes and 237Np by mass spectrometry

    International Nuclear Information System (INIS)

    Ross, P.; Nygren, U.; Appelblad, P.; Skipperud, L.; Sjoegren, A.

    2006-04-01

    The aim of the reference material in the Norcmass-project was to produce a low-level ( 239 Pu) sample of sufficient amount to allow individual laboratories to perform several tests without risk of using up the material. Although there are several reference materials available (eg IAEA) few have 239 Pu/ 240 Pu data and almost none have 237 Np/ 239 Pu-data. Those who have (eg IAEA-384) have very high concentrations and are not useful for testing analytical methods designed for low-level measurements where a large sample mass may be required. The reference material consist of the top 10cm of 2mm sieved soil pooled together from 12 different Danish locations collected during 2003. The Soil was blended and sieved through 0.6 and finally through a 0.4 mm sieve. A total amount of 17 kg soil was produced. Several aliquots of the material was subject to analysis by alpha spectrometry and ICP-MS. The material contain 239 + 240 Pu at a concentration of 0.24 ± 0.01 mBq/g and a 240 Pu/ 239 Pu atom ratio of 0.19 ± 0.006. The ratio 237 Np/ 239 Pu was determined to 0.32 ± 0.01. (au)

  9. Performance characteristics of a Bioassay method for plutonium using thermal ionisation mass spectrometry (TIMS)

    Energy Technology Data Exchange (ETDEWEB)

    Linauskas, S.H.; Elliot, N.L.; Paterson, L.M.; Totland, M.M

    2003-01-01

    Plutonium-in-urine analysis by radiochemical isolation of Pu followed by thermal ionisation mass spectrometry (TIMS) is capable of high sensitivity and precision measurements {sup 239}Pu and {sup 240}Pu. Bias and precision estimates for the TIMS bioassay program at Chalk River Laboratories easily met the ANSI N13.30 performance criteria standards with {sup 239}Pu results of 1.5% and 3.0%, respectively. Analytical blanks derived from water, artificial urine and true urine samples did not produce any statistically different results. During a four-year period of development and implementation of {sup 239}Pu measurements by TIMS, average sample blank values were reduced from 3.9 fg (9.0 {mu}Bq) to 0.57 fg (1.3 {mu}Bq). This reduction was achieved through rigorous application of clean-room handling techniques throughout sample processing. Blank data were found to follow a Iognormal distribution, and current detection limit parameters for L{sub c} and L{sub d} at the 95% significance levels are 0.85 fg {sup 239}Pu (2.0 {mu}Bq) and 1.3 fg {sup 239}Pu (3.0 {mu}Bq), respectively. Detection limits in this range are expected to be sufficient to identify intakes of Pu/Am mixtures at levels that are around one-twentieth of an ALl or better under routine monitoring situations for ICRP Type S and Type M inhalation solubility classes. (author)

  10. Effect of the plutonium isotopic composition on the performance of fast reactors; Effet de la composition isotopique du plutonium sur le rendement de reacteurs a neutrons rapides; Vliyanie izotopnogo sostava plutoniya na rabotu reaktorov na bystrykh nejtronakh; Efectos de la composicion isotopica del plutonio sobre el funcionamiento de los reactores rapidos

    Energy Technology Data Exchange (ETDEWEB)

    Yiftah, S [Israel Atomic Energy Commission (Israel)

    1962-03-15

    fisionables por neutrones termicos ({sup 239}Pu y {sup 241}Pu), cuanto mas impuro sea el plutonio, tanto menor sera la masa critica y mayor la razon de reproduccion. Tomando como ejemplo el reactor de 1500 l, se comprobo ademas que al eliminar un 40 por ciento del sodio inicialmente presente en el cuerpo, la variacion de reactividad tiende a ser negativa a medida que aumenta la proporcion de isotopos superiores contenidos en el combustible de plutonio (en forma de metal, oxido o carburo). (author) [Russian] Izotopnyj sostav plutoniya, kotoryj dolzhen ispol'zovat'sya v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh, budet zaviset' ot istochnika polucheniya plutoniya. V printsipe vozmozhny tri razlichnykh istochnika: a) proizvodyashchie reaktory; b) teplovye ehnergeticheskie reaktory (ispol'zuyushchie v kachestve topliva estestvennyj ili obogashchennyj uran); c) zony vosproizvodstv a reaktora na bystrykh nejtronakh. V osnovnom istochnik (a) i v nekotorom otnoshenii istochnik (s) budut davat' sravnitel'no 'chistyj' plutonij, t.e. glavnym obrazom plutonij-239, togda kak plutonij iz istochnika (b) budet 'gryaznym', t.e. plutoniem, bogatym izotopami plutoniya-240, plutoniya-241 i plutoniya-242. Stepen' 'zagryazneniya' budet zaviset' ot tipa reaktora, velichiny vygoraniya i voobshche ot istorii oblucheniya topliva. V takom sluchae voznikaet vopros, mozhno li ispol'zovat' v kachestve goryuchego dlya reaktorov na bystrykh nejtronakh lyubye vidy plutoniya. Dlya izucheniya vliyaniya razlichnogo izotopnogo sostava plutonievogo topliva v metallicheskom, oksidnom i karbidnom vide na rabotu reaktorov na bystrykh nejtronakh byli osushchestvleny ogranichennye serii podschetov po 16-gruppovoj diffuzionnoj teorii sfericheskoj geometrii s pomoshch'yu 16-gruppovogo komplekta poperechnykh sechenij, razrabotannogo nedavno Iftakhom, Okrentom i Mol'dauerom s ispol'zovaniem trekh razlichnykh vidov plutoniya, nachinaya s chistogo plutoniya-239 i povyshaya kolichestvo bolee vysokikh izotopov

  11. Study on the ICP-MS technology of trace uranium and plutonium in environmental water

    International Nuclear Information System (INIS)

    Zeng Min; Tian Junhua; Li Ye

    2006-10-01

    The method of detecting U and 239 Pu of the water in the environment was founded. 100 L water of river, reservoir and tap water were respectively sampled. The concentration of 239 Pu was analyzed by ICP-MS after the treatment by coprecipitation-anion exchange, the detection limit was 0.06 ng/L. Standard fitting curve and internal standard method was used to quantity, the result showed that the concentration of 239 Pu of the water of river, tap water was below the detection limit, the concentration of the water of reservoir was 10-14 g/L; all of the water were directly filtrated then detected by ICP-MS, the concentration of U of all the water was 0.5-1 μg/L. (authors)

  12. Transport and scavenging of Pu in surface waters of the Southern Hemisphere Oceans

    DEFF Research Database (Denmark)

    Gastaud, J.; Povinec, P.P.; Aoyama, M.

    2011-01-01

    The distribution of 239Pu in Atlantic and Indian Ocean waters about four decades after their main injection from atmospheric nuclear weapons tests is discussed. Recent data obtained in the framework of the SHOTS (Southern Hemisphere Ocean Tracer Studies) projects are evaluated and compared...... with previous investigations. Seawater samples were collected during the round the globe BEAGLE2003 (Blue Ocean Global Expedition) along the 30°S transect in the Atlantic and the 20°S transect in the Indian Ocean. The results indicate transport of surface waters labelled with 239Pu from the western North...... Pacific via the Indonesian Seas to the South Indian Ocean and then to the South Atlantic Ocean. Along the whole BEAGLE2003 sampling route, the Atlantic Ocean has the lowest 239Pu content due to its particle scavenging on the long way from the western North Pacific. On the other hand, concentrations...

  13. Effects of combined exposure of F344 rats to radiation and chronically inhaled cigarette smoke

    Energy Technology Data Exchange (ETDEWEB)

    Finch, G.L.; Nikula, K.J.; Barr, E.B. [and others

    1995-12-01

    Nuclear workers may be exposed to radiation in various forms, such as low-LET {gamma}-irradiation or {alpha}-irradiation from inhaled {sup 239}PuO{sub 2} particles. These workers may then have increased risk for lung cancer compared to the general population. Of additional concern is the possibility that interactions between radiation and other carcinogens may increase the risk of cancer induction, compared to the risks from either type of agent alone. An important and common lung carcinogen is cigarette smoke. The purpose of this project is to better determine the combined effects of chronically inhaled cigarette smoke and either inhaled {sup 239}PuO{sub 2} or external, thoracic X-irradiation on the induction of lung cancer in rats. Histologic and dosimetric evaluations of rats in the CS + {sup 239}PuO{sub 2} study continue, and the study of CS + X rays is beginning.

  14. The effect of isotope on the dosimetry of inhaled plutonium oxide

    International Nuclear Information System (INIS)

    Guilmette, R.A.; Griffith, W.C.

    1991-01-01

    Results of experimental studies in which animals inhaled 238 PuO 2 or 239 PuO 2 aerosols have shown that the biokinetics and associated radiation dose patterns for these two isotopes differ significantly due to differences in in-vivo solubility caused by the 260-fold difference in specific activity between 238 PuO 2 and 239 PuO 2 . We have adapted a biokinetics and dosimetry model derived from results of the ITRI dog studies to humans and have calculated dose commitments and annual limits on intake (ALI) for both Pu isotopes. Our results show that the ALI calculated in this study is one-third that for class Y 238 Pu from ICRP 30, and one-half or equal to that for class Y 239 Pu, depending on how activity in the thoracic lymph nodes is treated dosimetrically

  15. Assessment of Degree of Applicability of Benchmarks for Gadolinium Using KENO V.a and the 238-Group SCALE Cross-Section Library

    Energy Technology Data Exchange (ETDEWEB)

    Goluoglu, S.

    2003-12-01

    A review of the degree of applicability of benchmarks containing gadolinium using the computer code KENO V.a and the gadolinium cross sections from the 238-group SCALE cross-section library has been performed for a system that contains {sup 239}Pu, H{sub 2}O, and Gd{sub 2}O{sub 3}. The system (practical problem) is a water-reflected spherical mixture that represents a dry-out condition on the bottom of a sludge receipt and adjustment tank around steam coils. Due to variability of the mixture volume and the H/{sup 239}Pu ratio, approximations to the practical problem, referred to as applications, have been made to envelop possible ranges of mixture volumes and H/{sup 239}Pu ratios. A newly developed methodology has been applied to determine the degree of applicability of benchmarks as well as the penalty that should be added to the safety margin due to insufficient benchmarks.

  16. Effects of combined exposure of F344 rats to radiation and chronically inhaled cigarette smoke

    International Nuclear Information System (INIS)

    Finch, G.L.; Nikula, K.J.; Barr, E.B.

    1995-01-01

    Nuclear workers may be exposed to radiation in various forms, such as low-LET γ-irradiation or α-irradiation from inhaled 239 PuO 2 particles. These workers may then have increased risk for lung cancer compared to the general population. Of additional concern is the possibility that interactions between radiation and other carcinogens may increase the risk of cancer induction, compared to the risks from either type of agent alone. An important and common lung carcinogen is cigarette smoke. The purpose of this project is to better determine the combined effects of chronically inhaled cigarette smoke and either inhaled 239 PuO 2 or external, thoracic X-irradiation on the induction of lung cancer in rats. Histologic and dosimetric evaluations of rats in the CS + 239 PuO 2 study continue, and the study of CS + X rays is beginning

  17. Dose-effect studies with inhaled plutonium oxide in beagles

    International Nuclear Information System (INIS)

    Park, J.F.; Buschbom, R.L.; Case, A.C.

    1976-01-01

    Beagle dogs given single exposure to 239 PuO 2 or 238 PuO 2 aerosols are being observed for life-span dose-effect relationships. The 239 Pu body burden of the nine dogs dying due to pulmonary fibrosis-induced insufficiency during the first 3 years after exposure was 1 to 12 μCi. One of these dogs had a pulmonary tumor. Three additional dogs with body burdens of 0.7 to 1.8 μCi died due to pulmonary neoplasia 4-1/2 years after exposure. None of the dogs exposed to 238 Pu have died during the first two postexposure years. After inhalation of 239 PuO 2 or 238 PuO 2 lymphocytopenia was the earliest observed effect, occuring 0.5 to 2 years after deposition of greater than or equal to 80 nCi plutonium in the lungs

  18. Radiation factors and smoking interaction at lung cancer incidence for workers at a nuclear enterprise

    International Nuclear Information System (INIS)

    Tokarskaya, Z.B.; Khokhryakov, V.T.; Okladnikova, N.D.; Belyaeva, Z.D.; Zhuntova, G.V.; Fleck, C.M.; Schollnberger, H.; Drozhko, E.G.

    1998-01-01

    A study is reported which is a continuation of a previous investigation of lung cancer incidence in workers at a nuclear enterprise and its relation to three basic etiological factors: the body burden due to 239 Pu, chronic external gamma irradiation, and smoking. Whereas previously each of the factors was assessed separately, in the present study the attempt was made to assess the interaction of the factors. A statistical analysis of the data revealed that for the following pairs of factors a superposition effect could be seen: external gamma irradiation and 239 Pu body burden; external gamma irradiation and a medium level of smoking; and 239 Pu body burden and a medium level of smoking. (A.K.)

  19. Feasibility study of plutonium isotopic analysis of resin beads by nondestructive gamma-ray spectroscopy

    International Nuclear Information System (INIS)

    Li, T.K.

    1985-01-01

    We have initiated a feasibility study on the use of nondestructive low-energy gamma-ray spectroscopy for plutonium isotopic analysis on resin beads. Seven resin bead samples were measured, with each sample containing an average of 9 μg of plutonium; the isotopic compositions of the samples varied over a wide range. The gamma-ray spectroscopy results, obtained from 4-h counting-time measurements, were compared with mass spectrometry results. The average ratios of gamma-ray spectroscopy to mass spectrometry were 1.014 +- 0.025 for 238 Pu/ 239 Pu, 0.996 +- 0.018 for 240 Pu/ 239 Pu, and 0.980 +- 0.038 for 241 Pu/ 239 Pu. The rapid, automated, and accurate nondestructive isotopic analysis of resin beads may be very useful to process technicians and International Atomic Energy Agency inspectors. 3 refs., 1 fig., 3 tabs

  20. Study of a dosimetric methodology for plutonium by means of radiotonicological analysis in urine

    International Nuclear Information System (INIS)

    Bellintani, S.A.

    1988-01-01

    The present study is mainly concerned with an internal individual monitoring program for workers dealing with 239 Pu, by measuring the 239 Pu content in their urine. General aspects related with the plutonium radiotoxicity and its chemical, physical and metabolic properties are discussed. The methodology chosen for the 239 Pu analyses in urine is based on the wet ashing of the urine sample, followed by the plutonium separation by precipitation with lanthanium nitrate and extraction with thenoyltrifluoroacetone. After the separation, the samples is electrodeposited and the activity measured by alpha spectrometry. The results were then analyzed by taking into account the couting efficiency obtained of 23.72%, the chemical recovery of 85.3% and the lower limit of detection of 1.1 x 10 -3 Bq. Finally, the bases for the establishment of reference levels for urinary excretion are discussed by considering the maximum permissible body burden (MPBB) and the annual limit of intake (ALI). (author) [pt

  1. Final Task Report on NRF Measurements of Photon Scattering Resonances in Plutonium at the High Voltage Research Laboratory of MIT

    International Nuclear Information System (INIS)

    Johnson, M S; McNabb, D P; Norman, E B

    2007-01-01

    Conclusions of this report are that there are 13 new transitions associated with NRF states in 239 Pu that have been discovered. These resonances are between 2- and 2.5-MeV relative to the ground state in 239 Pu. The strengths of most these resonances are between 15 and 20 eV b. This approximately is the strength required for using the transmission detection method for NRF [Pruet et al J. Appl. Phys. 99 12310 (2006)] for six-sigma alarm confidence levels. Future measurements on 239 Pu at higher photon energies are necessary to probe for NRF strengths at higher energies. Such resonances may be more advantageous to the NRF technique with FINDER if they are stronger or if the mean free path of these energetic photons is longer

  2. Combined effects of inhaled plutonium oxide and benzo[a]pyrene on lung carcinogenesis in rats

    International Nuclear Information System (INIS)

    Metivier, H.; Masse, R.; Wahrendorf, J.; Lafuma, J.

    1986-01-01

    This study describes the effect of two intratracheal instillations (5 mg each) of benzo[a]pyrene (BP) on lung carcinogenesis in rats that had previously inhaled three levels of 239 PuO 2 . The BP does not modify survival in the high-level 239 PuO 2 -exposed rats, but markedly reduces survival in the two other groups. Median survival time with BP alone is shorter (666 days) than for the control group (838 days). Tumor incidence was increased by BP exposure, and the tumors were usually fatal, whereas tumors observed after 239 PuO 2 inhalation alone were usually not fatal. Statistical analysis of these data poses a problem because of the need to compare incidental and fatal tumors. 22 refs., 5 figs., 7 tabs

  3. Comparison of standard fast reactor calculations (Baker model)

    Energy Technology Data Exchange (ETDEWEB)

    Voropaev, A I; Van' kov, A A; Tsybulya, A M

    1978-12-01

    Compared are standard fast reactor calculations performed at different laboratories using several nuclear data files: BNAB-70 and OSKAR-75 (the USSR), CARNAVAL-4 (France), FD-5 (Great Britain), KFK-INR (West Germany), ENDF/B4 (the USA). Three fuel compositions were chosen: (1) /sup 239/Pu and /sup 238/U; (2) /sup 239/Pu, /sup 238/U and fission products; (3) /sup 239/Pu, /sup 240/Pu, /sup 238/U and fission products. Medium temperature was 300K. The calculations have been conducted in the diffusion approximation. Data on critical masses and breeding ratios are tabulated. Discrepancies in the calculations of all the characteristics are small since all the countries possess practically the same nuclear data files.

  4. Dose-effect studies with inhaled plutonium oxide in beagles

    International Nuclear Information System (INIS)

    Park, J.F.; Buschbom, R.L.; Case, A.C.

    1977-01-01

    Beagle dogs given a single exposure to 239 PuO 2 or 238 PuO 2 aerosols are being observed for life-span dose-effect relationships. The 239 Pu body burden of the nine dogs that died of pulmonary fibrosis-induced respiratory insufficiency during the first 3 yr after exposure was 1 to 12 μCi. One of these dogs had a pulmonary tumor. Five additional dogs with body burdens of 0.7 to 1.8 μCi died due to pulmonary neoplasia 3 to 5 yr after exposure. None of the dogs exposed to 238 Pu have died during the first 3 postexposure yr. Lymphocytopenia was the earliest observed effect after inhalation of 239 PuO 2 or 238 PuO 2 , occurring 0.5 to 2 yr after deposition of greater than or equal to 80 nCi plutonium in the lungs

  5. Determination of long-lived actinides in soil leachates by inductively coupled plasma: Mass spectrometry

    International Nuclear Information System (INIS)

    Crain, J.S.; Smith, L.L.; Yaeger, J.S.; Alvarado, J.A.

    1994-01-01

    Inductively coupled plasma -- mass spectrometry (ICP-MS) was used to concurrently determine multiple long-lived (t 1/2 > 10 4 y) actinide isotopes in soil samples. Ultrasonic nebulization was found to maximize instrument sensitivity. Instrument detection limits for actinides in solution ranged from 50 mBq L -1 ( 239 Pu) to 2 μBq L -1 ( 235 U) Hydride adducts of 232 Th and 238 U interfered with the determinations of 233 U and 239 Pu; thus, extraction chromatography was, used to eliminate the sample matrix, concentrate the analytes, and separate uranium from the other actinides. Alpha spectrometric determinations of 230 Th, 239 Pu, and the 234 U/ 238 U activity ratio in soil leachates compared well with ICP-MS determinations; however, there were some small systematic differences (ca. 10%) between ICP-MS and a-spectrometric determinations of 234 U and 238 U activities

  6. Neutron absorbers and detector types for spent fuel verification using the self-interrogation neutron resonance densitometry

    International Nuclear Information System (INIS)

    Rossa, Riccardo; Borella, Alessandro; Labeau, Pierre-Etienne; Pauly, Nicolas; Meer, Klaas van der

    2015-01-01

    The Self-Interrogation Neutron Resonance Densitometry (SINRD) is a passive non-destructive assay (NDA) technique that is proposed for the direct measurement of 239 Pu in a spent fuel assembly. The insertion of neutron detectors wrapped with different neutron absorbing materials, or neutron filters, in the central guide tube of a PWR fuel assembly is envisaged to measure the neutron flux in the energy region close to the 0.3 eV resonance of 239 Pu. In addition, the measurement of the fast neutron flux is foreseen. This paper is focused on the determination of the Gd and Cd neutron filters thickness to maximize the detection of neutrons within the resonance region. Moreover, several detector types are compared to identify the optimal condition and to assess the expected total neutron counts that can be obtained with the SINRD measurements. Results from Monte Carlo simulations showed that ranges between 0.1–0.3 mm and 0.5–1.0 mm ensure the optimal conditions for the Gd and Cd filters, respectively. Moreover, a 239 Pu fission chamber is better suited to measure neutrons close to the 0.3 eV resonance and it has the highest sensitivity to 239 Pu, in comparison with a 235 U fission chamber, with a 3 He proportional counter, and with a 10 B proportional counter. The use of a thin Gd filter and a thick Cd filter is suggested for the 239 Pu and 235 U fission chambers to increase the total counts achieved in a measurement, while a thick Gd filter and a thin Cd filter are envisaged for the 3 He and 10 B proportional counters to increase the sensitivity to 239 Pu. We concluded that an optimization process that takes into account measurement time, filters thickness, and detector size is needed to develop a SINRD detector that can meet the requirement for an efficient verification of spent fuel assemblies

  7. Plutonium-induced osteosarcomas in the St. Bernard

    International Nuclear Information System (INIS)

    Taylor, G.N.; Thurman, G.B.; Mays, C.W.; Shabestari, L.; Angus, W.; Eaton, J.; Hitchman, J.

    1978-01-01

    Thirteen osteosarcomas have been observed among the 7 St. Bernards that have died following the injection of 239 Pu. Preliminary data indicate that the St. Bernard is about 6 times more sensitive than the Beagle, and about 150 times more sensitive than the average person is to 239 Pu-induced bone sarcomas. Thus, the St. Bernard may be an excellent model to study the pathogenesis of bone cancer induction, to evaluate the relationship between spontaneous susceptibility and radiosensitivity, and to determine whether or not radiosensitivity significantly affects the toxicity ratio

  8. 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

  9. Subchronic inhalation of carbon tetrachloride alters the tissue retention of acutely inhaled plutonium-239 nitrate in F344 rats and syrian golden hamsters

    Energy Technology Data Exchange (ETDEWEB)

    Benson, J.M.; Barr, E.B.; Lundgren, D.L. [and others

    1995-12-01

    Carbon tetrachloride (CCl{sub 4}) has been used extensively in the nuclear weapons industry, so it is likely that nuclear plant workers have been exposed to both CCl{sub 4} and plutonium compounds. Future exposures may occur during {open_quotes}cleanup{close_quotes} operations at weapons productions sites such as the Hanford, Washington, and Rocky Flats, Colorado, facilities. Inhalation of 20 and 100 ppm CCl{sub 4} by hamsters reduces uptake of {sup 239}Pu solubilized from lung, shunting the {sup 239}Pu to the skeleton.

  10. Data reduction for neutron scattering from plutonium samples. Final report

    International Nuclear Information System (INIS)

    Seeger, P.A.

    1997-01-01

    An experiment performed in August, 1993, on the Low-Q Diffractometer (LQD) at the Manual Lujan Jr. Neutron Scattering Center (MLNSC) was designed to study the formation and annealing of He bubbles in aged 239 Pu metal. Significant complications arise in the reduction of the data because of the very high total neutron cross section of 239 Pu, and also because the sample are difficult to make uniform and to characterize. This report gives the details of the data and the data reduction procedures, presents the resulting scattering patterns in terms of macroscopic cross section as a function of momentum transfer, and suggests improvements for future experiments

  11. Proceedings of the Task 4 Waste Isolation Safety Assessment Program second contractor information meeting

    International Nuclear Information System (INIS)

    1978-01-01

    Volume 1 contains the following papers: Solution Species of 239 Pu in Oxidizing Environments; Solution Species of 239 Pu in the Environment; Theoretical and Experimental Evaluation of Waste Transport in Selected Rocks; Studies of Radionuclide Availability and Migration at the Nevada Test Site Relevant to Radioactive Waste Disposal; Systematic Study of Metal Ion Sorption on Selected Geologic Media; Chromatographic K/sub d/ values of Radionuclides; Effects of Redox Potentials on Sorption of Radionuclides by Geologic Media; and Transport Properties of Nuclear Waste in Geologic Media. Individual papers were processed

  12. Nuclear rotational population patterns in heavy-ion scattering and transfer reactions

    Energy Technology Data Exchange (ETDEWEB)

    Rasmussen, J O; Stoyer, M A [Lawrence Berkeley Lab., CA (USA); Canto, L F; Donangelo, R [Universidade Federal do Rio de Janeiro, RJ (Brazil); Ring, P [Technische Univ. Muenchen, Garching (Germany, F.R.). Fakultaet fuer Physik

    1991-05-01

    A model of {sup 239}Pu with decoupled neutron is used for theoretical calculations of rotational population patterns in heavy ion inelastic scattering and one-neutron transfer reactions. The system treated in {sup 90}Zr on {sup 239}Pu at the near-barrier energy of 500 MeV and backscattering angles of 180deg and 140deg. The influence of the complex nuclear optical potential is seen to be very strong, and the Nilsson wave function of the odd neutron produces a distinctive pattern in the transfer reaction. (orig.).

  13. Fission product yields

    International Nuclear Information System (INIS)

    Valenta, V.; Hep, J.

    1978-01-01

    Data are summed up necessary for determining the yields of individual fission products from different fissionable nuclides. Fractional independent yields, cumulative and isobaric yields are presented here for the thermal fission of 235 U, 239 Pu, 241 Pu and for fast fission (approximately 1 MeV) of 235 U, 238 U, 239 Pu, 241 Pu; these values are included into the 5th version of the YIELDS library, supplementing the BIBFP library. A comparison is made of experimental data and possible improvements of calculational methods are suggested. (author)

  14. Nuclear reactor for breeding 233U

    International Nuclear Information System (INIS)

    Bohanan, C.S.; Jones, D.H.; Raab, H.F. Jr.; Radkowsky, A.

    1976-01-01

    A light-water-cooled nuclear reactor capable of breeding 233 U for use in a light-water breeder reactor includes physically separated regions containing 235 U fissile material and 238 U fertile material and 232 Th fertile material and 239 Pu fissile material, if available. Preferably the 235 U fissile material and 238 U fertile material are contained in longitudinally movable seed regions and the 239 Pu fissile material and 232 Th fertile material are contained in blanket regions surrounding the seed regions. 1 claim, 5 figures

  15. Proceedings of the Task 4 Waste Isolation Safety Assessment Program second contractor information meeting

    Energy Technology Data Exchange (ETDEWEB)

    None

    1978-01-01

    Volume 1 contains the following papers: Solution Species of {sup 239}Pu in Oxidizing Environments; Solution Species of {sup 239}Pu in the Environment; Theoretical and Experimental Evaluation of Waste Transport in Selected Rocks; Studies of Radionuclide Availability and Migration at the Nevada Test Site Relevant to Radioactive Waste Disposal; Systematic Study of Metal Ion Sorption on Selected Geologic Media; Chromatographic K/sub d/ values of Radionuclides; Effects of Redox Potentials on Sorption of Radionuclides by Geologic Media; and Transport Properties of Nuclear Waste in Geologic Media. Individual papers were processed.

  16. Nuclear forensic applications involving high spatial resolution analysis of Trinitite cross-sections

    International Nuclear Information System (INIS)

    Donohue, P.H.; Antonio Simonetti; Koeman, E.C.; Sara Mana; University of Iowa, Iowa City, IA; Burns, P.C.; University of Notre Dame, Notre Dame, IN

    2015-01-01

    This study reports a comprehensive cross-sectional analysis of major and trace element abundances and 240 Pu/ 239 Pu ratios within vertically oriented Trinitite thin sections. The upper glassy layer (∼2 mm thick) represents fused desert sand combined with devolatilized fallout from the debris cloud. The vertical distribution of 240 Pu/ 239 Pu ratios indicates that residual fuel was incorporated deeper (up to ∼10 mm depth) into Trinitite than previously reported. This requires thorough mixing and disturbance of the upper cm of the blast site prior to or during the initial melting of the desert sand resulting from the nuclear explosion. (author)

  17. Fetal doses from plutonium-239 and polonium-210

    International Nuclear Information System (INIS)

    Harrison, J.D.; Morgan, A.; Stather, J.W.

    1992-01-01

    The transfer of 239 Pu and 210 Po from the maternal circulation to the developing embryo and fetus was studied in rodents. The highest concentrations of both isotopes were measured in the yolk sac. In utero doses to haemopoietic tissue have been calculated taking account of transfer to the blastocyst/egg cylinder, yolk sac, liver and bone marrow. From animal data, the concentration ratios relative to maternal liver for these tissues were taken to be 0.1, 2, 0.01 and o.02, respectively for 239 Pu; and 1, 2, 0.1 and 0.1, respectively, for 210 Po. These concentration ratios were applied to periods of human gestation of 0-2.5 weeks, 2.5-6 weeks, 6-12 weeks and 12-38 weeks, and used to calculate fetal tissue doses for chronic maternal intake by ingestion of 1 kBq 239 Pu or 2 kBq 210 Po in the year of pregnancy (1 ALI for a member of the public). On this basis, the total in utero dose to haemopoietic tissue was about 1 μSv from 239 Pu and 60 μSv from 210 Po compared with red bone marrow doses to the mother in the year of 19 μSv from 239 Pu and 160 μSv from 210 Po. The yolk sac and bone marrow dominated in utero doses from both nuclides. For 239 Pu, because of its long half life, an important consideration was activity present in the offspring at birth and committed dose equivalents to red bone marrow in the child and mother. The total dose to haemopoietic tissue in the offspring to age 70 years, including in utero doses, was calculated as 13 μSv compared with a maternal dose to red bone marrow of 1400 μSv. For both isotopes the risk of leukaemia in the year of pregnancy was estimated to be of the same order for mother and fetus. For 239 Pu, the overall risk to 70 years of age was two orders of magnitude higher for the mother than her offspring. For 239 Pu, an acute intake of 1 kBq by ingestion during the period of yolk sac haemopoiesis would result in the highest in utero dose, estimated at about 20 μSv. However, activity at birth would be lower and the overall

  18. Plutonium uptake by the green alga Scenedesmus obliquus (Turp) Kutz, as a function of isotope and oxidation state

    Energy Technology Data Exchange (ETDEWEB)

    Tkacik, M.F.

    1977-01-01

    This study was designed to determine the effect of plutonium chemical valence state on the availability of small concentrations of /sup 238/Pu and /sup 239/Pu to algae. The uptake experiments involved the green alga Scenedesmus obliquus, grown in batch cultures. Plutonium concentrations accumulated by this alga were linearly related to plutonium concentrations. There was no significant difference (rho = 0.05) in algal plutonium accumulations, on a mass basis, of either /sup 238/Pu or /sup 239/Pu in either Pu/sup +4/ or Pu/sup +6/ oxidation state at the concentrations studied.

  19. Chain and independent fission product yields adjusted to conform with physical conservation laws. Part 2

    International Nuclear Information System (INIS)

    Crouch, E.A.C.

    1976-01-01

    Previously reported adjustments to the chain yields and independent yields for the thermal neutron induced fission of 233 U, 235 U, 239 Pu and 241 Pu, the fast neutron induced fission of 232 Th, 233 U, 235 U, 238 U, 239 Pu, 240 Pu and 241 Pu, and the 14 MeV neutron induced fission of 232 Th, 233 U, 235 U and 238 U, have been recalculated using the principle of least squares. The adjustments to the chain yields so found are much smaller than those previously reported. (author)

  20. Dosimetry results for Big Ten and related benchmarks

    International Nuclear Information System (INIS)

    Hansen, G.E.; Gilliam, D.M.

    1980-01-01

    Measured average reaction cross sections for the Big Ten central flux spectrum are given together with calculated values based on the U.S. Evaluated Nuclear Data File ENDF/B-IV. Central reactivity coefficients for 233 U, 235 U, 239 Pu, 6 Li and 10 B are given to check consistency of bias between measured and calculated reaction cross sections for these isotopes. Spectral indexes for the Los Alamos 233 U, 235 U and 239 Pu metal critical assemblies are updated, utilizing the Big Ten measurements and interassembly calibrations, and their implications for inelastic scattering are reiterated

  1. Plutonium uptake by the green alga Scenedesmus obliquus (Turp) Kutz, as a function of isotope and oxidation state

    International Nuclear Information System (INIS)

    Tkacik, M.F.

    1977-01-01

    This study was designed to determine the effect of plutonium chemical valence state on the availability of small concentrations of 238 Pu and 239 Pu to algae. The uptake experiments involved the green alga Scenedesmus obliquus, grown in batch cultures. Plutonium concentrations accumulated by this alga were linearly related to plutonium concentrations. There was no significant difference (rho = 0.05) in algal plutonium accumulations, on a mass basis, of either 238 Pu or 239 Pu in either Pu +4 or Pu +6 oxidation state at the concentrations studied

  2. Calculated critical parameters in simple geometries for oxide and nitrate water mixtures of U-233, U-235 and Pu-239 with thorium. Final report

    International Nuclear Information System (INIS)

    Converse, W.E.; Bierman, S.R.

    1979-11-01

    Calculations have been performed on water mixtures of oxides and nitrates of 233 U, 235 U, and 239 Pu with chemically similar thorium compounds to determine critical dimensions for simple geometries (sphere, cylinder, and slab). Uranium enrichments calculated were 100%, 20%, 10%, and 5%; plutonium calculations assumed 100% 239 Pu. Thorium to uranium or plutonium weight ratios (Th: U or Pu) calculated were 0, 1, 4, and 8. Both bare and full water reflection conditions were calculated. The results of the calculations are plotted showing a critical dimension versus the uranium or plutonium concentration. Plots of K-infinity and material buckling for each material type are also shown

  3. Technique for the Measurement of Low-Level Radioactivity of Organic Iodine in Large-Volume Urine Samples; Technique de Mesure de la Faible Radioactivite de l'Iode Organique Contenu dans des Echantillons d'Urine de Grand Volume; Metod izmereniya nizkikh aktivnostej organicheskogo joda v krupnykh obraztsakh mochi; Tecnicas de Medicion de Bajas Actividades de Yodo Organico Contenido en Muestras de Orina de Gran Volumen

    Energy Technology Data Exchange (ETDEWEB)

    Nicolesco-Zinca, D.; Matei, I. [Institut d' Endocrinologie de l' Academie Roumaine, Bucarest (Romania)

    1965-10-15

    In nuclear endocrinology there are two major problems connected with the determination of renal excretion of iodine in the form of organic compounds labelled in vitro, namely: (a) their quantitative separation from the iodide also present in urine, even if the concentration of the iodide is twenty times greater; and (b) the determination of their low-level radioactivity in large-volume urine samples, their concentration per millilitre of urine being approximately 10{sup -5} of the dose administered which, in turn, must be as low as possible. Classically, separation is carried- out by paper chromatography, for which only small samples of urine are used. This technique is laborious and requires time and equipment for chromatography. Determination of radioactivity on paper involves contamination of the entire band. In spite of correction, only 89.9% of the radioactivity is recovered, and even less when an extract of butanol is used. With the technique described by the authors, a large volume of urine sample is passed through a microcolumn of H{sup +} cation-exchange resin. The organic compounds of the radioiodine remain fixed on the cation- exchange resin and their radioactivity is measured by means of a Nal(Tl) crystal well-type scintillator. On verification for the given conditions, we found the recovery of the urine diiodotyrosine complete, with a standard error averaging 0.42% for 10 experiments. This method has been used for determining the deiodation of diiodotyrosine in 11 patients with normal deiodation and in 10 cretins with goitre, of whom five showed a deficiency of deiodation. The dose administered was 1 {mu}Ci of diiodotyrosine{sup -131}L The method allows for the administration of a radioactive dose at least 50 times lower than in classical methods, and makes possible the separation of diiodotyrosine and its recovery from a sample of 40-50 ml of urine (with a standard error of 0.42% in a period of a few hours) using Nal(Tl) well-type crystal scintillation equipment, which is currently available in nuclear medical laboratories. (author) [French] Dans l'endocrinologie nucleaire deux problemes importants se posent en ce qui concerne la determination de l'excretion renale de l'iode sous forme de composes organiques marques in vitro: a) leur separation quantitative de l'iodure coexistant dans l'urine, meme si la concentration de ce dernier est vingt fois plus grande; b) la determination de leur faible radioactivite dans des echantillons d'urine de grand volume, leur concentration par millilitre d'urine etant approximativement 10{sup -5} fois celle de la dose administree, dont la radioactivite doit etre, a son tour, aussi faible que possible. La separation s'effectue habituellement par chromatographie sur papier, pour laquelle on n'utilise que de petits echantillons d'urine. Cette technique, qui exige des appareils pour chromatographie, est d'une application difficile et longue. Elle implique une contamination de toute la bande de papier. Malgre les corrections apportees, la recuperation de la radioactivite n'est que de 89,9%, et moins encore lorsqu'on utilise un extrait de butanol. La technique des auteurs consiste a faire passer un echantillon de grand volume d'urine a travers une microcolonne d'un cationique H{sup +}. Les composes organiques du radioiode restent tixes sur le cationique et leur radioactivite est mesuree a l'aide d'une sonde a scintillation a cristal de Nal(Tl) creux. La recuperation de la diiodotyrosine de l'urine a ete verifiee dans des conditions donnees; on 1'a trouvee complete, avec une erreur standard de 0,42% sur la moyenne de dix experiences. Cette methode a ete appliquee pour determiner la desiodation de la diiodotyrosine chez onze patients presentant une desiodation normale et chez dix cretins avec goftre, dont cinq ont montre un deficit de desiodation. La radioactivite administree a ete de 1 {mu}Ci de diiodotyrosine-{sup 131}L La methode decrite par les auteurs permet l'administration d'une dose radioactive au moins 50 fois plus faible que celle qu'exige la methode classique. On peut ainsi separer la diiodotyrosine et la recuperer dans un echantillon de 40-50 ml d'urine (avec une erreur standard de 0,42% dans un laps de temps de quelques heures) en utilisant une installation a cristal a scintillation de Nal(Tl) creux, que l'on trouve couramment dans les laboratoires de medecine nucleaire. (author) [Spanish] La determinacion de la excrecion renal de yodo en forma de compuestos organicos marcados in vitro plantea dos serios problemas en endocrinologia nuclear: a) su separacion cuantitativa del yoduro tambien presente en la orina, incluso cuando la concentracion de este ultimo es veinte veces mayor; b) la determinacion de su debil actividad enmuetras de orina de gran volumen, y que su concentracion por mililitro de orina representa aproximadamente 10{sup -5} de la radiactividad administrada que, a su vez, debe ser lo mas baja posible. La separacion suele efectuarse por cromatografia sobre papel, para lo cual solo se utilizan pequenas muestras de orina. Esta tecnica es laboriosa y exige mucho tiempo y aparatos para cromatografia. Al proceder a la determinacion de la radiactividad sobre el papel, se encuentra una contaminacion de toda la tira. A pesar de las correcciones aplicadas, se recupera solamente el 89,9% de la radiactividad, y atin menos si se emplea un extracto butanolico. Los autores recurren a una tecnica consistente en hacer pasar un gran volumen de orina por una micro- columna de resina cationica en su forma hidrogenada. Los compuestos organicos del radioyodo quedan retenidos en la resina y se determinan midiendo la radiactividad de la columna con una sonda de centelleo de cristal de Nal hueco. Los autores comprobaron que la recuperacion de la diyodotirosina de la orina es practicamente cuantitativa, siendo el error tipo de 0,42% para diez experimentos. El metodo se ha empleado para determinar la desyodacion de la diyodotirosina en 11 pacientes que presentan una desyodacion normal y en 10 cretinos con bocio, en cinco de los cuales la desyodacion era deficiente. Se administro 1 {mu}Ci de diyodotirosina-{sup 131}I. El metodo se puede emplear administrando una dosis radiactiva por lo menos 50 veces menor y permite separar la diyodotirosina y recuperarla en una muestra de 40 a 50 mi de orina con un error tipo de 0,42% en un plazo de algunas horas; requiere un aparato de centelleo con cristal de Nal hueco que se encuentra corrientemente en los laboratorios de medicina nuclear. (author) [Russian] V jadernoj jendokrinologii voznikajut dve bol'shie problemy v otnoshenii opredelenija pochechnogo vydelenija joda kak organicheskih soedinenij,' mechennyh in vitro: - ih kolichestvennoe razdelenie ot iodistogo soedinenija, prisutstvujushhego v moche, dazhe esli koncentracija joda v dvadcat' raz bol'she; - opredelenie ih nizkoj aktivnosti v krupnyh obrazcah mochi, prichem koncentracija na 1 ml mochi sostavljaet priblizitel'no 10{sup -5} ot vvedennoj aktivnosti, kotoraja dolzhna, v svoju ochered', byt' po vozmozhnosti nizkoj. Obychno razdelenie proizvoditsja metodom bumazhnoj hromatografii, kotoryj ispol'zuet lish' nebol'shie obrazcy mochi. Jetot metod trudoemok, trebuet mnogo vremeni i priborov dlja hromatografii. Pri opredelenii aktivnosti na bumage zagrjaznenie obnaruzhivaetsja na vsej lente. Nesmotrja na popravki rekuperacija aktivnosti sostavljaet lish' 89,9%i eshhe men'she, esli primenjaetsja butanovyj jekstrakt. Po izlagaemomu metodu krupnyj obrazec mochi prohodit cherez mikrokolonku kationobmen- noj smoly N{sup +}. Organicheskie soedinenija radioaktivnogo ioda fiksirujutsja na kationobmennoj smole, i ih aktivnost' opredeljaetsja s pomoshh'ju scintilljacionnogo zonda, imejushhego kristall NaJ(Tl). Posle proverki dlja zadannyh uslovij rekuperacii diiodotirozina mochi my nashli molnuju rekuperaciju so standartnymi pogreshnostjami v srednem 0,42% dlja 10 jeksperimentov . Jetot metod primenjalsja dlja opredelenija deziodizacii diiodotirozina u 11 pacientov s normal'noj deziodizaciej i u 10 kretinov s zobom, u 5 iz kotoryh byl obnaruzhen deficit deziodizacii. Vvedennaja aktivnost' sostavljala 1 mkkjuri diiodotirozina, mechennogo jodom-131. Opisyvaemyj metod pozvoljaet vvodit' po krajnej mere v 50 raz men'shuju dozu aktiv - nosti, chem pri obychnyh metodah, razdeljat' diiodotirozin i obespechivat' ego rekuperaciju iz obrazca s ob{sup e}mom 40-50 ml mochi so standartnoj pogreshnost'ju porjadka 0,42%v techenie neskol'kih chasov. Pri jetom ispol'zuetsja ustanovka s scintilljacionnym kristallom NaJ, kotoraja shiroko vstrechaetsja v laboratorijah jadernoj mediciny. (author)

  4. The research of sub-picogram plutonium's quantitative analysis by isotope mass spectrometry

    International Nuclear Information System (INIS)

    Tang Lei; Long Kaiming; Yang Tianli; Liu Xuemei

    2005-10-01

    By using active carbon powder as emission matter, the detect sensitivity of 239 Pu was 0.5 pg (1 ± 0.15, 95% confidence level), improved 20 times compared with the sensitivity 10 pg (1 ± 0.5) of the tradition method. The sub-picogram plutonium sample was determined quantatively by isotope dilution mass spectrometry (IDMS). (authors)

  5. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    International Nuclear Information System (INIS)

    Adams, J.P.; Carboneau, M.L.

    1999-01-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body

  6. Variations in Pu isotopic composition in soils from the Spitsbergen (Norway): Three potential pollution sources of the Arctic region.

    Science.gov (United States)

    Łokas, E; Anczkiewicz, R; Kierepko, R; Mietelski, J W

    2017-07-01

    Although the polar regions have not been industrialised, numerous contaminants originating from human activity are detectable in the Arctic environment. This study reports evidence of 240 Pu/ 239 Pu atomic ratios in the tundra and initial soils from different parts of west and central Spitsbergen and recognizes possible environmental inputs of non-global fallout Pu. The average atomic ratio of 240 Pu/ 239 Pu equal to 0.179 (ranging between 0.129 and 0.201) in tundra soils are comparable to the characteristic ratio for global fallout (0.180). However, the 240 Pu/ 239 Pu atomic ratios in the initial soils from proglacial zone of glaciers change within wide range between 0.1281 and 0.234 with the mean value of 0.169. By combining alpha and mass spectrometry, the three-sources model was used to identify the Pu sources in initial soils. Our study indicated that the main source of Pu is nuclear tests and that a second source with lower Pu ratio may come from weapons grade Pu (unexploded weapons grade Pu ie. material from bomb which didn't undergo nuclear explosions for example for security tests). Additionally, we found samples with high 238 Pu/ 239+240 Pu activity ratios and with typical global fallout 240 Pu/ 239 Pu atomic ratios, which are associated with separate sources of pure 238 Pu from the SNAP-9A satellite burn up in the atmosphere. Copyright © 2017 Elsevier Ltd. All rights reserved.

  7. Characterization of a facility for the measurement of fission fragment transport effects: experimental determination of the fission rates for fissile and fissionable isotopes

    International Nuclear Information System (INIS)

    Benetti, P.; Raselli, G.L.; Tigliole, A. Borio di; Cagnazzo, M.; Cesana, A.; Mongelli, S.; Terrani, M.

    2002-01-01

    The transfer facility of the LENA laboratory allows the direct neutron irradiation of fissionable material in the D channel of the TRIGA reactor. A test measurement carried out with a ionization chamber and a 239 Pu sample shows the possibility to use this tool for the study of the transport effects of the fission fragment emerging from thin layers of fissile materials. (author)

  8. Application of Reactor Antineutrinos: Neutrinos for Peace

    Science.gov (United States)

    Suekane, F.

    2013-02-01

    In nuclear reactors, 239Pu are produced along with burn-up of nuclear fuel. 239Pu is subject of safeguard controls since it is an explosive component of nuclear weapon. International Atomic Energy Agency (IAEA) is watching undeclared operation of reactors to prevent illegal production and removal of 239Pu. In operating reactors, a huge numbers of anti electron neutrinos (ν) are produced. Neutrino flux is approximately proportional to the operating power of reactor in short term and long term decrease of the neutrino flux per thermal power is proportional to the amount of 239Pu produced. Thus rector ν's carry direct and real time information useful for the safeguard purposes. Since ν can not be hidden, it could be an ideal medium to monitor the reactor operation. IAEA seeks for novel technologies which enhance their ability and reactor neutrino monitoring is listed as one of such candidates. Currently neutrino physicists are performing R&D of small reactor neutrino detectors to use specifically for the safeguard use in response to the IAEA interest. In this proceedings of the neutrino2012 conference, possibilities of such reactor neutrinos application and current world-wide R&D status are described.

  9. A technical alpha-active aerosol express measurement system for volumetric activity monitoring.; Metodika ehkspressnogo opredeleniya ob`emnoj aktivnosti tekhnogennykh al`fa-aktivnykh aehrozolej.

    Energy Technology Data Exchange (ETDEWEB)

    Badovskij, V P; Dubar, L V; Tokarevskij, V V; Shevchenko, S V; Shcherbina, V G [Myizhgaluzevij Naukovo-Tekhnyichnij Tsentr ` ` Ukrittya ` ` , Natsyional` na Akademyiya Nauk Ukrayini, Chornobil` (Ukraine)

    1994-12-31

    A possibility of a volumetric aerosol activity determination at the level of MPCa for {sup 239} Pu with a measurement time less than 60 minutes is discussed. For achieving maximum reduction of the natural background the virtual impactor and alpha-spectroscopy are proposed to be employed. Results of investigation of the virtual impactor parameters at the << Shelter >> and at the laboratory are described.

  10. Disposition of 238Pu(NO3)4 following inhalation by beagle dogs

    International Nuclear Information System (INIS)

    Dagle, G.E.; Cannon, W.C.; Schirmer, R.E.; Stevens, D.L. Jr.

    1979-01-01

    Twelve dogs were given a single inhalation exposure to 238 Pu(NO 3 ) 4 to study deposition and translocation up to 1 yr. Preliminary data suggest a greater and more rapid translocation of 238 Pu(NO 3 ) 4 to bone and liver than was observed for 239 Pu(NO 3 ) 4

  11. Fission track analysis of Pu in small specimens of biological material: Technical progress report, August 1, 1987--July 31, 1988

    International Nuclear Information System (INIS)

    Wrenn, M.E.

    1988-01-01

    The objective of this research is to develop a highly specific and ultrasensitive method capable of detecting 100 aCi/liter of 239 Pu in human urine. The method using neutron induced fission track analysis is to be made free of interference from uranium, the only naturally occurring element with an isotope which fissions with thermal neutrons. A simplified flow diagram for the method is shown in Figure 1. Briefly 239 Pu is coprecipitated quantitatively from urine with rhodozonic acid. The precipitate containing the 239 Pu is dissolved in HCl and is sequentially passed through two ion exchange columns and reduced in volume. The element is then deposited in a circular area on a thick polycarbonate detector and a thinner detector is placed over the circular deposit. The plastic detectors are then irradiated to a high thermal neutron fluence in a research reactor. The detectors are etched in a caustic solution for controlled times and temperatures in order to develop the fission tracks. Images of tracks are formed both on the thin and thick plastic detectors. Total tracks in the thinner detector are measured with a locally developed spark counter and in the thick plastic are measured by counting with a microscope. The results will be made quantitative by constructing a calibration curve for 239 Pu. 3 refs., 9 figs., 3 tabs

  12. Plutonium in Southern Hemisphere Ocean Waters

    Energy Technology Data Exchange (ETDEWEB)

    Hirose, K. [Sophia University, Tokyo (Japan); Aoyama, M. [Meteorological Research Institute, Tsukuba (Japan); Gastaud, J.; Levy, I. [Marine Environment Laboratories, International Atomic Energy Agency (Monaco); Fukasawa, M. [Japan Agency for Marine-Earth Science and Technology Yokosuka (Japan); Kim, C. -S. [Environment Laboratories, International Atomic Energy Agency, Seibersdorf (Austria); Povinec, P. P. [Comenius University, Bratislava (Slovakia); Roos, P. [Riso National Laboratory, Roskilde (Denmark); Sanchez-Cabeza, J. A. [Universitat Autonoma de Barcelona, Bellaterra (Spain); Yim, S. A. [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

    2013-07-15

    Plutonium in seawater collected by the BEAGLE2003 cruise was determined using ICP-SF-MS and alpha spectrometry after Fe co-precipitation and radiochemical purification. Levels and distributions of dissolved plutonium activity concentrations in Southern Hemisphere ocean waters are summarized here, including historical data. Pu-239 concentrations in surface water of the central South Pacific (32.5{sup o}S) in 2003 were around 1 mBq/m{sup 3}. The {sup 239}Pu concentrations in the Indian Ocean surface waters (20{sup o}S) were similar to that in the South Pacific, whereas the {sup 239}Pu concentrations in the South Atlantic surface waters (30{sup o}S) were markedly lower than those in the South Pacific and Indian Oceans. The {sup 239}Pu vertical profile pattern was similar to that in the North Pacific subtropical gyre, although {sup 239}Pu concentrations in the deep South Pacific were significantly lower than those in the North Pacific. One of the dominant factors controlling plutonium distributions in the Southern Hemisphere oceans is biogeochemical processes including particle scavenging. (author)

  13. Current status of life-span studies with inhaled plutonium in beagles at Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Park, J.F.; Dagle, G.E.; Ragan, H.A.; Weller, R.E.; Stevens, D.L.

    1986-01-01

    Beagles that inhaled 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 , in dose-level groups of 20 dogs, with initial lung burdens of ∼2, 15, 70, 300, 1100, or 5500 nCi, are now 11, 9, or 5 years postexposure. Lung tumors, bone tumors, and radiation pneumonitis, the plutonium-exposure-related causes of death observed to date, have occurred in the two, three, and four highest dose-level groups exposed to 238 PuO 2 , 239 Pu(NO 3 ) 4 , and 239 PuO 2 , respectively. No plutonium-exposure-related deaths have thus far been observed in dose-level groups exposed to less than ∼40 times the current maximum permissible lung dose for a plutonium worker. Plutonium-exposure-related effects not directly related to the cause of death include chronic lymphopenia, chronic neutropenia, sclerosis of the tracheobronchial lymph nodes, focal radiation pneumonitis, adenomatous hyperplasia in the liver, and dystrophic osteolytic lesions in the skeleton. No plutonium-exposure-related effects have thus far been observed in dose-level groups that received less than ∼15 times the current maximum permissible lung dose for a plutonium worker. 10 refs., 5 figs., 4 tabs

  14. Plutonium-239 production rate study using a typical fusion reactor

    International Nuclear Information System (INIS)

    Faghihi, F.; Havasi, H.; Amin-Mozafari, M.

    2008-01-01

    The purpose of the present paper is to compute fissile 239 Pu material by supposed typical fusion reactor operation to make the fuel requirement for other purposes (e.g. MOX fissile fuel, etc.). It is assumed that there is a fusion reactor has a cylindrical geometry and uses uniformly distributed deuterium-tritium as fuel so that neutron wall load is taken at 10(MW)/(m 2 ) . Moreover, the reactor core is surrounded by six suggested blankets to make best performance of the physical conditions described herein. We determined neutron flux in each considered blanket as well as tritium self-sufficiency using two groups neutron energy and then computation is followed by the MCNP-4C code. Finally, material depletion according to a set of dynamical coupled differential equations is solved to estimate 239 Pu production rate. Produced 239 Pu is compared with two typical fission reactors to find performance of plutonium breeding ratio in the case of the fusion reactor. We found that 0.92% of initial U is converted into fissile Pu by our suggested fusion reactor with thermal power of 3000 MW. For comparison, 239 Pu yield of suggested large scale PWR is about 0.65% and for LMFBR is close to 1.7%. The results show that the fusion reactor has an acceptable efficiency for Pu production compared with a large scale PWR fission reactor type

  15. Plutonium-239 production rate study using a typical fusion reactor

    Energy Technology Data Exchange (ETDEWEB)

    Faghihi, F. [Research Center for Radiation Protection, Shiraz University, Shiraz (Iran, Islamic Republic of)], E-mail: faghihif@shirazu.ac.ir; Havasi, H.; Amin-Mozafari, M. [Department of Nuclear Engineering, School of Engineering, Shiraz University, 71348-51154 Shiraz (Iran, Islamic Republic of)

    2008-05-15

    The purpose of the present paper is to compute fissile {sup 239}Pu material by supposed typical fusion reactor operation to make the fuel requirement for other purposes (e.g. MOX fissile fuel, etc.). It is assumed that there is a fusion reactor has a cylindrical geometry and uses uniformly distributed deuterium-tritium as fuel so that neutron wall load is taken at 10(MW)/(m{sup 2}) . Moreover, the reactor core is surrounded by six suggested blankets to make best performance of the physical conditions described herein. We determined neutron flux in each considered blanket as well as tritium self-sufficiency using two groups neutron energy and then computation is followed by the MCNP-4C code. Finally, material depletion according to a set of dynamical coupled differential equations is solved to estimate {sup 239}Pu production rate. Produced {sup 239}Pu is compared with two typical fission reactors to find performance of plutonium breeding ratio in the case of the fusion reactor. We found that 0.92% of initial U is converted into fissile Pu by our suggested fusion reactor with thermal power of 3000 MW. For comparison, {sup 239}Pu yield of suggested large scale PWR is about 0.65% and for LMFBR is close to 1.7%. The results show that the fusion reactor has an acceptable efficiency for Pu production compared with a large scale PWR fission reactor type.

  16. Additions and corrections to the communications presented by France at the Geneva Conference in august 1955; Additifs et correctifs aux communications presentees par la France a la conference de Geneve d'aout 1955

    Energy Technology Data Exchange (ETDEWEB)

    Labeyrie, J; Weill, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

    1956-07-01

    A graphic correction is given for the communication number 442 of the C.E.A. at the Geneva conference about the measurement of atmosphere radioactivity and pollution near an atomic centre. An addition to the communication number 446 of the C.E.A. at the Geneva conference about the measurement of the cross section of fissile nucleus for slow neutrons is presented. It discussed the measurement of the cross section of {sup 235}U nucleus fission for neutrons of 25 keV by comparing the fission cross section of {sup 235}U and the activation cross section of {sup 197}Au with two different neutrons sources. The principle and experimental procedures are explained and the experimental data and results are given. A note about the cross section of {sup 239}Pu fission for slow neutrons is added. A modification of the appendix in the communication number 405 of the C.E.A. at the Geneva conference about the study of the energy dependent variation of the cross sections of {sup 233}U, {sup 235}U and {sup 239}Pu fission for fast neutrons is given. The variation of the fission cross sections of {sup 233}U, {sup 235}U and {sup 239}Pu with the neutrons energy is given as well as the variation of the counting ratio of fission between {sup 239}Pu and {sup 235}U with the neutrons sources distance. The efficiency of the 'long' counter is discussed. (M.P.)

  17. Uranium concentrations in human bone

    International Nuclear Information System (INIS)

    Schlenker, R.A.; Oltman, B.G.

    1981-01-01

    The uranium concentration in bone from an individual injected with 239 Pu has been determined, using the fission-track method. The data are consistent with those reported about 10 years ago by Welford and Baird for New York City area residents and by Hamilton in England. They are at variance with the more recent data of Welford et al

  18. Determination of 90Sr and Pu isotopes in contaminated groundwater samples by inductively coupled plasma mass spectrometry

    Science.gov (United States)

    Zoriy, Miroslav V.; Ostapczuk, Peter; Halicz, Ludwik; Hille, Ralf; Becker, J. Sabine

    2005-04-01

    A sensitive analytical method for determining the artificial radionuclides 90Sr, 239Pu and 240Pu at the ultratrace level in groundwater samples from the Semipalatinsk Test Site area in Kazakhstan by double-focusing sector field inductively coupled plasma mass spectrometry (ICP-SFMS) was developed. In order to avoid possible isobaric interferences at m/z 90 for 90Sr determination (e.g. 90Zr+, 40Ar50Cr+, 36Ar54Fe+, 58Ni16O2+, 180Hf2+, etc.), the measurements were performed at medium mass resolution under cold plasma conditions. Pu was separated from uranium by means of extraction chromatography using Eichrom TEVA resin with a recovery of 83%. The limits of detection for 90Sr, 239Pu and 240Pu in water samples were determined as 11, 0.12 and 0.1 fg ml-1, respectively. Concentrations of 90Sr and 239Pu in contaminated groundwater samples ranged from 18 to 32 and from 28 to 856 fg ml-1, respectively. The 240Pu/239Pu isotopic ratio in groundwater samples was measured as 0.17. This isotope ratio indicates that the most probable source of contamination of the investigated groundwater samples was the nuclear weapons tests at the Semipalatinsk Test Site conducted by the USSR in the 1960s.

  19. Workshop on environmental research for transuranic elements, Seattle, Washington, November 12--14, 1975

    International Nuclear Information System (INIS)

    1975-01-01

    Brief summaries are presented of discussions among scientists conducting research on the transport and diffusion of transuranium elements in aquatic and terrestrial ecosystems. Emphasis was placed on 238 Pu, 239 Pu, 240 Pu, and 241 Am in ecosystems and food chains. Areas for future research were suggested to insure the safe storage of radioactive wastes from the nuclear industry

  20. Application of static electricity radioisotope eliminators in oil-processing and petrochemical industry

    International Nuclear Information System (INIS)

    Zhuravlev, V.S.; Evmenov, A.K.; Bondarev, L.M.; Kharlamov, O.V.

    1977-01-01

    Examples are discussed of the use of radioisotope eliminators of the static electricity on the basis of the 239 Pu apha radiation sources in the technological processes of the production and processing synthetic caoutchoucs, rubbers and film materials. The efficiency of different types of eliminators is testified; prospects of their application in the industry are outlined

  1. DOE life-span radiation effects studies at Pacific Northwest Laboratory

    International Nuclear Information System (INIS)

    Thompson, R.C.; Cross, F.T.; Dagle, G.E.; Park, J.F.; Sanders, C.L.

    1986-01-01

    Major life-span radiation effects studies at Pacific Northwest Laboratory fall into three categories: (1) studies with beagle dogs exposed to plutonium compounds via a single inhalation; (2) studies with dogs and rats exposed chronically via inhalation to various combinations and concentrations of radon, radon daughters, and other components of uranium mine atmospheres; and (3) a study in which rats are exposed via single inhalation, in very large numbers, to very low concentrations of 239 PuO 2 . Exposure of beagles currently on study was initiated in 1970 with 239 PuO 2 , in 1973 with 238 PuO 2 , and in 1976 with 239 Pu(NO 3 ) 4 . These experiments involve more than 500 animals, many of them still alive. Experiments seeking to explain the increased incidence of lung cancer in uranium miners have been in progress since 1966. Present emphasis is on studies with rats, in an attempt to define dose-effect relationships at the lowest feasible radon-daughter exposure levels. Our very-low-level experiment with inhaled 239 PuO 2 in rats, with exposures still under way, includes 1000 rats in the control group and 1000 rats in the lowest-exposure group, where life-span lung doses of <5 rads are anticipated

  2. Accelerator-breeder, an application of high-energy accelerators to solving our energy problems

    International Nuclear Information System (INIS)

    Grand, P.; Batchelor, K.; Powell, J.R.; Steinberg, M.

    1977-01-01

    The rising costs of 235 U and other fossil fuels, and the schedule for implementing the breeder reactor have renewed interest in the utilization of accelerators for breeding 233 U or 239 Pu. A discussion is given of some of the basic accelerator parameters and choices to be made in order to meet the technical and economic requirements of such a facility

  3. Migration of 90Sr, 137Cs and Pu in soils. Verification of a computer model on the behaviour of these radiocontaminants in soils of Western Europe

    International Nuclear Information System (INIS)

    Frissel, M.J.; Poelstra, P.; Klugt, N. van der.

    1980-01-01

    The main emphasis in 1979 was on the 239 240 Pu model for simulating translocations in soil. The verification was hampered because data for 239 Pu were available from only two locations. A comparison between the observed and predicted Pu distribution however indicated the possibility of using the available simulation approach for 239 240 Pu. (Auth.)

  4. 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

  5. National Low-Level Waste Management Program Radionuclide Report Series, Volume 17: Plutonium-239

    Energy Technology Data Exchange (ETDEWEB)

    J. P. Adams; M. L. Carboneau

    1999-03-01

    This report, Volume 17 of the National Low-Level Waste Management Program Radionuclide Report Series, discusses the radiological and chemical characteristics of plutonium-239 (Pu-239). This report also discusses waste types and forms in which Pu-239 can be found, waste and disposal information on Pu-239, and Pu-239 behavior in the environment and in the human body.

  6. Generation of one energy group cross section library with MC2 computer code

    International Nuclear Information System (INIS)

    Cunha Menezes Filho, A. da; Souza, A.L. de.

    1982-01-01

    One group temperature dependent cross sections are generated via MC 2 for Pu-242, Ni-58, Fe-56, U-235, U-238, Pu-239, Pu-240, Pu-241, Be-9 e Th-232. The influence of the buckling and the weighting functions is studied throught calculations of an important integral parameter: the critical radius. (author) [pt

  7. UK nuclear data progress report for the period January - December 1981

    International Nuclear Information System (INIS)

    Lees, E.W.

    1982-06-01

    Summaries are given of work by AERE Harwell, AEEW Winfrith, National Physical Laboratory, NRPB, Birmingham Radiation Centre and the Universities of Birmingham and Edinburgh. A paper on fission product decay heat from 235 U and 239 Pu is included. (U.K.)

  8. Spatial and temporal distribution of Pu in the Northwest Pacific Ocean using modern coral archives.

    Science.gov (United States)

    Lindahl, Patric; Andersen, Morten B; Keith-Roach, Miranda; Worsfold, Paul; Hyeong, Kiseong; Choi, Min-Seok; Lee, Sang-Hoon

    2012-04-01

    Historical (239)Pu activity concentrations and (240)Pu/(239)Pu atom ratios were determined in skeletons of dated modern corals collected from three locations (Chuuk Lagoon, Ishigaki Island and Iki Island) to identify spatial and temporal variations in Pu inputs to the Northwest Pacific Ocean. The main Pu source in the Northwest Pacific is fallout from atmospheric nuclear weapons testing which consists of global fallout and close-in fallout from the former US Pacific Proving Grounds (PPG) in the Marshall Islands. PPG close-in fallout dominated the Pu input in the 1950s, as was observed with higher (240)Pu/(239)Pu atom ratios (>0.30) at the Ishigaki site. Specific fallout Pu contamination from the Nagasaki atomic bomb and the Ivy Mike thermonuclear detonation at the PPG were identified at Ishigaki Island from the (240)Pu/(239)Pu atom ratios of 0.07 and 0.46, respectively. During the 1960s and 1970s, global fallout was the major Pu source to the Northwest Pacific with over 60% contribution to the total Pu. After the cessation of the atmospheric nuclear tests, the PPG again dominated the Pu input due to the continuous transport of remobilised Pu from the Marshall Islands along the North Equatorial Current and the subsequent Kuroshio Current. The Pu contributions from the PPG in recent coral bands (1984 onwards) varied over time with average estimated PPG contributions between 54% and 72% depending on location. Copyright © 2011 Elsevier Ltd. All rights reserved.

  9. Association of radionuclides with different molecular size fractions in soil solution: implications for plant uptake

    International Nuclear Information System (INIS)

    Nisbet, A.F.; Shaw, S.; Salbu, B.

    1993-01-01

    The feasibility of using hollow fibre ultrafiltration to determine the molecular size distribution of radionuclides in soil solution was investigated. The physical and chemical composition of soil plays a vital role in determining radionuclide uptake by plant roots. Soil solution samples were extracted from loam, peat and sand soils that had been artificially contaminated with 137 Cs, 90 Sr, 239 Pu and 241 Am six years previously as part of a five-year lysimeter study on radionuclide uptake to crops. Ultrafiltration of soil solution was performed using hollow fibre cartridges with a nominal molecular weight cut off of 3 and 10 kD. The association of 137 Cs, 90 Sr, 239 Pu and 241 Am with different molecular size fractions of the soil solution is discussed in terms of radionuclide bioavailability to cabbage grown in the same three soils. 137 Cs and 90 Sr were present in low molecular weight forms and as such were mobile in soil and potentially available for uptake by the cabbage. In contrast, a large proportion (61-87%) of the 239 Pu and 241 Am were associated with colloidal and high molecular weight material and therefore less available for uptake by plant roots. The contribution from low molecular weight species of 239 Pu and 241 Am to the total activity in soil solution decreased in the order loam ≥ peat ≥ sand. Association of radionuclides with low molecular weight species of less than 3 kD did not, however, automatically imply availability to plants. (author)

  10. SFINX: Soviet-French integral experiment on measuring the capture and fission at Masurca and BFS

    International Nuclear Information System (INIS)

    Doulin, V.A.; Mikhailov, J.M.; Mozhaev, V.K.

    1990-01-01

    The SFINX experiment was aimed at the comparison of experimental procedures used at the MASURCA and the BFS critical assemblies for measuring the ratio of the 238 U and 239 Pu average fission cross-sections to the 235 U average cross-section (F8/F5, F9/F5) and of the 238 U average capture cross-section to the 239 Pu average fission cross section (C8/F9). As part of the calibration of the measurements F8/F5 and F9/F5 were also measured in a thermal column. To obtain C8/F9, absolute measurements of capture rates in 238 U and fission rates in 239 Pu and 235 U were carried out. The measurements were made in September 1987 at the MASURCA facility (FRANCE) in the BALZAC 1 critical assembly and in the thermal column of the HARMONIE facility. In April 1989 these measurements were complemented by joint measurements of the 239 Pu absolute fission rate at the BFS 55-1 critical assembly (USSR)

  11. Solution of human respiratory tract model for chronic inhalation intake

    International Nuclear Information System (INIS)

    Nadar, Minal Y.; Singh, I.S.; Rao, D.D.; Pradeepkumar, K.S.

    2014-01-01

    For the radiation workers of fuel reprocessing and fuel fabrication plants, inhalation is one of the major routes of intake of internal contamination. In case of routine monitoring which would result in lung activity above detection limit, it is assumed that intake has occurred at the midpoint of monitoring interval so that underestimation introduced by the unknown time of intake is less than a factor of three. In the plants, chronic intakes of 239 Pu are possible if low levels of 239 Pu activities remain undetected. In ICRP-78, the retention values are given as a function of time for continuous chronic inhalation of 239 Pu at 1.71 Bq/day that would result in Committed Effective Dose (CED) of 20 mSv. Retention values (R) are not given for inhalation intake at any other rate. Therefore, Human Respiratory Tract Model (HRTM) is solved for continuous chronic inhalation at 1 Bq/day rate for type M compounds of 239 Pu to estimate R as a function of time. These values will be useful in estimating intake from lung activity measurements in case of chronic intakes

  12. Mixed ligand chelate therapy for plutonium and cadmium poisoning

    Energy Technology Data Exchange (ETDEWEB)

    Schubert, J; Derr, S K [Hope Coll., Holland, MI (USA)

    1978-09-28

    Some experiments with mice are described in which complete removal of tissue deposits of /sup 239/Pu and prevention of mortality in animals given lethal doses of Cd were achieved using a mixed ligand chelate treatment (MLC). The mixed ligand consisted of diethylenetriaminepentaacetic acid and salicylic acid.

  13. A preliminary assessment of sup(239,240)Pu concentrations in a stream near Argonne National Laboratory

    International Nuclear Information System (INIS)

    Singh, H.; Marshall, J.S.

    1977-01-01

    The plutonium levels in Sawmill Creek, a stream which flows through the site of the Argonne National Laboratory have been determined and are compared here with the environmental levels reported in related studies. The major source of artificial radioactivity in the creek is Argonne's nuclear facilities which produce low-level wastes following clean-up and dilution in the ANL sewage plant. Samples were collected within 1 mile upstream and 1 mile downstream of ANL's waste discharge into the creek. Samples consisted of filtered water, filterable solids, whole water, Cladophora sp., sunfish (gill and G.I. tracts), isopods, and sediments. Results showed that: (1) The filterable solids from the effluent water contained 99% of 239 Pu in contrast to 37% from the upstream water sample. (2) The downstream 239 Pu levels in the whole water of Sawmill Creek were much higher than those reported in related studies. (3) 239 Pu appears to be scavenged primarily by Cladophora sp. in the downstream water of the creek. (4) Fish G.I. tract and its content contained seven times more 239 Pu activity than fish gills. (U.K.)

  14. Options for clean-up of the Maralinga test site

    International Nuclear Information System (INIS)

    1985-06-01

    This report examines the limit of contamination of the soil and ground cover by 239 Pu, 235 U and 241 Am which may be considered as permitting the unrestricted land use of the former nuclear weapon test sites at Emu and Maralinga by Aboriginal groups. It reports on the options available to achieve this objective and their cost

  15. On-Line/At-Line Technetium Monitor Using Scintillating Ion Exchange Resins for the Savannah River Site

    International Nuclear Information System (INIS)

    Wach, S.T.

    2000-01-01

    The results of this study indicate that the combination of extraction chromatography and on-line flow-cell scintillation counting can exceed a 99Tc detection limit of 0.005 Ci/mL in the presence of 90Sr, 137Cs, and 239Pu in less than an 18 minute analysis time

  16. Isotope dilution alpha spectrometry for the determination of plutonium concentration in irradiated fuel dissolver solution : IDAS and R-IDAS

    International Nuclear Information System (INIS)

    Ramaniah, M.V.; Jain, H.C.; Aggarwal, S.K.; Chitambar, S.A.; Kavimandan, V.D.; Almaula, A.I.; Shah, P.M.; Parab, A.R.; Sant, V.L.

    1980-01-01

    The report presents a new technique, Isotope Dilution Alpha Spectrometry (IDAS) and Reverse Isotope Dilution Alpha Spectrometry (R-IDAS) for determining the concentration of plutonium in the irradiated fuel dissolver solution. The method exploits sup(238)Pu in IDAS and sup(239)Pu in R-IDAS as a spike and provides an alternative method to Isotope Dilution Mass Spectrometry (IDMS) which requires enriched sup(242)Pu as a spike. Depending upon the burn-up of the fuel, sup(238)Pu or sup(239)Pu is used as a spike to change the sup(238)Pu/(sup(239)Pu+sup(240)Pu)α activity ratio in the sample by a factor of 10. This change is determined by α-spectrometry on electrodeposited sources using a solid state silicon surface barrier detector coupled to a multichannel analyser. The validity of a simple method based on the geometric progression (G.P.) decrease for the far tail of the spectrum to correct for the tail contribution of sup(238)Pu peak (5.50 MeV) to the low energy sup(239)Pu + sup(240)Pu peak (5.17 MeV) is established. Results for the plutonium concentration on different irradiated fuel dissolver solutions with burn-uo ranging from J,000 to 100,000 MWD/TU are presented and compared with those obtained by IDMS. The values obtained by IDAS or R-IDAS and IDMS agree within 0.5%. (auth.)

  17. First and second chance fission calculations for actinides and related topics

    International Nuclear Information System (INIS)

    Maino, G.; Menapace, E.; Motta, M.; Ventura, A.

    1980-01-01

    First and second chance contributions to neutron induced fission cross sections in an energy range of interest for reactor applications (E/sub n/less than or equal to 13 MeV) were obtained by extensive and consistent calculations for 241 Am; moreover, a simplified semiempirical approach was applied to 235 U and 239 Pu

  18. Comparative uptake and distribution of plutonium, americium, curium and neptunium in four plant species

    Energy Technology Data Exchange (ETDEWEB)

    Schreckhise, R E; Cline, J F [Battelle Pacific Northwest Labs., Richland, WA (USA)

    1980-05-01

    Uptake of the nitrate forms of /sup 238/Pu, /sup 239/Pu, /sup 241/Am, /sup 244/Cm and /sup 237/Np from soil into selected parts of four different plant species grown under field conditions was compared Alfalfa, barley, peas and cheatgrass were grown outdoors in small weighing lysimeters filled with soil containing these radionuclides. The plants were harvested at maturity, divided into selected components and radiochemically analyzed by alpha-energy analysis. Soil concentration did not appear to affect the plant uptake of /sup 238/Pu, /sup 239/Pu, /sup 241/Am or /sup 244/Cm for the two levels utilized. The relative plant uptake of the five different transuranics was /sup 237/Np>/sup 244/Cm approximately equal /sup 241/Am>/sup 239/Pu approximately equal/sup 238/Pu. Relative uptake values of Np for various plant parts ranged from 2200 to 45,000 times as great as for Pu, while Am and Cm values were 10-20 times as great. The values for seeds were significantly lower than those for the other aboveground plant parts for all four transuranic elements. The legumes accumulated approx. 10 times more than the grasses. A comparison of the postulated radionuclide content of plants grown in soil contaminated with material from spent liquid metal fast breeder reactor fuels indicated that concentrations of isotopes of Am, Cm and Np would exceed /sup 239/Pu values.

  19. Equipment and applications for gamma spectrometry

    International Nuclear Information System (INIS)

    Hemingway, J.D.

    1986-01-01

    In this article the theoretical aspects of gamma spectroscopy are discussed. Coaxial germanium detectors and planar detectors are described. Applications of gamma spectroscopy to the detection of the exposure of a population to naturally occuring radioactive gases and their daughter products; the accumulation of iodine isotopes in the thyroid and measuring the quantity of 239 Pu in the lungs are discussed. (UK)

  20. Analysis of two dimensional charged particle scintillation using video image processing techniques

    International Nuclear Information System (INIS)

    Sinha, A.; Bhave, B.D.; Singh, B.; Panchal, C.G.; Joshi, V.M.; Shyam, A.; Srinivasan, M.

    1993-01-01

    A novel method for video recording of individual charged particle scintillation images and their offline analysis using digital image processing techniques for obtaining position, time and energy information is presented . Results of an exploratory experiment conducted using 241 Am and 239 Pu alpha sources are presented. (author). 3 figs., 4 tabs

  1. Integral decay-heat measurements and comparisons to ENDF/B--IV and V

    International Nuclear Information System (INIS)

    England, T.R.; Schenter, R.E.; Schmittroth, F.

    Results from recent integral decay-power experiments are presented and compared with summation calculations. The experiments include the decay power following thermal fission of 233 U, 235 U, and 239 Pu. The summation calculations use ENDF/B-IV decay data and yields from Versions IV and V. Limited comparisons of experimental β and γ spectra with summation calculations using ENDF/B-IV are included. Generalized least-squares methods are applied to the recent 235 U and 239 Pu decay-power experiments and summation calculations to arrive at evaluated values and uncertainties. Results for 235 U imply uncertainties less than 2% (1 sigma) for the ''infinite'' exposure case for all cooling times greater than 10 seconds. The uncertainties for 239 Pu are larger. Accurate analytical representations of the decay power are presented for 235 , 238 U, and 239 Pu for use in light-water reactors and as the nominal values in the new ANS 5.1 Draft Standard (1978). Comparisons of the nominal values with ENDF/B-IV and the 1973 ANS Draft Standard in current use are included. Gas content, important to decay-heat experiments, and absorption effects on decay power are reviewed. 37 figures, 8 tables

  2. Adsorption of some radionuclides on kaolinite mineral surface

    International Nuclear Information System (INIS)

    Hafez, M.B.; Said, F.I.A.

    1986-01-01

    Fixation of 187 Cs(I), 144 Ce(III), 90 Sr(II), 233 U(VI), 239 Pu(IV) and 211 Am(III) from aqueous and phosphate media on kaolinite was studied. The fixation of the nuclides on the mineral was found to depend on the pH and the hydrolytic behaviour of the elements

  3. Natural Pu-traces within the continental crust

    International Nuclear Information System (INIS)

    Ganz, M.; Barth, H.; Fuest, M.; Molzahn, D.; Brandt, R.

    1991-01-01

    Pu-traces are observed in the environmental all over the world, 'man made'-Pu as well as 'natural' Pu ( 239 Pu). 239 Pu occurs within a range of about 10 -12 g Pu/g sample in pitchblende. In the FRG, the deep-drilling project 'KTB, Kontinentales Tiefbohrprogramm', was started with the aim to obtain a very deep hole (14 km). We wanted to establish upper concentration limits for plutonium in samples from KTB. For a first investigation, we obtained a 400 g sample of granite from a pre-drill of KTB. Its Pu-concentration was ≤ (4.5 ± 2.5)x10 -16 g 239 Pu/g sample. To compare this result to the Pu-content in geological brines, we obtained a sample from a borehole at the Salton Sea Geothermal field (Southeastern California). In this sample we found an upper concentration limit of (2.1 ± 1.0)x10 -16 g 239 Pu/g sample. (orig.)

  4. Artificial radionuclides in the atmosphere over Lithuania

    Energy Technology Data Exchange (ETDEWEB)

    Lujaniene, G. [Institute of Physics, Nuclear and Environmental Radioactivity Research Laboratory, Savanoriu 231, LT-02300 Vilnius (Lithuania)], E-mail: lujaniene@ar.fi.lt; Aninkevicius, V. [Semiconductor Physics Institute, A. Gostauto 11, LT-01108 Vilnius (Lithuania); Lujanas, V. [Institute of Physics, Nuclear and Environmental Radioactivity Research Laboratory, Savanoriu 231, LT-02300 Vilnius (Lithuania)

    2009-02-15

    Measurements of airborne radioactive aerosol concentration were carried out on the basis of 1-3 days samples after the Chernobyl disaster and during the period of 1992-2003. Transport of 'hot' particles of different composition resulted in the high activity concentrations of {sup 137}Cs, {sup 238}Pu, {sup 239,240}Pu and {sup 241}Am in the atmosphere in Vilnius at the end of April 1986. The {sup 240}Pu/{sup 239}Pu atom ratio showed clear evidence of non-global plutonium originating from the Chernobyl accident in the atmosphere over Lithuania. The {sup 240}Pu/{sup 239}Pu atom ratio ranged from 0.14 to 0.40 in monthly samples in Vilnius in 1995-2003. An increase in activity concentration of {sup 137}Cs by a factor of 100 (up to 300 {mu}Bq/m{sup 3}) was found following forest fires in the Ukraine and Belarus. However, no transport of the Chernobyl plutonium was observed and the {sup 240}Pu/{sup 239}Pu atom ratio in samples collected during the forest fires was found to be 0.229 and 0.185, respectively. The exponential decrease in the {sup 240}Pu/{sup 239}Pu atom ratio from 0.30 to 0.19 (mean values) was observed in 1995-2003.

  5. Contamination of living environment and human organism with plutonium

    International Nuclear Information System (INIS)

    Benes, J.

    1981-01-01

    The applicability of 239 Pu in nuclear power is discussed. The radiotoxic properties of plutonium, its tissue distribution and the effects of internal and external contamination are described. The contamination of the atmosphere, water, and soil with plutonium isotopes is discussed. Dosimetry is described of plutonium in the living and working environments as is plutonium determination in the human organism. (H.S.)

  6. Comparison of plutonium systemic distribution in rats and dogs with published data in humans.

    Science.gov (United States)

    Melo, Dunstana R; Weber, Waylon; Doyle-Eisele, Melanie; Guilmette, Raymond A

    2014-11-01

    This manuscript compares the behavior of monomeric (239)Pu(4+)-citrate injected intravenously in rats and dogs with a comparison of available humans' data. The experimental design for these two studies consisted of eight groups sacrificed at predetermined time-points post exposure. All organs and tissues as well as daily urinary and fecal excretion were analyzed. Liver and skeleton were the organs with the highest (239)Pu uptake in both species; 76% in dogs and 70% in rats at 24 hours (h) post IV administration. By the end of the study (28 days, d), the activity in skeleton and liver was 85% in dogs and 65% in rats. The urinary excretion function seems to be similar for rats, dogs and humans but the daily fecal to urinary excretion ratio differs between species. A rapid clearance from the liver of rats was observed compared to dogs. Skeleton-to-liver ratios are variable between species. Urinary and fecal excretion patterns for dogs are consistent with human data, indicating that dogs seem to represent better the (239)Pu behavior in humans. The data confirm that the better animal model to evaluate the efficacy of (239)Pu chelating compounds is the canine model.

  7. Preface to the injection tables

    International Nuclear Information System (INIS)

    Anon.

    1977-01-01

    Twelve groups of dogs received intravenous injections of various doses of 226 Ra, 239 Pu, 228 Ra, 228 Th, 90 Sr, 241 Am, 249 Cf, or 252 Cf at approximately 17 months of age. The animals were euthanized when death appeared imminent. Data are presented on the calculated radiation dose to the skeleton and pathological changes observed at autopsy

  8. Analysis of Radial Plutonium Isotope Distribution in Irradiated Test MOX Fuel Rods

    Energy Technology Data Exchange (ETDEWEB)

    Oh, Jae Yong; Lee, Byung Ho; Koo, Yang Hyun; Kim, Han Soo

    2009-01-15

    After Rod 3 and 6 (KAERI MOX) were irradiated in the Halden reactor, their post-irradiation examinations are being carried out now. In this report, PLUTON code was implemented to analyze Rod 3 and 6 (KAERI MOX). In the both rods, the ratio of a maximum burnup to an average burnup in the radial distribution was 1.3 and the contents of {sup 239}Pu tended to increase as the radial position approached the periphery of the fuel pellet. The detailed radial distribution of {sup 239}Pu and {sup 240}Pu, however, were somewhat different. To find the reason for this difference, the contents of Pu isotopes were investigated as the burnup increased. The content of {sup 239}Pu decreased with the burnup. The content of {sup 240}Pu increased with the burnup by the 20 GWd/tM but decreased over the 20 GWd/tM. The local burnup of Rod 3 is higher than that of Rod 6 due to the hole penetrated through the fuel rod. The content of {sup 239}Pu decreased more rapidly than that of {sup 240}Pu in the Rod 6 with the increased burnup. It resulted in a radial distribution of {sup 239}Pu and {sup 240}Pu similar to Rod 3. The ratio of Xe to Kr is a parameter to find where the fissions occur in the nuclear fuel. In both Rod 3 and 6, it was 18.3 in the whole fuel rod cross section, which showed that the fissions occurred in the plutonium.

  9. Biological effects like cancer formation due to inhalational exposure to plutonium. What are evident in animal experiments?

    International Nuclear Information System (INIS)

    Oghiso, Yoichi

    2013-01-01

    Literatures on the title subject are reviewed and problems to be solved are given. There are 2 reports of dog experiments of inhaled Pu by Pacific Northwest Laboratory (PNL), which have given results incompatible/compatible with risk assessments hitherto: one with the micro-particle of Pu-nitrate, 239 Pu(NO 3 ) 4 , in which the dog lung is compared with human's by histology and autoradiography, presenting findings that differ from the previous ICRP assumption of the homogeneous distribution in the lung; and the other with 239 PuO 2 , indicating that non-tumorous diseases are agreeable with the determinative effect defined by ICRP. Other literatures have shown that effects of Pu inhalation differ dependently on the solubility of its chemical form and on its isotope ( 239 Pu and 238 Pu). Size of the inhaled Pu particle affects its deposition and thereby its influence on the air tract and other tissues. Rats are also used in Pu inhalation experiments. The significant increase of malignant lung tumor incidence is shown with 239 PuO 2 inhalation at >1 Gy lung absorbed dose by PNL and Inhalation Toxicology Research Institute (ITRI) and by National Institute of Radiological Sciences (NIRS), at >0.7 Gy and not at 239 PuO 2 inhalation in dogs involves the long-term decrease of peripheral lymphocytes, acute radiation pneumonia and chronic fibroid lung at 10-20 Gy, which can be a cause of death. There are many studies of the lung tumor formation at various carcinogenic steps in rats. Problems to be solved for the inhaled Pu compound are the elucidation of accuracy and validity concerning the metabolic parameters, alpha-ray dose assessment, dose rate effects of particle size; the biological factors modifying the metabolism and effect; and the relationship of cancer formation with non-tumorous diseases. (T.T)

  10. Protracted chelate therapy after incorporation of plutonium 239 in rats

    International Nuclear Information System (INIS)

    Gemenetzis, E.

    1976-01-01

    The author has tested in how far 239 Pu can be mobilized by Ca and Zn, Desfenioxamin B(DFDA) and by combined doses of Ca-DTPA and DFDA. The pre-experiment covered the 239 Pu-metabolism in untreated male and female rats and the distribution in dependence of the way of application. If treatment is started immediately by multiple chelate doses, the first two injections play the main part in the decorporation of 239 Pu. The combination Ca-DTPA30 + DFDA30 μMol x kg -1 is proved to be the best means of decorporation for the whole body. The efficiency of another therapy depends essentially on the treatment used, a daily treatment showing the best effects. If treatment is started later with multiple chelate doses, the total decorporation efficiency is of less value, especially in the skeleton. Aequimolar doses of Ca-DTPA and Zn-DTPA have the same degree of efficiency. This indicates that during protracted chelate treatment starting later, Ca-DTPA could be substituted by the less toxic Zn-DTPA after incorporation of 239 Pu. These results show that intermittant administration of the week's dose is more efficient than a single chelate administration of the whole week's dose at once. Permanent chelate infusion does not seem necessary in any case since it has the same effect as 3 to 5 injections per week and is difficult to carry out in medical practice. Thus, it seems advisable to divide up the weekly dose into 3-5 injections. In case of a wound contamination, the efficiency of immediate intensive treatment depends on the 239 Pu compound used, on the chelate used, and on its dosage. (orig.) [de

  11. The effect of varying physical and chemical characteristics of inhaled plutonium aerosols on metabolism and excretion

    International Nuclear Information System (INIS)

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

    1976-01-01

    The effects of different chemical and physical parameters of plutonium aerosols on lung retention, tissue distribution and excretion patterns were evaluated in beagle dogs. Polydisperse aerosols of 239 Pu of different chemical form were produced by heating droplets nebulized from a solution of 239 PuIV in 1M HC1 to temperatures ranging from 325 0 C to 1150 0 C. Droplets containing 238 Pu(OH) 4 were treated at 1150 0 C and the resultant polydisperse aerosol used or separated into monodisperse size groups. Beagle dogs were exposed by inhalation to provide initial lung burdens in the range of 0.75 to 1.0μCi. The aerosols were characterized as to particle size and size distribution, and an in-vitro solubility measurement was made on samples of the aerosol from each animal exposure. Different production temperatures for the 239 Pu aerosols resulted in lung retention half-times that increased as the production temperature increased. The 239 Pu tissue distribution and urinary excretion patterns were correlated with lung retention. Faecal excretion was greater for aerosols produced at lower temperatures. Lung retention half-times for 238 Pu monodisperse aerosols were not greatly different from particle sizes of 0.8 and 1.9μm activity median aerodynamic diameter (AMAD). The third monodisperse aerosol intended to be 3.0μm AMAD had a bimodal particle size distribution and contained a significant fraction of readily soluble material. The 238 Pu polydisperse aerosol had a slightly lower lung retention, increased urinary excretion and translocation to tissues than the comparable 239 Pu polydisperse material. This study serves to emphasize the importance of complete analysis of the aerosol material as well as early excretion data following accidental human exposure to aerosols containing plutonium. The role of chemical form and aerosol particle size in evaluation of such cases is discussed. (author)

  12. Ultra-trace plutonium determination in small volume seawater by sector field inductively coupled plasma mass spectrometry with application to Fukushima seawater samples.

    Science.gov (United States)

    Bu, Wenting; Zheng, Jian; Guo, Qiuju; Aono, Tatsuo; Tagami, Keiko; Uchida, Shigeo; Tazoe, Hirofumi; Yamada, Masatoshi

    2014-04-11

    Long-term monitoring of Pu isotopes in seawater is required for assessing Pu contamination in the marine environment from the Fukushima Dai-ichi Nuclear Power Plant accident. In this study, we established an accurate and precise analytical method based on anion-exchange chromatography and SF-ICP-MS. This method was able to determine Pu isotopes in seawater samples with small volumes (20-60L). The U decontamination factor was 3×10(7)-1×10(8), which provided sufficient removal of interfering U from the seawater samples. The estimated limits of detection for (239)Pu and (240)Pu were 0.11fgmL(-1) and 0.08fgmL(-1), respectively, which corresponded to 0.01mBqm(-3) for (239)Pu and 0.03mBqm(-3) for (240)Pu when a 20L volume of seawater was measured. We achieved good precision (2.9%) and accuracy (0.8%) for measurement of the (240)Pu/(239)Pu atom ratio in the standard Pu solution with a (239)Pu concentration of 11fgmL(-1) and (240)Pu concentration of 2.7fgmL(-1). Seawater reference materials were used for the method validation and both the (239+240)Pu activities and (240)Pu/(239)Pu atom ratios agreed well with the expected values. Surface and bottom seawater samples collected off Fukushima in the western North Pacific since March 2011 were analyzed. Our results suggested that there was no significant variation of the Pu distribution in seawater in the investigated areas compared to the distribution before the accident. Copyright © 2014 Elsevier B.V. All rights reserved.

  13. Plutonium 239 retention in former workers of the Thule base

    International Nuclear Information System (INIS)

    Juul-Jensen, P.; Ulbak, K.

    1988-07-01

    In a memorandum of 1987 on a comprehensive health examination of persons employed at Thule air-base at the time of the crash of a nuclear-armed B-52 bomber in 1968, the National Board of Health suggested performing analyses for plutonium of urinesamples from 50-100 selected persons. This programme was carried out during the winter 1987-88. Collection of samples and evaluation of results were done by the National Institute of Radiation Hygiene. Department of Health Physics, National Laboratory Risoe, made the analyses. Included in the group were persons, who according to records from 1968 were judged to have had above-average potential for uptake of plutonium, as well as s number of persons, who before the summer 1987 had approached the social services and/or the Department of Dermatology, Marselisborg Hospital, with complaints of health effects attributed to the work at Thule air-base. 62 persons were included and results from the analyses of 53 24-hour-samples of urine, as well as from a number of control- and standard are presented. The technique used for the analysis had a minimum detectable activity for 239 Pu of 200 μBq per sample. Consequently, according to internationally recognized models for uptake, distribution and retention of plutonium in the human organism, it is possible in 1988 to recognize an intake by inhalation in 1968 of 300 Bq 239 Pu . No sample was found to contain 239 Pu . So the results indicate, that any intake of 239 Pu by the persons here involved, as a consequence of their work at Thule airbase in 1968, did not exceed 300 Bq. An intake of 300 Bq 239 Pu can be evaluated to result in a 50-year committed dose equivalent of 20 mSv. The current dose-limit for occupationally exposed persons is 50 mSv/y. (author)

  14. Book of abstracts of the 3rd International conference and the 3rd International School for young scientists Interaction of hydrogen isotopes with structural materials. IHISM-07; Tezisy dokladov Tret'ej mezhdunarodnoj konferentsii i Tret'ej mezhdunarodnoj Shkoly molodykh uchenykh i spetsialistov Vzaimodejstvie izotopov vodoroda s konstruktsionnymi materialami. IHISM-07

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The book involves abstracts of presentations at the 3rd International Conference and the 3rd International School for Young Scientists Interaction of Hydrogen Isotopes with Structural Materials (IHISM-07). The activities of Russian and foreign scientific centers associated with the use of hydrogen isotopes in power engineering, national economy and basic research are considered. The presentations cover the following areas: kinetics and interaction between hydrogen isotopes and solids including effects of radiogenic helium accumulation, hydrides and hydride transformations; structural transformations and mechanical properties; equipment and research techniques.

  15. A 4{pi} Anticoincidence Arrangement for Measurements of Beta-Ray Emitting Isotopes; Montage a Anticoiencidence 4{pi} pour la Mesure des Radioisotopes Emetteurs Beta; 4{pi} sistema schetchikov antisovpadenij dlya izmerenij beta-izluchayushchikh izotopov; Aparato de Recuento 4{pi} en Anticoincidencia para Medir Emisores Beta

    Energy Technology Data Exchange (ETDEWEB)

    Srdoc, D. [Institute ' ' Ruder Boskovic' ' , Zagreb, Yugoslavia (Croatia)

    1965-10-15

    A 4{pi} anticoincidence, low-background counting system consisting of two specially designed parallel plate counters and a bridge anticoincidence circuit is described. Each counter is of a flat, mica window ''pancake'' type. The diameter of the counters is much larger than the gap between the plates. Good counting properties are obtained in spite of the unusual counter geometry, owing to the flexibility of the counter shape design when a neon-halogen mixture is used. The counters are so arranged that both windows face the sample, leaving a narrow slit for the sample holder. The sample is spread on a thin metalized plastic film. The pulses from both counters due to beta-particles coming from the sample are recorded, giving a 4{pi} counting geometry. The pulses due to cosmic particles triggering both counters simultaneously cancel out in a simple bridge anticoincidence arrangement, thus eliminating the need for an electronic circuit. Furthermore, the parallel plate counters used here for beta-particle counting possess a markedly reduced sensitivity to gamma-rays near the threshold voltage, resulting in a further lowering of the background. Sources of beta-particles of higher energies, as well as gamma-ray sources, can also be measured by the described system, because in the proposed geometry there is no possibility of triggering both counters simultaneously, as is the case with the conventional guard-counter arrangements. (author) [French] Le memoire decrit un ensemble de mesure a anticolhcidence 4{pi}, ayant un faible bruit de fond, compose de deux compteurs speciaux a plateaux paralleles relies par un pont d'anticofncidence. Ces deux compteurs sont de type circulaire plat a fenetre de mica. Le diametre du compteur est tres superieur a l'espace entre les plaques. Malgre sa geometrie inusitee, l'appareil a des proprietes de comptage satisfaisantes en raison de la souplesse que lui conferent ses caracteristiques lorsqu'on utilise un melange halogene-neon. Les compteurs sont disposes de maniere que les fenetres se trouvent l'une et l'autre en face de l'echantillon, un espace etroit etant menage pour le porte-echantillon. L'echantillon est etale sur une mince pellicule de matiere plastique metallisee. Les impulsions fournies par les deux compteurs en presence des particules beta provenant de l'echantillon sont enregistrees, donnant une geometrie de comptage 4{pi}. Les impulsions dues aux particules cosmiques actionnant les deux compteurs simultanement sont annulees par un simple dispositif d'anticofncidence a pont, ce qui supprime la necessite d'un circuit electronique selecteur. En outre, les compteurs a plateaux paralleles utilises pour la mesure des particules beta sont peu sensibles aux rayonnements gamma a proximite du seuil de tension, ce qui contribue a reduire encore le bruit de fond. Le montage decrit permet aussi de mesurer l'activite de sources beta de haute energie et de sources gamma, etant donne que la geometrie proposee empeche le declenchement simultane des deux compteurs, lequel se produit, par contre, dans les ensembles de comptage classiques a anneau de garde. (author) [Spanish] La memoria describe un aparato de recuento 4{pi} en anticoincidencia, de baja actividad de fondo, formado por dos contadores especiales de placas paralelas y un circuito de anticoincidencia en puente. Los contadores son del tipo 'oblea', planos, con ventana de mica. Su diametro es mucho mayor que el espacio que media entre las placas. Pese a la geometria peculiar de los contadores sus propiedades de recuento son satisfactorias gracias a la flexibilidad lograda al emplear una mezcla de neon y halogeno. Los contadores estan dispuestos de manera que ambas ventanas miran hacia la muestra, dejando una ranura estrecha para el portamuestras. La muestra se extiende sobre una delgada pelicula de material plastico metalizado. Se registran los impulsos que originan en ambos contadores las particulas beta emitidas por la muestra, obteniendose una geometria de recuento 4{pi}, Los rayos cosmicos disparan simultaneamente ambos contadores y los impulsos a que dan lugar se anulan en un sencillo dispositivo de anticoincidencia en puente, merced al cual se puede prescindir de un circuito electronico. Ademas, los contadores de placas paralelas que se emplean para el recuento de particulas beta poseen una sensibilidad notablemente reducida frente a los rayos gamma en las proximidades de la tension umbral, lo que aminora aun mas la actividad de fondo. El sistema descrito permite medir fuentes beta de energias mas elevadas y fuentes gamma dado que la geometria propuesta impide que ambos contadores sean disparados simultaneamente, como sucederia con los aparatos convencionales de contadores protegidos. (author) [Russian] Opisyvaetsja 4{pi} sistema schetchikov antisovpadenij s nizkim fonom, sostojashhaja iz 2 special'no skonstruirovannyh schetchikov s parallel'nymi plastinami i mostovoj shemy scheta antisovpadenij. Kazhdyj schetchik predstavljaet soboj plastinu so sljudjanym okoshkom, imejushhuju toroidal'no-diskovuju formu. Diametr schetchikov namnogo prevyshaet rasstojanie mezhdu plastinami. Poluchaetsja horoshaja schetnaja harakteristika, nesmotrja na neobychnuju geometriju schetchika, blagodarja gibkoj konstrukcii formy schetchika, kogda ispol'zuetsja neono-gelogennaja smes'. Schetchiki raspolagajut takim obrazom, chto oba okoshka obrashheny v storonu obrazca, pri jetom ostaetsja uzkaja shhel' dlja derzhatelja obrazca. Obrazec nanosjat na tonkuju plastmassovuju plenku s metallicheskoj osnovoj. Registrirujut impul'sy iz oboih schetchikov, voznikajushhie za schet beta-chastic, kotorye ispuskaet obrazec, v rezul'tate chego poluchaetsja 4{pi} geometrija scheta. Impul'sy za schet kosmicheskih chastic, zapuskajushhie oba schetchika odnovremenno, pogashajutsja v prostoj mostovoj sisteme schetchikov antisovpadenij i tem samym ustranjaetsja neobhodimost' v jelektronnoj sheme. Krome togo, schetchiki s parallel'nymi plastinami, kotorye ispol'zujutsja zdes' dlja scheta beta-chastic, imejut javno oslablennuju chuvstvitel'nost' k gamma-izlucheniju vblizi porogovogo naprjazhenija, v rezul'tate chego proishodit dal'nejshee snizhenie fona. Istochniki beta-chastic s bolee vysokimi jenergijami, a takzhe istochniki gamma-izluchenija mozhno tozhe izmerit' s pomoshh'ju opisannoj sistemy, poskol'ku v predlagaemoj geometrii otsutstvuet vsjakaja vozmozhnost' odnovremennogo zapuska oboih schetchikov, kak jeto imeet mesto v obychnyh sistemah schetchikov s blokirovkoj. (author)

  16. Some possible uses of radioisotopes in the rubber industry; Certaines possibilites d'emploi des radioisotopes dans l'industrie du caoutchouc; Nekotorye vozmozhnosti ispol'zovaniya radioaktivnykh izotopov v rezinovoj promyshlennosti; Algunas posibilidades de utilizacion de los radioisotopos en la industria del caucho

    Energy Technology Data Exchange (ETDEWEB)

    Shimorda, J; Mozhishek, M; Klimanek, L; Staroba, J [Nauchno-Issledovatel' skij Institut Tekhnologii Reziny i Plastmass (NIITRP), Gorod Gotval' dov, Chekhoslovatskaya Sotsialisticheskaya Respublika (Czech Republic)

    1962-01-15

    A method is described for using beta-emitters (Tl{sup 204} and S{sup 35}) for measuring the wearing qualities of motor-vehicle tyres, checking the homogeneity of tyre rubber, and non-contact thickness-gauging of rubberized fabrics. (author) [French] Le memoire expose une methode permettant d'employer des emetteurs beta ({sup 204}Tl et {sup 35}S) pour la mesure de la resistance des pneumatiques d'automobiles, le controle de l'uniformite du caoutchouc des pneus et la mesure sans contact de l'epaisseur des tissus caoutchoutes. (author) [Spanish] Los autores describen un metodo de utilizacion de emisores {beta} ({sup 204}Tl y {sup 35}S) para la medicion de la resistencia al desgaste de los neumaticos de automovil para la verificacion de la homogeneidad del caucho destinado a la fabricacion de neumaticos y para la medicion a distancia del espesor de las telas cauchutadas. (author) [Russian] Opisana metodika ispol'zovaniya beta-izluchatelej (Tl{sup 204} i S{sup 35}) dlya izmereniya velichiny iznosostojkosti avtomobil'nykh shin, dlya kontrolya gomogennosti shinnykh rezin i dlya beskontaktnogo izmereniya tolshchiny obrezinennykh tkanej. (author)

  17. Temporal record of Pu isotopes in inter-tidal sediments from the northeastern Irish Sea

    Energy Technology Data Exchange (ETDEWEB)

    Lindahl, Patric, E-mail: patriclindahl@yahoo.com [School of Geography, Earth and Environmental Sciences, University of Plymouth, Drake Circus, Plymouth PL4 8AA (United Kingdom); Worsfold, Paul; Keith-Roach, Miranda [School of Geography, Earth and Environmental Sciences, University of Plymouth, Drake Circus, Plymouth PL4 8AA (United Kingdom); Andersen, Morten B. [Bristol Isotope Group, School of Earth Sciences, University of Bristol, Wills Memorial Building, Bristol BS8 1RJ (United Kingdom); Kershaw, Peter; Leonard, Kins [The Centre for Environment, Fisheries and Aquaculture Science, Lowestoft Laboratory, Pakefield Road, Suffolk NR33 0HT (United Kingdom); Choi, Min-Seok [Division of Earth and Environmental Science, Korea Basic Science Institute, 113 Gwahangno, Yusung-gu, Daejon 305-333 (Korea, Republic of); Boust, Dominique [Laboratoire de Radioecologie, Institut de Radioprotection et de Surete Nucleaire, BP 10, 50130 Cherbourg-Octeville (France); Lesueur, Patrick [University of Caen Basse Normandie, M2C UMR CNRS 6143, 14000 Caen (France)

    2011-11-01

    A depth profile of {sup 239}Pu and {sup 240}Pu specific activities and isotope ratios was determined in an inter-tidal sediment core from the Esk Estuary in the northeastern Irish Sea. The study site has been impacted with plutonium through routine radionuclide discharges from the Sellafield nuclear reprocessing plant in Cumbria, NW England. A pronounced sub-surface maximum of {approx} 10 kBq kg{sup -1} was observed for {sup 239+240}Pu, corresponding to the peak in Pu discharge from Sellafield in 1973, with a decreasing trend with depth down to {approx} 0.04 kBq kg{sup -1} in the deeper layers. The depth profile of {sup 239+240}Pu specific activities together with results from gamma-ray spectrometry for {sup 137}Cs and {sup 241}Am was compared with reported releases from the Sellafield plant in order to estimate a reliable sediment chronology. The upper layers (1992 onwards) showed higher {sup 239+240}Pu specific activities than would be expected from the direct input of annual Sellafield discharges, indicating that the main input of Pu is from the time-integrated contaminated mud patch of the northeastern Irish Sea. The {sup 240}Pu/{sup 239}Pu atom ratios ranged from {approx} 0.03 in the deepest layers to > 0.20 in the sub-surface layers with an activity-weighted average of 0.181. The decreasing {sup 240}Pu/{sup 239}Pu atom ratio with depth reflects the changing nature of operations at the Sellafield plant from weapons-grade Pu production to reprocessing spent nuclear fuel with higher burn-up times in the late 1950s. In addition, recent annual {sup 240}Pu/{sup 239}Pu atom ratios in winkles collected during 2003-2008 from three stations along the Cumbrian coastline showed no significant spatial or temporal differences with an overall average of 0.204, which supports the hypothesis of diluted Pu input from the contaminated mud patch. - Highlights: {yields} Depth profiles of {sup 239}Pu and {sup 240}Pu determined in a northeastern Irish Sea sediment. {yields

  18. Neutron absorbers and detector types for spent fuel verification using the self-interrogation neutron resonance densitometry

    Energy Technology Data Exchange (ETDEWEB)

    Rossa, Riccardo, E-mail: rrossa@sckcen.be [SCK-CEN, Belgian Nuclear Research Centre, Boeretang, 200, B2400 Mol (Belgium); Université libre de Bruxelles, Ecole polytechnique de Bruxelles, Service de Métrologie Nucléaire (CP 165/84), Avenue F.D. Roosevelt, 50, B1050 Brussels (Belgium); Borella, Alessandro, E-mail: aborella@sckcen.be [SCK-CEN, Belgian Nuclear Research Centre, Boeretang, 200, B2400 Mol (Belgium); Labeau, Pierre-Etienne, E-mail: pelabeau@ulb.ac.be [Université libre de Bruxelles, Ecole polytechnique de Bruxelles, Service de Métrologie Nucléaire (CP 165/84), Avenue F.D. Roosevelt, 50, B1050 Brussels (Belgium); Pauly, Nicolas, E-mail: nipauly@ulb.ac.be [Université libre de Bruxelles, Ecole polytechnique de Bruxelles, Service de Métrologie Nucléaire (CP 165/84), Avenue F.D. Roosevelt, 50, B1050 Brussels (Belgium); Meer, Klaas van der, E-mail: kvdmeer@sckcen.be [SCK-CEN, Belgian Nuclear Research Centre, Boeretang, 200, B2400 Mol (Belgium)

    2015-08-11

    The Self-Interrogation Neutron Resonance Densitometry (SINRD) is a passive non-destructive assay (NDA) technique that is proposed for the direct measurement of {sup 239}Pu in a spent fuel assembly. The insertion of neutron detectors wrapped with different neutron absorbing materials, or neutron filters, in the central guide tube of a PWR fuel assembly is envisaged to measure the neutron flux in the energy region close to the 0.3 eV resonance of {sup 239}Pu. In addition, the measurement of the fast neutron flux is foreseen. This paper is focused on the determination of the Gd and Cd neutron filters thickness to maximize the detection of neutrons within the resonance region. Moreover, several detector types are compared to identify the optimal condition and to assess the expected total neutron counts that can be obtained with the SINRD measurements. Results from Monte Carlo simulations showed that ranges between 0.1–0.3 mm and 0.5–1.0 mm ensure the optimal conditions for the Gd and Cd filters, respectively. Moreover, a {sup 239}Pu fission chamber is better suited to measure neutrons close to the 0.3 eV resonance and it has the highest sensitivity to {sup 239}Pu, in comparison with a {sup 235}U fission chamber, with a {sup 3}He proportional counter, and with a {sup 10}B proportional counter. The use of a thin Gd filter and a thick Cd filter is suggested for the {sup 239}Pu and {sup 235}U fission chambers to increase the total counts achieved in a measurement, while a thick Gd filter and a thin Cd filter are envisaged for the {sup 3}He and {sup 10}B proportional counters to increase the sensitivity to {sup 239}Pu. We concluded that an optimization process that takes into account measurement time, filters thickness, and detector size is needed to develop a SINRD detector that can meet the requirement for an efficient verification of spent fuel assemblies.

  19. Application of FORSS sensitivity and uncertainty methodology to fast reactor benchmark analysis

    Energy Technology Data Exchange (ETDEWEB)

    Weisbin, C.R.; Marable, J.H.; Lucius, J.L.; Oblow, E.M.; Mynatt, F.R.; Peelle, R.W.; Perey, F.G.

    1976-12-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions, and associated uncertainties. This paper presents the theory and code description as well as the first results of applying FORSS to fast reactor benchmarks. Specifically, for various assemblies and reactor performance parameters, the nuclear data sensitivities were computed by nuclide, reaction type, and energy. Comprehensive libraries of energy-dependent coefficients have been developed in a computer retrievable format and released for distribution by RSIC and NNCSC. Uncertainties induced by nuclear data were quantified using preliminary, energy-dependent relative covariance matrices evaluated with ENDF/B-IV expectation values and processed for /sup 238/U(n,f), /sup 238/U(n,..gamma..), /sup 239/Pu(n,f), and /sup 239/Pu(..nu..). Nuclear data accuracy requirements to meet specified performance criteria at minimum experimental cost were determined.

  20. Application of FORSS sensitivity and uncertainty methodology to fast reactor benchmark analysis

    International Nuclear Information System (INIS)

    Weisbin, C.R.; Marable, J.H.; Lucius, J.L.; Oblow, E.M.; Mynatt, F.R.; Peelle, R.W.; Perey, F.G.

    1976-12-01

    FORSS is a code system used to study relationships between nuclear reaction cross sections, integral experiments, reactor performance parameter predictions, and associated uncertainties. This paper presents the theory and code description as well as the first results of applying FORSS to fast reactor benchmarks. Specifically, for various assemblies and reactor performance parameters, the nuclear data sensitivities were computed by nuclide, reaction type, and energy. Comprehensive libraries of energy-dependent coefficients have been developed in a computer retrievable format and released for distribution by RSIC and NNCSC. Uncertainties induced by nuclear data were quantified using preliminary, energy-dependent relative covariance matrices evaluated with ENDF/B-IV expectation values and processed for 238 U(n,f), 238 U(n,γ), 239 Pu(n,f), and 239 Pu(ν). Nuclear data accuracy requirements to meet specified performance criteria at minimum experimental cost were determined

  1. Different spectra with the same neutron source

    International Nuclear Information System (INIS)

    Vega C, H. R.; Ortiz R, J. M.; Hernandez D, V. M.; Martinez B, M. R.; Hernandez A, B.; Ortiz H, A. A.; Mercado, G. A.

    2010-01-01

    Using as source term the spectrum of a 239 Pu-Be source several neutron spectra have been calculated using Monte Carlo methods. The source term was located in the centre of spherical moderators made of light water, heavy water and polyethylene of different diameters. Also a 239 Pu-Be source was used to measure its neutron spectrum, bare and moderated by water. The neutron spectra were measured at 100 cm with a Bonner spheres spectrometer. Monte Carlo calculations were used to calculate the neutron spectra of bare and water-moderated spectra that were compared with those measured with the spectrometer. Resulting spectra are similar to those found in power plants with PWR, BWR and Candu nuclear reactors. Beside the spectra the dosimetric features were determined. Using moderators and a single neutron source can be produced neutron spectra alike those found in workplaces, this neutron fields can be utilized to calibrate neutron dosimeters and area monitors. (Author)

  2. The fission cross section ratios and error analysis for ten thorium, uranium, neptunium and plutonium isotopes at 14. 74 MeV neutron energy

    Energy Technology Data Exchange (ETDEWEB)

    Meadows, J.W.

    1987-03-01

    The error information from the recent measurements of the fission cross section ratios of nine isotopes, /sup 230/Th, /sup 232/Th, /sup 233/U, /sup 234/U, /sup 236/U, /sup 238/U, /sup 237/Np, /sup 239/Pu, and /sup 242/Pu, relative to /sup 235/U at 14.74 MeV neutron energy was used to calculate their correlations. The remaining 36 non-trivial and non-reciprocal cross section ratios and their errors were determined and compared to evaluated (ENDF/B-V) values. There are serious differences but it was concluded that the reduction of three of the evaluated cross sections would remove most of them. The cross sections to be reduced are /sup 230/Th - 13%, /sup 237/Np - 9.6% and /sup 239/Pu - 7.6%. 5 refs., 6 tabs.

  3. Linear compartment model of plutonium dynamics in a deciduous forest ecosystem

    International Nuclear Information System (INIS)

    Garten, C.T. Jr.; Gardner, R.H.; Dahlman, R.C.

    1977-01-01

    Systems ecology techniques have been useful in simulating the fate and dynamics of radionuclides in forest ecosystems. The applications of systems models in this context are twofold: projection of the time-dependent distribution of radioisotopes among various ecosystems components, and manipulation of the modeled system to determine the sensitivity of components to variation in transfer coefficients and, thereby, identify critical fluxes affecting system behavior. The present paper describes a systems model that projects the possible fate of plutonium in a deciduous forest ecosystem. The isotopes of interest are 239 Pu and 240 Pu which have physical half lives of 2.44 x 10 4 and 6540 years, respectively. These isotopes are indistinguishable by alpha spectrometry hence 239 Pu is used to refer to both

  4. Expression of Kirsten murine sarcoma virus sequences in Beagle dog tissues

    Energy Technology Data Exchange (ETDEWEB)

    Kerkof, P R; Kelly, G

    1988-12-01

    Labeled cDNA synthesized from RNA extracted from {sup 238}PuO{sub 2}-, {sup 239}PuO{sub 2}-, and {sup 90}Sr-induced lung tumors in Beagle dogs, from nontumor tissue from {sup 239}PuO{sub 2}-exposed dogs, and from unexposed dog lung and liver tissue produces strong hybridization signals with a plasmid (pKSma) that contains Kirsten murine sarcoma virus (KMSV) sequences. At least 90 percent of the KMSV sequences are expressed in these dog tissues, including sequences corresponding to p21 K-ras, qp70 envelope glycoprotein, and at least one other proviral sequence. The expression of Kirsten ras and other sarcoma virus sequences may have important implications for the interpretation of carcinogenesis studies in these dogs. (author)

  5. Nuclear Data Parameter Adjustment BNL-INL

    International Nuclear Information System (INIS)

    Palmiotti, G.; Hoblit, S.; Herman, M.; Nobre, G.P.A.; Palumbo, A.; Hiruta, H.; Salvatores, M.

    2013-01-01

    This presentation reports on the consistent adjustment of nuclear data parameters performed within a BNL-INL collaboration. The main advantage compared to the classical adjustment of multigroup constants is to provide final nuclear data constrained by the nuclear reaction theory and consistent with both differential and integral measurements. The feasibility of a single-isotope assimilation was tested on a few priority materials ( 23 Na, 56 Fe, 105 Pd, 235,238 U, 239 Pu) using a selection of clean integral experiments. The multi-isotope assimilation is under study for the Big-3 ( 235,238 U, 239 Pu). This work shows that a consistent assimilation is feasible, but there are pitfalls to avoid (e.g. non-linearity, cross section fluctuations) and prerequisites (e.g. realistic covariances, good prior, realistic weighting of differential and integral experiments). Finally, only all experimental information combined with the state of the art modelling may provide a 'right' answer

  6. Investigation of plutonium behaviour in artificially contaminated soil

    International Nuclear Information System (INIS)

    Luksiene, B.; Druteikiene, R.

    2006-01-01

    The vertical migration and transformation of plutonium chemical forms artificially supplied to sandy loam columns after its exposure to natural conditions for about one year was investigated. An analysis of artificially contaminated samples after one year had shown that 81% of 239 Pu 4+ and 44% of 239 Pu 3+ were accumulated in the 0-5 cm layer of sandy loam. The data of sequential analysis of the same type of soil at the adequate artificial contamination level after one month exposure under laboratory conditions are presented as well. Pu 239 binding to soil geochemical fractions was rather uneven. The largest amount of Pu 239 (60%) was determined in the residual fraction. Consequently, it can be assumed that organic substances and some inorganic compounds, which usually are the main components of a residual fraction, affects the retention and migration of plutonium in the soil. (authors)

  7. Experimental investigation of mass efficiency curve for alpha radioactivity counting using a gas-proportional detector

    International Nuclear Information System (INIS)

    Semkow, T.M.; Bari, A.; Parekh, P.P.; Haines, D.K.; Gao, H.; Bolden, A.N.; Dahms, K.S.; Scarpitta, S.C.; Thern, R.E.; Velazquez, S.

    2004-01-01

    Gross α counting of evaporated water residues offers a simple method for screening α radioactivity in water for both public health and emergency purposes. The evaporation process for water has been improved by using a combination of roughening of the surface of counting planchettes, two-stage evaporation, and temperature-controlled block heating. The efficiency of the gas-proportional detector for α-particle detection in water residues was studied as a function of sample mass-thickness in the range between 0.1 and 13 mg cm -2 . The effect of α energy on the efficiency, as well as moisture absorption on the samples, were studied using 230 Th, 238 U, 239 Pu, 241 Am, and 244 Cm radionuclides. Also, α-to-β crosstalk was investigated as a function of sample mass for 230 Th, 239 Pu, 210 Po, 241 Am, and 244 Cm. The improved method can also be applied for gross α detection in biological fluids

  8. Study of DD versus DT fusion fuel cycles for different fusion-fission hybrid energy systems

    International Nuclear Information System (INIS)

    Gohar, Y.; Baker, C.C.

    1981-01-01

    A study was performed to investigate the characteristics of an energy system to produce fissile fuel for fission reactors. DD and DT fusion reactors were examined in this study with either a thorium or uranium blanket for each fusion reactor. Various fuel cycles were examined for light-water reactors including the denatured fuel cycles (which may offer proliferation resistance compared to other fuel cycles); these fuel cycles include a uranium fuel cycle with 239 Pu makeup, a thorium fuel cycle with 239 Pu makeup, a denatured uranium fuel cycle with 233 U makeup, and a denatured thorium fuel cycle with 233 U makeup. Four different blankets were considered for this study. The first two blankets have a tritium breeding capability for DT reactors. Lithium oxide (Li 2 O) was used for tritium breeding due to its high lithium density and high temperature capability; however, the use of Li 2 O may result in higher tritium inventories compared to other solid breeders

  9. The Geochemical Behaviour of Tc, Np, and Pu in Spent Nuclear Fuel in an Oxidizing Environment

    Energy Technology Data Exchange (ETDEWEB)

    Buck, Edgar C.; Hanson, Brady D.; McNamara, Bruce K.; R. Giere and P. Stille

    2004-10-01

    Studies at the Nopal and Shinkolowbwe uranium deposits show that the primary uraninite (UO2) altered to a suite of secondary uranyl minerals similar to those observed in corrosion tests with uranium oxide . Although the Nopal I deposit tells us something about the possible fate of uranium, it tells us little about the likely fate of the important long-lived radionuclides; iodine (129I), cesium (135Cs), technetium (99Tc), neptunium (237Np), and plutonium (239Pu). Most performance assessment (PA) models, assume conservatively, that as the UO2 matrix corrodes, the key radionuclides (129I, 99Tc, 237Np, and 239Pu) will be released congruently. In so doing, these PA models force increased reliance on human engineered barriers.

  10. The Geochemical Behavior of Tc, Np, and Pu in Spent Nuclear Fuel in an Oxidizing Environment

    International Nuclear Information System (INIS)

    Buck, Edgar C.; Hanson, Brady D.; McNamara, Bruce K.; R. Giere; P. Stille

    2004-01-01

    Studies at the Nopal and Shinkolowbwe uranium deposits show that the primary uraninite (UO2) altered to a suite of secondary uranyl minerals similar to those observed in corrosion tests with uranium oxide . Although the Nopal I deposit tells us something about the possible fate of uranium, it tells us little about the likely fate of the important long-lived radionuclides; iodine (129I), cesium (135Cs), technetium (99Tc), neptunium (237Np), and plutonium (239Pu). Most performance assessment (PA) models, assume conservatively, that as the UO2 matrix corrodes, the key radionuclides (129I, 99Tc, 237Np, and 239Pu) will be released congruently. In so doing, these PA models force increased reliance on human engineered barriers

  11. Certified reference materials for radionuclides in Bikini Atoll sediment (IAEA-410) and Pacific Ocean sediment (IAEA-412)

    DEFF Research Database (Denmark)

    Pham, M. K.; van Beek, P.; Carvalho, F. P.

    2016-01-01

    The preparation and characterization of certified reference materials (CRMs) for radionuclide content in sediments collected offshore of Bikini Atoll (IAEA-410) and in the open northwest Pacific Ocean (IAEA-412) are described and the results of the certification process are presented. The certified...... radionuclides include: 40K, 210Pb (210Po), 226Ra, 228Ra, 228Th, 232Th, 234U, 238U, 239Pu, 239+240Pu and 241Am for IAEA-410 and 40K, 137Cs, 210Pb (210Po), 226Ra, 228Ra, 228Th, 232Th, 235U, 238U, 239Pu, 240Pu and 239+240Pu for IAEA-412. The CRMs can be used for quality assurance and quality control purposes...

  12. Plutonium interaction with a bacterial strain isolated from the waste isolation pilot plant (WIPP) environment

    International Nuclear Information System (INIS)

    Strietelmeier, B.A.; Kraus, S.M.; Leonard, P.A.; Triay, I.R.

    1996-01-01

    This work was conducted as part of a series of experiments to determine the association and interaction of various actinides with bacteria isolated from the WIPP site. The majority of bacteria that exist at the site are expected to be halophiles, or extreme halophiles, due to the high concentration of salt minerals at the location. Experiments were conducted to determine the toxicity of plutonium-n-239, neptunium-237 and americium-243 to several species of these halophiles and the results were reported elsewhere. As an extension of these experiments, we report an investigation of the type of association that occurs between 239 Pu and the isolate WIPP-1A, isolated by staff at Brookhaven National Laboratory, when grown in a high-salt, defined medium. Using scanning electron microscopy (SEM) techniques, we demonstrate a surface association of the 239 Pu with the bacterial cells

  13. Effects of transuranics on pulmonary lymph nodes of rodents

    International Nuclear Information System (INIS)

    Sanders, C.L.

    1976-01-01

    Pulmonary lymph nodes have been suggested as the ''critical'' tissue for insoluble, inhaled transuranic compounds owing to the high concentration of transuranics in these lymph nodes. About 800 rats were given from 0.2 to 3600 nCi of 238 PuO 2 or 239 PuO 2 by inhalation, intratracheal instillation, intrapleural injection, or intraperitoneal injection. From about 1 to 10 percent of deposited plutonium was translocated to pulmonary lymph nodes, the amount depending on the time after deposition and the route of administration; 238 PuO 2 was cleared from pulmonary lymph nodes faster than 239 PuO 2 owing to the greater in vivo solubility of 238 PuO 2 . No primary tumors of pulmonary lymph nodes were observed, indicating that this tissue was not the critical tissue for carcinogenic induction

  14. Transport process of Pu isotope in marginal seas of the western North Pacific Ocean

    Energy Technology Data Exchange (ETDEWEB)

    Yamada, Masatoshi [Department of Radiation Chemistry, Institute of Radiation Emergency Medicine, Hirosaki University, Hirosaki, 036-8564, Aomori (Japan); Zheng, Jian [Research Center for Radiation Protection, National Institute of Radiological Sciences, 4-9-1 Anagawa, Inage, 263-8555, Chiba (Japan)

    2014-07-01

    Significant quantities of Pu isotopes have been released into the marine environment as the result of atmospheric nuclear weapons testing. Most radionuclides globally dispersed in atmospheric nuclear weapons testing were released into the environment during the 1950's and 1960's. In the western North Pacific Ocean, the principal source can be further distinguished as two distinct sources of Pu: close-in tropospheric fallout from nuclear weapons testing at the Pacific Proving Grounds (PPG) in the Marshall Islands and global stratospheric fallout. Since the {sup 240}Pu/{sup 239}Pu atom ratio is characteristic for the Pu emission source, information on Pu isotopic signature is very useful to better understand the transport process in the oceans and to identify the sources of Pu. The mean atom ratio of {sup 240}Pu/{sup 239}Pu from the global stratospheric fallout is 0.180 ±0.014 based on soil sample data, whereas that from close-in tropospheric fallout from the PPG is 0.33 - 0.36. The {sup 240}Pu/{sup 239}Pu atom ratios in seawater samples collected in marginal seas of the western North Pacific Ocean will provide important and useful data for understanding the process controlling Pu transport and for distinguishing future Pu sources. The objectives of this study were to measure the {sup 239+240}Pu concentrations and {sup 240}Pu/{sup 239}Pu atom ratios in seawater from the Sea of Okhotsk, Japan Sea, South China Sea and Sulu Sea and to discuss the transport process of Pu. Large-volume seawater samples (250 L each) were collected from the surface to the bottom in marginal seas of the western North Pacific Ocean with acoustically triggered quadruple PVC sampling bottles during the R/V Hakuho-Maru cruise. The {sup 239}Pu and {sup 240}Pu concentrations and {sup 240}Pu/{sup 239}Pu atom ratios were measured with a double-focusing SF-ICP-MS, which was equipped with a guard electrode to eliminate secondary discharge in the plasma and to enhance overall sensitivity. In

  15. Investigation of plutonium behaviour in artificially contaminated soil

    International Nuclear Information System (INIS)

    Lukshiene, B.; Druteikiene, R.

    2006-01-01

    The vertical migration and transformation of plutonium chemical forms artificially supplied to sandy loam columns after its exposure to natural conditions for about one year was investigated. An analysis of artificially contaminated samples after one year had shown that 81% of 239 Pu 4+ and 44% of 239 Pu 3+ were accumulated in the 0-5 cm layer of sandy loam. The data of sequential analysis of the same type of soil at the adequate artificial contamination level after one month exposure under laboratory conditions are presented as well. Pu 239 binding to soil geochemical fractions was rather uneven. The largest amount of Pu 239 (60 %) was determined in the residual fraction. Consequently, it can be assumed that organic substances and some inorganic compounds, which usually are the main components of a residual fraction, affects the retention and migration of plutonium in the soil. (authors)

  16. Plutonium isotopic measurements by gamma-ray spectroscopy

    International Nuclear Information System (INIS)

    Gunnink, R.

    1973-11-01

    A method is reported for analysis of isotopic and total plutonium by detecting and analyzing gamma rays emitted by the sample. A computerized prototype-system was developed and is now being routinely used at the Savannah River Plant for the nondestructive assay of solution samples. The analyses for 238 Pu, 239 Pu, 240 Pu, 241 Pu, and for 241 Am, when it is present, can be made in counting times as short as 10 to 15 minutes under optimum conditions. Comparison of isotopic ratio values with mass spectrometry generally shows agreement within 0.1 percent for 239 Pu and about 1 percent for 240 Pu and 241 Pu. Some preliminary isotopic measurements on solids are also discussed. (U.S.)

  17. Plutonium determination in urine by techniques of mass spectrometry; Determinacion de plutonio en orina por tecnicas de espectrometria de masas

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez M, H. [ININ, Departamento de Quimica, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Yllera de Ll, A., E-mail: hector.hernandez520@gmail.com [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Departamento de Medio Ambiente, Av. Complutense 22, 28040 Madrid (Spain)

    2013-10-15

    The objective of this study was to develop an analytic method for quantification and plutonium reappraisal in plane tables of alpha spectrometry be means of the mass spectrometry technique of high resolution with plasma source inductively coupled and desolvator Aridus (Aridus-Hr-Icp-Ms) and mass spectrometry with accelerator (AMS). The obtained results were, the recovery percentage of Pu in the plane table was of ∼ 90% and activity minimum detectable obtained with Aridus-Hr-Icp-Ms and AMS was of ∼ 3 and ∼ 0.4 f g of {sup 239}Pu, respectively. Conclusion, the results demonstrate the aptitude of the Aridus-Hr-Icp-Ms and AMS techniques in the Pu reappraisal in plane tables with bigger speed and precision, improving the values notably of the activity minimum detectable that can be obtained with the alpha spectrometry (∼ 50 f g of {sup 239}Pu). (author)

  18. Pathology associated with inhaled plutonium in beagles

    International Nuclear Information System (INIS)

    Dagle, G.E.; Park, J.F.; Weller, R.E.; Ragan, H.A.; Stevens, D.L.

    1986-01-01

    The pathology associated with the inhalation of plutonium was studied in beagle dogs given a single exposure to aerosols of 239 PuO 2 , 238 PuO 2 , or 239 Pu(NO 3 ) 4 . The temporal-spatial relationships between plutonium deposition and the development of lesions in dogs were evaluated up to 11 years, 8 years, or 5 years, respectively, after exposures, resulting in initial lung burdens ranging from ∼2 to ∼5500 nCi. Exposure of the lung to high dose levels produced a spectrum of progressively more severe morphological changes, ranging from radiation pneumonitis to fibrosis. Lung tumors occurred at exposure levels that did not result in early death from radiation pneumonitis or fibrosis. Bronchiolar-alveolar carcinomas, papillary adenocarcinomas, epidermoid carcinomas, and combined epidermoid and adenocarcinomas were observed. Sclerosing tracheobronchial lymphadenitis, radiation osteodystrophy, osteosarcoma, and hepatic adenomatous hyperplasia were the principal extrapulmonary lesions resulting from translocation of plutonium. 15 refs., 2 tabs

  19. Development of an ultra-sensitive detection method for transuranium elements with respect to ocean water samples from Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Hain, Karin Margarete

    2016-03-30

    The development of a detection method for the identification of a possible emission of actinides into the Pacific Ocean by the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, was the major aim of this PhD thesis. It is shown in this work that in addition to the isotopic plutonium ratio {sup 240}Pu/{sup 239}Pu, which is an important signature for different contamination sources, the {sup 241}Pu/{sup 239}Pu ratio has to be determined, to distinguish between a Fukushima entry of actinides and nuclear weapon fallout in the Pacific Ocean. Furthermore, this study was aiming for the improvement of the data on the neptunium ({sup 237}Np) distribution in the ocean. For the detection of the trace concentrations of actinides in the order of mBq/m{sup 3} in a small sample volume of 20 L ocean water, the ultra-sensitive method accelerator mass spectrometry (AMS) was chosen. A chemical separation procedure for Pu and Np based on extraction chromatography was developed using mass spectrometry and radiometric analysis to determine the chemical recovery. {sup 241}Am, which causes isobaric background to {sup 241}Pu in mass spectrometric measurements, was separated with a suppression of at least 10{sup -4} from Pu by this method. The detection method adjusted to Pu and Np was successfully verified by analyzing the concentration of Pu in certified reference material with AMS at the Maier-Leibnitz-Laboratory (MLL) in Munich. Due to a temporary closure of the MLL, 12 sea water samples, collected in autumn 2012, were prepared at the Radiochemie Muenchen and measured at the Vienna Environmental Research Laboratory (VERA). The sampling station closest to the FDNPP was located at a distance of 39.6 km. Three of the samples showed a slightly elevated {sup 240}Pu/{sup 239}Pu ratio of up to 0.23{sup +0.04}{sub -0.03} compared to global fallout ({sup 240}Pu/{sup 239}Pu = 0.180±0.007), whereas all measured {sup 241}Pu/{sup 239}Pu ratios were clearly consistent with nuclear weapon

  20. Comparison of the NaI-CsI phoswich and a hyperpure germanium array for in vivo detection of the actinides

    Energy Technology Data Exchange (ETDEWEB)

    Berger, C D; Goans, R E [Oak Ridge National Lab., TN (USA)

    1981-04-01

    An array of hyperpure germanium detectors has recently been employed at ORNL for the identification and quantification of internally deposited actinides. Its advantages over the phoswich detector - the current state-of-the-art for detection of the actinides - were found to be improved background reduction and superior energy resolution. The germanium system and the currently operating phoswich system are discussed and compared. The improvement in performance of the germanium system over the phoswich system (a factor of 2.5 for /sup 239/Pu and 15.3 for /sup 241/Am) appears to justify the financial investment, particularly when /sup 241/Am is used as an indirect means of detection and measurement of /sup 239/Pu.