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Sample records for 106ru 141ce 144ce

  1. An experimental study of the time dependence of uptake from soil of 137Cs, 106Ru, 144Ce and 99Tc into green vegetables, wheat and potatoes

    In this study the experimental data were analysed using the CEGB's dynamic foodchain model, and were used to validate the relevant part of the model structure, to produce model-specific input data and to identify possible future improvements to the model structure. The root uptake of the specified radionuclides was studied and the concentration levels measured. The data were analysed using a simplified version of the general model. The compartment system incorporated within the model was shown to be capable of reproducing the data for 137Cs, 106Ru and 144Ce to an extent sufficient to justify its use in ingestion radiological dose assessments, but to be less successful in fitting the 99Tc data. The analysis resulted in the production of a well validated set of model-specific input data relevant to UK conditions and agricultural practice differing significantly from values obtained from global literature surveys. Possible future improvements to the model structure were also identified, aimed at providing improved estimates of crop contamination levels for timescales in excess of those considered in this study. (U.K.)

  2. Chromatographic isolation of 144Ce and 144Pr from the wastes of irradiated uranium treatment

    A two-step chromatographic technique was elaborated to isolate 144Ce, 144Pr from a solution of uranium fission products in 6M HNO3. The oxidation to Ce(III) by bromate and selective adsorption of 144Ce(IV) on anion exchange column were used to concentrate and purify 144Ce. Some impurities of uranium, 95Zr, 95Nb, 106Ru remain in 144Ce solution after the first step of its isolation. The final purification is achieved by passing the 6M HNO3 solution of 144Ce(IV) through the HDEHP-coated teflon column. The decontamination factors of 144Ce from main fission products are given. 7.2 mCi of (144Ce+144Pr) are recovered from each gram of irradiated uranium trioxide with the yield greater than 99%. An improvement of known generator was carried out to elute a purer 144Pr from maternal 144Ce(IV) adsorbed on the anion exchange column. (author)

  3. A new 144Ce/144Pr radioisotope generator system

    A miniaturized generator system was developed containing manganese dioxide-coated alumina on which 144Ce is deposited and from which 144Pr is eluted with an aqueous solution of 1% KIO3 in 1 N nitric acid. More than 60% of the 144Pr was recovered with a 99.9% radionuclide purity even after 2000 ml eluant and 1000 1 or air had been passed through the column. (author)

  4. Absolute standardization of 106Ru by anti-coincidence method

    The system of absolute standardization activity of radionuclide by anti-coincidence counting and live-time techniques was implemented at LNMRI in 2008 to reduce the impacts of some influence factors in the determination of the activity with coincidence counting technique used for decades in the lab, for example, the measurement time. With the anti-coincidence system, the variety of radionuclides that can be calibrated by LNMRI was increased, in relation to the type of decay. The objective of this work is the standardization of 106Ru by the method of counting anti-coincidence and estimate its measurement uncertainties. (author)

  5. β-Ray brachytherapy with 106Ru plaques for retinoblastoma

    Purpose: A retrospective analysis of 134 patients who received 106Ru brachytherapy for retinoblastomas (175 tumors in 140 eyes). Treatment and follow-up were analyzed with special emphasis on tumor control organ, preservation, and late complications. Results: Treated tumors had a mean height and diameter of 3.7 ± 1.4 mm and 5.0 ± 2.8 disk diameters, respectively. The radiation dose values were recalculated according to the calibration standard recently introduced by the National Institute of Standards and Technology. The recalculation revealed a mean applied dose of 419 Gy at the sclera (SD, 207 Gy) and 138 Gy (SD, 67 Gy) at the tumor apex. The 5-year tumor control rate was 94.4%. Tumor recurrence was more frequent in eyes with vitreous tumor cell seeding or fish-flesh regression. The estimated 5-year eye preservation rate was 86.5%. Previous treatment by brachytherapy or external beam radiotherapy, as well as a large tumor diameter, were significant factors for enucleation. The radiotherapy-induced complications after 5 years of follow-up were retinopathy (22%), optic neuropathy (21%), and cataract (17%). These complications were significantly more frequent after prior brachytherapy or external beam radiotherapy. Conclusion: Brachytherapy using 106Ru plaques is a highly efficient therapy with excellent local tumor control and an acceptable incidence of side effects

  6. Toxicity of 144Ce inhaled in a relatively insoluble form by immature beagle dogs. VI

    Immature Beagle dogs (approximately equal to 3 months of age at exposure) have been exposed by inhalation to a relatively insoluble form of 144Ce (in fused aluminosilicate particles) to compare the resulting patterns of metabolism, dosimetry and biological effects with those seen in dogs exposed at 12 and 14 months of age and at 8 to 10.5 years of age. Five blocks of longevity animals, each consisting of 10 exposed dogs and one control, are currently on experiment. The initial lung burdens of the 144Ce-exposed dogs range from 0.004 to 140 μCi 144Ce/kg body weight. Three dogs with initial lung burdens of 73 to 120 μCi 144Ce/kg body weight died at 66 to 121 days after exposure with pulmonary injury and congestive heart failure. One dog with an initial lung burden of 140 μCi 144Ce/kg body weight died at 91 days after exposure with severe radiation pneumonitis and minimal pulmonary fibrosis and another dog whose initial lung burden was 70 μCi 144Ce/kg body weight died at 511 days after exposure with pulmonary injury that was mainly fibrotic in nature. Two dogs with initial lung burdens of 52 and 64 μCi 144Ce/kg body weight had primary pulmonary hemangiosarcomas and died at 618 and 689 days, respectively, with cumulative average absorbed beta doses to lung of 23,000 and 29,000 rads. One dog with an initial lung burden of 28 μCi 144Ce/kg body weight was euthanized at 1227 days after exposure with a hemangiosarcoma of the mediastinum, and another dog with an initial lung burden of 12 μCi 144Ce/kg body weight died at 1520 days after exposure from epilepsy. Serial observations are continuing on the surviving 40 exposed and five control dogs

  7. Transfer from soil to plants of 106Ru as nitrosyl and as chloride

    The transfer of 106Ru in a soil-plant ecosystem was investigated with respect to two chemical forms in compact soil samples under greenhouse conditions with surface and deep-layer contamination. Considerable differences in the uptake of 106Ru were observed between 106RuCl3 and 106Ru-nitrosyl during the first 5-8 wk after the contamination of the soil. The translocation of 106Ru in the soil showed an inhomogeneous distribution of the radioruthenium, with a great part of the total activity remaining in the upper soil layer between 0 and 5 cm even 10 mo after contamination of the soil surface. During the whole experiment, reemission of 106Ru into the air was investigated by using special air collectors under different temperature and light conditions. Although a continuous checking out for a time of about 8 mo, no measurable concentrations of 106Ru could be out for a time of about 8 mo, no measurable concentrations of 106Ru could be found in examined air filters

  8. Clinical quality assurance for 106Ru ophthalmic applicators

    Background and purpose: Episcleral brachytherapy using 106Ru/106Rh ophthalmic applicators is a proven method of therapy of uveal melanomas sparing the globe and in many cases sparing the vision. In the year 2001, an internal clinical quality assurance procedure revealed that part of the ophthalmic applicators leaked and that the calibration was erroneous. Consequently, the producer modernized its production procedures and, in May 2002, introduced a dose rate calibration that is traceable to the NIST standard. This NIST calibration confirmed that the previous calibration had been incorrect. In order to study the effects of the producer's new internal quality assurance procedures on the ophthalmic applicators, applicators of this new generation were submitted to a newly improved internal clinical acceptance test. Patients and methods: The internal clinical acceptance test consists of a leakage test and a dosimetric test of the ophthalmic applicators. The leakage test simulates contact of the ophthalmic applicators with chloride containing body fluid. The dosimetric tests measure depth dose curves and dose rate with a plastic scintillator dosimetric system and compare them with the indications in the producer's certificate. Furthermore, the depth dose profile of the most frequently used applicator (type CCB) was compared with published data. Results: The internal clinical leakage test showed that all of the tested ophthalmic applicators belonging to the new generation (n=17) were tight and not contaminated. The dosimetric acceptance tests applied to seven different types of applicators revealed that the relative depth dose profiles in the therapeutically relevant range (up to a depth of ≤7 mm) deviate from the producer's indications only by -2.7 to +3.2%. The acceptance test of the dose rate values of the ophthalmic applicators at a distance of 2 mm from the surface of the applicators resulted in a coefficient of variation of 1.7% (n=17). In the evaluation of the

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

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

  10. Toxicity of inhaled 144CeCl3 in beagle dogs. VIII

    Studies on the metabolism, dosimetry, and effects of inhaled 144CeCl3 in the Beagle dog are continuing to provide information that will aid in assessing the biological consequences of inhaling 144Ce such as might be released in certain nuclear accidents. Studies on the tissue distribution of inhaled 144CeCl3 have shown that the 144Ce deposited in lung is translocated at a moderately rapid rate to liver and skeleton and that significant radiation doses are accumulated by all three organs. Fifty-five dogs that inhaled 144CeCl3 and 15 control dogs were placed in a longevity study and are being observed for their lifespan. The 144Ce dogs had long-term retained burdens with values ranging from 20 to 2900 μCi. Thirty-one of the dogs exposed to 144CeCl3 have died; 8 at 21 to 44 days after inhalation with signs attributed to severe bone marrow damage and associated pancytopenia; 2 at 138 and 144 days with radiation pneumonitis; 3 at 309 to 874 days with hepatic necrosis; 1 at 510 days with marrow aplasia; 1 at 375 days with pulmonary fibrosis; and 16 at 799 to 3081 days, most with neoplasms or myeloproliferative disorders. In this last group, 1 dog had an osteosarcoma, 3 had squamous cell carcinomas of the maxilla, 2 of the latter also having primary pulmonary neoplasms, 5 had hemangiosarcomas of the liver, 1 had a hemangiosarcoma of the nasal cavity, 2 had myelogenous leukemia, 1 had myelofibrosis with myeloid metaplasia, 1 had spinal cord ependymomas, and 2 did not have neoplasms. One of these had severe myelomalacia and the other diffuse hepatic lipidosis with severe degeneration. Two controls died; 1 with a thyroid carcinoma and 1 with aspiration pneumonia. Serial observations are continuing on the 24 surviving 144CeCl3 dogs and 13 control dogs. (U.S.)

  11. Toxicity of inhaled 144CeCl3 in beagle dogs. XI

    Studies on the metabolism, dosimetry and effects of inhaled 144CeCl3 in Beagle dogs are being conducted to assess the biological consequences of inhaling 144Ce such as might be released in certain nuclear accidents. Studies on the organ distribution of inhaled 144CeCl3 have shown that the 144Ce deposited in the lung is translocated at a moderately rapid rate to liver and skeleton and that significant radiation doses are accumulated by all three organs. Fifty-five dogs that inhaled 144CeCl3 and 15 control dogs are being observed for their life span. The 144Ce dogs have long-term retained burdens with values ranging from 20 to 2900 μCi. Forty-five of the dogs exposed to 144CeCl3 have died; eight from 21 to 44 days after inhalation with severe bone marrow damage and associated pancytopenia; two at 138 and 144 days with radiation pneumonitis; three from 309 to 874 days with hepatic necrosis; one at 510 days with marrow aplasia; one at 375 days with pulmonary fibrosis; and 30 from 799 to 4085 days, most with neoplasms or myeloproliferative disorders. In this last group, one dog had an osteosarcoma, five had squamous cell carcinomas of the nasal cavity (two also having primary pulmonary neoplasms), six had hemangiosarcomas of the liver, one had a hemangiosarcoma of the nasal cavity, two had myelogenous leukemia, one had myelofibrosis with myeloid metaplasia, one had spinal cord ependymomas, one had a malignant melanoma (also an ependymoma) and two had mammary adenocarcinomas. Three dogs had primary pulmonary neoplasms including two with bronchogenic adenocarcinomas and one with an adenoma. Seven did not have malignant neoplasms. Two of these had severe myelomalacia, one had pulmonary edema, three had congestive heart failure and one had diffuse hepatic lipidosis with severe hepatic degeneration

  12. Inter-taxa differences in root uptake of 103/106Ru by plants

    Ruthenium-106 is of potential radioecological importance but soil-to-plant Transfer Factors for it are available only for few plant species. A Residual Maximum Likelihood (REML) procedure was used to construct a database of relative 103/106Ru concentrations in 114 species of flowering plants including 106 species from experiments and 12 species from the literature (with 4 species in both). An Analysis of Variance (ANOVA), coded using a recent phylogeny for flowering plants, was used to identify a significant phylogenetic effect on relative mean 103/106Ru concentrations in flowering plants. There were differences of 2465-fold in the concentration to which plant species took up 103/106Ru. Thirty-nine percent of the variance in inter-species differences could be ascribed to the taxonomic level of Order or above. Plants in the Orders Geraniales and Asterales had notably high uptake of 103/106Ru compared to other plant groups. Plants on the Commelinoid monocot clades, and especially the Poaceae, had notably low uptake of 103/106Ru. These data demonstrate that plant species are not independent units for 103/106Ru concentrations but are linked through phylogeny. It is concluded that models of soil-to-plant transfer of 103/106Ru should assume that; neither soil variables alone affect transfer nor plant species are independent units, and taking account of plant phylogeny might aid predictions of soil-to-plant transfer of 103/106Ru, especially for species for which Transfer Factors are not available

  13. Toxicity of 144Ce inhaled in a relatively insoluble form by immature Beagle dogs. XII

    Immature Beagle dogs (3 months old) were exposed once by inhalation to an aerosol of 144Ce incorporated in fused aluminosilicate particles. The influence of this age on the dose-response relationships is being compared to that of 13-mo-old and 8 to 10.5-yr-old dogs. This study involves 49 dogs that received graded initial lung burdens from 0.004 to 140 μCi 144Ce/kg body weight and five control dogs. To date, 19 of the 144Ce-exposed dogs and one of the controls have died. Dogs with the highest initial lung burdens of 144Ce died during the first 4 months with radiation pneumonitis, pulmonary fibrosis, and congestive heart failure. Pulmonary hemangiosarcoma was the primary finding in dogs that died at 1.5 to 2 years after exposure. Deaths beyond that time have been due primarily to extrapulmonary hemangiosarcomas. Observations are continued on the surviving 30 144Ce-exposed and four control dogs at 7.0 to 11.2 years after exposure

  14. Toxicity of 144Ce inhaled in a relatively insoluble form by aged Beagle dogs. XII

    The toxicity of relatively insoluble 144Ce inhaled by 8- to 10.5-year-old Beagle dogs is being investigated to determine possible age-related differences in long-term biological responses. Forty-two dogs were exposed to aerosols of 144Ce in fused aluminosilicate particles to yield initial lung burdens of 2.2 to 75 μCi 144Ce/kg body weight, and 12 control dogs were exposed to non-radioactive fused aluminosilicate particles. All 144Ce-exposed and control dogs have died or were euthanized between 197 and 2726 days after the inhalation exposure. Prominent findings in the 144Ce-exposed dogs were radiation pneumonitis in 19 of the 23 dogs that died during the first 943 days after exposure, and neoplastic disease in 13 of the 20 dogs that died beyond 904 days after exposure. Pulmonary tumors were found in five of these dogs. In contrast to the study with young adult dogs, in which pulmonary hemangiosarcomas were one of the prominent findings, all of these tumors were carcinomas

  15. Toxicity of inhaled 144Ce in fused aluminosilicate particles in aged beagle dogs. V

    The toxicity of 144Ce in fused aluminosilicate particles inhaled by 8- to 10.5-yr-old dogs is being investigated to provide information on age-related differences in the response of older members of the human population to accidental inhalation of radioactive aerosols. These data on aged dogs will be compared to the results of similar studies of dogs exposed at approximately 3 mo or 12 to 14 mo of age. Six blocks of five female dogs each have been divided into four exposure levels with mean initial lung burdens of 7.2, 14, 28 and 57 μCi 144Ce/kg body weight. Six blocks of four male dogs have been divided into three exposure levels with mean initial lung burdens of 7.2, 14 and 28 μCi 144Ce/kg body weight. Controls in each block were exposed to fused aluminosilicate particles containing stable cerium. Fifteen dogs with initial lung burdens ranging from 20 to 75 μCi 144Ce/kg body weight and cumulative doses to lung of from 22,000 to 74,000 rads have died or were euthanized 197 to 1207 days after exposure with clinicopathologic findings of radiation pneumonitis and pulmonary fibrosis.Pulmonary retention of the inhaled 144Ce was similar to that observed previously in dogs exposed at 18 to 22 mo of age in a radiation dose pattern study. Serial observations are continuing on the 19 surviving 144Ce-exposed and eight control dogs

  16. Toxicity of 144Ce fused clay particles inhaled by aged dogs. III

    The toxicity of 144Ce fused clay particles inhaled by 8- to 10.5-year-old dogs is being investigated to provide information on age-related differences in the response of older members of the human population to accidental inhalation of radioactive aerosols. These data on aged dogs will be compared to the results of similar studies using dogs exposed at approximately 3 months or 12 to 14 months of age. To date, 7 blocks of 5 dogs each, divided into 4 exposure levels with mean initial lung burdens of 7.5, 14, 24, and 57 μCi/kg body weight and control dogs exposed to non-labeled fused clay particles have been entered into a longevity study. Twelve dogs with initial lung burdens ranging from 20 to 75 μCi 144Ce/kg body weight and cumulative doses to lung of from 22,000 to 74,000 rads have died at 197 to 943 days post-inhalation with clinico-pathologic findings of radiation pneumonitis and pulmonary fibrosis. Two of these also had congestive heart failure. In addition, 4 dogs with ILBs of 8 to 14 μCi 144Ce/kg body weight have died of mammary neoplasms or congestive heart failure but without radiation pneumonitis. One dog with an ILB of 9 μCi 144Ce/kg body weight died with a chronic interstitial foreign body pneumonia. Two control dogs have died, one with a mammary carcinoma and one with pyometra. Pulmonary retention of the inhaled 144Ce was similar to that observed previously in dogs exposed at 18 to 22 months of age in a radiation dose pattern study. Serial observations are continuing on the 11 surviving 144Ce-exposed dogs and 5 controls. (U.S.)

  17. Toxicity of 144Ce inhaled in a relatively insoluble form by immature Beagle dogs. VIII

    The influence of age at exposure on the resulting patterns of deposition, retention, dosimetry and biological effects from a single inhalation exposure to a relatively insoluble form of a beta-emitting radionuclide with a relatively long physical half-life is being investigated. Immature Beagle dogs (3 months of age) have been exposed once, by inhalation, to an aerosol of 144Ce incorporated in fused aluminosilicate particles. Eighteen of these dogs were serially sacrificed to study the patterns of deposition, retention and dosimetry and the remaining 49 dogs received graded initial lung burdens that ranged from 0.004 to 140 μCi 144Ce/kg body weight and are being observed over their life span for study of the resulting long-term biological effects. Five control dogs are also included in this study. To date, 13 of the 144Ce-exposed dogs in the longevity study and none of the controls have died. Dogs with the highest initial lung burdens of 144Ce died first (during the first 4 months) with radiation pneumonitis, pulmonary fibrosis and congestive heart failure. Pulmonary hemangiosarcoma was the primary finding in dogs that died at 1.5 to 2 years after exposure. Deaths beyond that time have primarily involved extrapulmonary hemangiosarcomas. One dog, 627B, with an initial lung burden of 24 μCi 144Ce/kg body weight died during the past year at 2341 days after exposure with a widely disseminated hemangiosarcoma showing heavy involvement of the liver and skin. Observations are continuing on the surviving 36 144Ce-exposed and five control dogs

  18. Toxicity of 144Ce inhaled in a relatively insoluble form by aged beagle dogs. VI

    The toxicity of 144Ce inhaled in fused aluminosilicate particles by 8 to 10.5-year-old dogs is being investigated to provide information on age-related differences in the response of older members of the human population to accidental inhalation of radioactive aerosols. These data on aged dogs will be compared to the results of similar studies of dogs exposed at approximately 3 months or 12 to 14 months of age. Six blocks of five female dogs each have been divided into four exposure levels with mean initial lung burdens of 7.2, 14, 28 and 57 μCi 144Ce/kg body weight. Six blocks of four male dogs each have been divided into three exposure levels with mean initial lung burdens of 7.2, 14 and 28 μCi 144Ce/kg body weight. Controls in each block were exposed to fused aluminosilicate particles containing stable cerium. Eighteen dogs with initial lung burdens ranging from 14 to 75 μCi 144Ce/kg body weight and cumulative doses to lung of from 22,000 to 74,000 rads have died or were euthanized 197 to 1207 days after exposure with clinicopathologic findings of radiation pneumonitis and pulmonary fibrosis

  19. Effect of 144Ce inhaled in fused clay particles on the tracheobronchial lymph nodes

    Tracheobronchial lymph node changes and lymphopenia are sequelae to inhalation of relatively insoluble radioactive aerosols by Beagle dogs. To assess the development of these lesions, tracheobronchial lymph nodes from dogs that inhaled 144Ce in fused clay particles were examined at intervals from 2 to 730 days after exposure. Initial lung burdens in the dogs studied ranged from 33 to 63 μCi/kg body weight. The concentration of radioisotope in the tracheobronchial lymph nodes increased during the first year after exposure and exceeded that in the lung about 100 days after exposure. Autoradiographs of the lymph nodes showed that 144Ce particles were present in macrophages in the paracortical zone two days after exposure and that concentrations continued to increase in the paracortical zone and medullary cords. Histologic changes in the nodes included atrophy of the germinal centers and lymphocytic follicles, loss of lymphocytes and accumulation of macrophages in the paracortical zone, accumulation of pigment and isotope-laden macrophages in the medullary cords, occasional infiltrates of neutrophils in the medullary cords and, at later time periods, focal fibrosis of the medullary cords. Tracheobronchial lymph node weights of the dogs exposed to 144Ce in fused clay were not decreased until 512 days after exposure. These findings indicate that tracheobronchial lymph nodes accumulate relatively high burdens of 144Ce after inhalation of 144Ce in a relatively insoluble form and that the pathologic changes resulting from these burdens are basically atrophic in nature. Primary neoplasms in lymph nodes have not been observed in dogs with initial lung burdens from 0.0024 to over 30 μCi/kg body weight followed for up to 2000 days post-exposure. At the higher levels, however, a high incidence of primary pulmonary neoplasia has been observed. (U.S.)

  20. Study on the characteristics of indigenously developed 106Ru/106Rh source

    A pilot study was initiated to investigate the characteristics of 106Ru/106Rh source for the purpose of inducting it in Quality Assurance programme of personnel monitoring by Bhabha Atomic Research Centre. Towards this goal, a prototype 106Ru/106Rh source was fabricated indigenously. Different parameters such as activity, gamma ray spectrum, beam uniformity, percentage depth dose, output of the source, contribution of gamma and beta components of the source were studied. The detectors used in the study are CaSO4:Dy Teflon disc, pocket dosimeter, HPGe detector and radiochromic films. - Highlights: • Indigenous development of 106Ru/106Rh source for QA in personnel monitoring. • Source parameters such as activity of the source, gamma spectrum were studied. • Dosimetric parameters such as beam uniformity, BSF, gamma and beta contribution and PDD were studied. • TLDs, EBT radiochromic film, HPGe and electronic pocket dosimeter were used in the study

  1. Numerical calculation of relative dose rates from spherical 106Ru beta sources used in ophthalmic brachytherapy

    Eduardo de Paiva

    2015-01-01

    Full Text Available Concave beta sources of 106Ru/106Rh are used in radiotherapy to treat ophthalmic tumors. However, a problem that arises is the difficult determination of absorbed dose distributions around such sources mainly because of the small range of the electrons and the steep dose gradients. In this sense, numerical methods have been developed to calculate the dose distributions around the beta applicators. In this work a simple code in Fortran language is developed to estimate the dose rates along the central axis of 106Ru/106Rh curved plaques by numerical integration of the beta point source function and results are compared with other calculated data.

  2. Numerical calculation of relative dose rates from spherical 106Ru beta sources used in ophthalmic brachytherapy

    de Paiva, Eduardo

    Concave beta sources of 106Ru/106Rh are used in radiotherapy to treat ophthalmic tumors. However, a problem that arises is the difficult determination of absorbed dose distributions around such sources mainly because of the small range of the electrons and the steep dose gradients. In this sense, numerical methods have been developed to calculate the dose distributions around the beta applicators. In this work a simple code in Fortran language is developed to estimate the dose rates along the central axis of 106Ru/106Rh curved plaques by numerical integration of the beta point source function and results are compared with other calculated data.

  3. Toxicity of 144Ce inhaled in a relatively insoluble form by immature Beagle dogs. VII

    Immature Beagle dogs (approx. = 3 months of age at exposure) have been exposed by inhalation to a relatively insoluble form of 144Ce (in fused aluminosilicate particles) to compare the resulting patterns of metabolism, dosimetry and biological effects with those seen in dogs exposed at 12 and 14 months of age and at 8 to 10.5 years of age. Five blocks of longevity animals, each consisting of 10 exposed dogs and one control, are currently being studied. The initial lung burdens of the 144Ce-exposed dogs range from 0.004 to 140 μCi 144Ce/kg body weight. Three dogs with initial lung burdens of 73 to 120 μCi 144Ce/kg body weight died at 66 to 121 days after exposure with pulmonary injury and congestive heart failure. One dog with an initial lung burden of 140 μCi 144Ce/kg body weight died at 91 days after exposure with severe radiation pneumonitis and minimal pulmonary fibrosis and another dog whose initial lung burden was 70 μCi 144Ce/kg body weight died at 511 days after exposure with pulmonary injury that was mainly fibrotic in nature. Four dogs with initial lung burdens of 52 to 79 μCi/kg body weight had primary pulmonary hemangiosarcomas and died between 618 and 738 days, with cumulative average absorbed beta doses to lung of 23,000 to 31,000 rads. Two of these dogs, 1027S and 1024D, died within the past year. One dog with an initial lung burden of 28 μCi/kg body weight was euthanized at 1227 days after exposure with an hemangiosarcoma of the mediastinum. Within the past year, Dog 627S, with an initial lung burden of 48 μCi/kg body weight, died 1732 days after exposure with hemangiosarcoma primary in the liver or spleen. A dog with an initial lung burden of 12 μCi/kg body weight died from epilepsy at 1520 days after exposure. Serial observations are continuing on the surviving 37 exposed and five control dogs

  4. Toxicity of inhaled 144Ce fused clay particles in beagle dogs. VII

    The metabolism, dosimetry, and effects of inhaled 144Ce in fused clay particles are being investigated in the Beagle dog to aid in assessing the biological consequences of release of 144Ce in a relatively insoluble form such as might occur in certain types of nuclear accidents. The toxicity of inhaled 144Ce fused clay is also of general interest since it is representative of intermediate-lived beta-emitting radionuclides. Two major studies with young adult dogs (12 to 14 months of age at exposure) are involved: (1) a metabolism and dosimetry study in which 24 dogs were serially sacrificed over an extended period of time, and (2) a longevity study with 2 series of dogs; Series I with 15 dogs exposed to aerosols of 144Ce in fused clay particles to yield initial lung burdens of 11 to 210 μCi/kg body weight and 3 control dogs exposed to nonradioactive fused clay particles and Series II with 96 dogs exposed to aerosols of 144Ce in fused clay particles to yield initial lung burdens of 0.0024 to 66 μCi/kg body weight and 12 control dogs exposed to nonradioactive fused clay particles. Twenty-eight dogs died or were euthanized at 143 to 2396 days after inhalation of 144Ce. The prominent findings were radiation pneumonitis in 17 dogs that died or were euthanized at early time periods and neoplastic disease in 10 of the 11 dogs that died or were euthanized at 750 days or later; 5 with hemangiosarcoma of the lung, 1 with both a hemangiosarcoma and a fibrosarcoma of the lung, 1 with both a bronchiolo-alveolar carcinoma and a hemangiosarcoma of lung, 1 with a hemangiosarcoma of lung, bronchiolo-alveolar carcinoma, and a bronchiogenic adenocarcinoma, and 1 each with a hemangiosarcoma of the mediastinum and of the spleen. The cumulative radiation dose to the lung at time of death has ranged from 22,000 to 140,000 rads. Serial observations are continuing on the 83 survivors and 15 controls. (U.S.)

  5. Shortcomings of the industrial quality assurance of 106Ru ophthalmic plaques

    Background: Beta emitting 106Ru applicators manufactured by Bebig GmbH (Berlin, Germany) are widely used to treat intraocular tumors. The applicators are fixed to the bulbus and removed after several days. The following therapy relevant defects have been detected by an internal clinical acceptance test: risk of leakage and inconsistent dose-rate specifications by the manufacturer. In the meantime, components of the internal clinical acceptance test have been adopted successfully by the manufacturer of the 106Ru ophthalmic plaques. Material and Method: 106Ru ophthalmic plaques were tested with the following internal clinical acceptance tests: visual inspection, surface contamination, leakage, and dose-rate verification. The surface contamination test consists of a wet wipe test at moderate pressure. For the leakage test of the 106Ru ophthalmic plaques a clinically relevant scenario was developed in which the contact of the applicator with human tissue is simulated. In the course of it the applicator is inserted into Ringer's solution for several days. The certified energy dose-rate statements of the manufacturer are examined with a 1 mm3 plastic scintillator for consistency. (orig.)

  6. Internal clinical acceptance test of the dose rate of 106Ru/106Rh ophthalmic applicators

    For the last forty years or so, episcleral brachytherapy using 106Ru/106Rh ophthalmic applicators has been a proven method of therapy for uveal melanomas, sparing the globe and in many cases conserving the vision. In episcleral brachytherapy, a radioactive 106Ru/106Rh ophthalmic applicator (BEBIG Co., Berlin, Germany) is temporarily fixed on the surface of the bulbus oculi, whereby the intraocular tumour gets irradiated protractedly through the sclera. 106Ru/106Rh ophthalmic applicators are primarily beta sources, i.e. they generate a local dose escalation both in the vessels supplying the tumour and in the tumour itself, while simultaneously sparing the risk structures. In its certificates, BEBIG, the manufacturer of the product, indicates a dose rate for the 106Ru/106Rh ophthalmic applicators at a dose specification reference point which ensures traceability to the NIST standard (12/2001). The dose specification reference point is situated at a distance of 2 mm from the middle of the inner (concave) surface of the applicators, and the dose rate was measured with a scintillation detector (diameter 1 mm, height 0.5 mm). The manufacturer indicates for this dose rate at the dose specification reference point a relative measurement uncertainty of ±20% within the 95% confidence interval. Since the introduction of the NIST calibration, the quality of the calibration passed on by BEBIG to the user has been examined for n=45 ophthalmic applicators

  7. Extraction of carrier-free 144Ce with acetylacetone and 8-hydroxyquinoline

    The extraction of carrier-free 144Ce with 3.25 to 0.65 M solutions of acetylacetone in carbon tetrachloride and with 1.0 to 0.01 M solutions of 8-hydroxyquinoline in chloroform at a constant as well as variable pH was investigated. On the basis of the analysis of distribution curves it may be presumed that in both extraction systems the oxidation of cerium(III) to cerium(IV) microamounts takes place. The distribution curves of extraction and reextraction in the systems with 8-hydroxyquinoline show a considerable complexity. In the extraction system with acetylacetone constants were found which satisfactorily express the distribution of 144Ce in this system. (author)

  8. Biological effects of repeated exposure of beagle dogs to relatively insoluble aerosols of 144Ce. IV

    This experiment is being conducted to study the behavior and long-term biological effects in Beagle dogs of 144Ce inhaled in fused aluminosilicate particles in repeated inhalation exposures for comparison with similar data from dogs that were exposed only once to a similar aerosol. Four groups of nine dogs each were exposed once every eight weeks for two years (13 exposures) to achieve specified exposure goals. The 144Ce-exposed dogs received increasing or relatively constant beta radiation dose rates in contrast to the steadily decreasing dose rate seen after a single inhalation exposure. Exposures in the first and second groups were planned to yield a cumulative absorbed dose to lung of approximately equal to 35,000 rads and those in the third group approximately equal to 17,000 rads within two years after the first exposure. Singly exposed dogs that had died with pulmonary tumors when this experiment was initiated had cumulative doses to death of 29,000 to 61,000 rads. All 13 exposures have been completed. One dog in the 4.5-μCi 144Ce/kg body weight group died at 771 days after first exposure with emaciation, adrenal cortical degeneration and bone marrow aplasia. One control dog died accidentally during anesthesia. During the past year, two additional dogs have died. One dog in the repeated 2.5-μCi 144Ce/kg body weight group died at 1256 days after the first exposure with radiation pneumonitis and pulmonary fibrosis and a control dog died at 1052 days with autoimmune hemolytic anemia. The remaining 32 dogs appear to be in good physical condition except for a persistent lymphopenia at approximately equal to 4 years after the first exposure. They are being maintained for life span observations

  9. The uptake of 90Sr, 137Cs and 144Ce by leaves of spring wheat and rape

    The distribution and accumulation of 90Sr, 137Cs, 144Ce through the leaf surface into the plant have been studied. The results show that the uptake rate of 137Cs by crop plant is about 53%, while the uptake rate for 90Sr and 144Ce is about 0.4%. However 90Sr is absorbed in significant amount from soil whereas 137Cs is absorbed in negligible amount

  10. Internal Clinical Acceptance Test of the Dose Rate of 106Ru/106Rh Ophthalmic Applicators

    Episcleral brachytherapy using 106Ru/106Rh ophthalmic applicators is a proven method of therapy for uveal melanomas, sparing the globe and in many cases, conserving vision. In its certificates, Bebig, the manufacturer of the product, indicates a dose rate for the 106Ru/106Rh ophthalmic applicators which ensures traceability to the NIST standard (12/2001). Since the introduction of the NIST calibration, the quality of the calibration provided by Bebig to the clinical user has been examined for 45 ophthalmic applicators with a plastic scintillator measurement system. Of these, 20 ophthalmic applicators had a dose rate at the dose specification reference point that exceeded the dose rate stated in the manufacturer's certificate by up to 23%. (author)

  11. Influence of chelation therapy (DTPA) on 141Ce retention in rats

    We investigated the influence of oral and parenteral administration of chelation therapy on the retention of 141Ce in young rats. Opposite to results obtained in adult rats present results show high efficacy of oral chelation therapy in reducing radiocerium retention in the whole body and organs of suckling rats. (author) 3 refs

  12. Liver tumors in Beagle dogs exposed by inhalation to 144CeCl3

    Primary malignant hepatic neoplasms developed in 9 of 55 Beagle dogs (16 percent) exposed to 144CeCl3 in CsCl aerosol (seven primary hepatic hemangiosarcomas, one hepatocellular carcinoma and one intrahepatic bile duct carcinoma). Cerium-144 was rapidly translocated from the lung to the liver and skeleton; the liver received the highest cumulative beta dose. The latent periods of hepatic hemangiosarcomas appeared to be dose-related; death from hepatic hemangiosarcoma occurred earlier in dogs which received higher beta doses

  13. Development of a phantom and assessment of (141)Ce as a surrogate radionuclide for flood field uniformity testing of gamma cameras.

    Saxena, Sanjay Kumar; Kumar, Yogendra; Malpani, Basant; Rakshit, Sutapa; Dash, Ashutosh

    2016-06-01

    This paper describes an indigenous method for development and deployment of rechargeable liquid filled phantom with newly proposed radionuclide (141)Ce for determination of extrinsic uniformity of gamma cameras. Details about design of phantom, neutron irradiation of cerium targets, chemical processing of (141)Ce, charging of phantom with (141)Ce solution and their performance evaluation are presented. Suitability of (141)Ce in quality assurance of gamma cameras used in in-vivo diagnostic imaging procedures has been amply demonstrated. PMID:27031297

  14. Biological effects of repeated inhalation exposure of Beagle dogs to relatively insoluble aerosols of 144Ce. V

    The behavior and long-term biological effects in Beagle dogs of 144Ce inhaled in fused aluminosilicate particles in repeated inhalation exposures are being studied for comparison with data from dogs that were exposed only once to a similar aerosol. Four groups of nine dogs each were exposed once every 8 weeks for 2 years (13 exposures) to achieve specified exposure goals. These goals were: to increase the lung burden by 2.5 μCi 144Ce/kg body weight with each exposure in the first group; to reestablish lung burdens of 9 or 4.5 μCi 144Ce/kg body weight in the second and third groups, respectively; and to expose controls (fourth group) to fused aluminosilicate particles containing stable cerium. With these exposure sequences, the 144Ce-exposed dogs received increasing or relatively constant beta radiation dose rates in contrast to the steadily decreasing dose rate seen after a single inhalation exposure. Exposures in the first and second groups were planned to yield a cumulative absorbed dose to lung of approx. = 35,000 rads and those in the third group approx. = 17,000 rads within two years after the first exposure. All 13 exposures have been completed. During the past year, one dog in the 9.0 μCi 144Ce/kg body weight group died at 1558 days after the first exposure with autoimmune hemolytic anemia. The remaining 24 144Ce-exposed and seven control dogs generally appear to be in good physical condition with exception of a persistent lymphopenia at approx. = 5 years after the first exposure. They are continuing to be maintained for life span observations

  15. K-shell ionization in the beta decay of 141Ce

    The total K-shell ionization probability accompanying the β- decay of 141Ce to the 0.145-MeV level in 141Pr was determined to be (1.79 +- 0.11) x 10-4 from Pr Kα x rays in coincidence with the 0.145-MeV gamma ray. This result is in very good agreement with the theoretical calculations of Law and Suzuki

  16. Effects of inhaled 144Ce on cardiopulmonary function and histopathology of the dog

    Twelve dogs inhaled single doses of relatively insoluble particles containing 144Ce and six dogs inhaled particles containing stable cerium as controls. Pulmonary function, clinical, and radiographic evaluations were performed serially. The dogs developed progressive radiation pneumonitis and pulmonary fibrosis similar to that previously reported for whole-lung irradiation from internal or external sources. Focal histologic changes in bronchioles and alveoli were detected functionally during treadmill and tube-breathing stresses at a time when the dogs' clinical and radiographic appearances were normal. Moderate functional impairment was associated with more severe inflammatory and proliferative changes in airways and alveoli. Severe impairment resulted from progressive fibrosis and scarring. These were several strong correlations between functional indices and histological scores. There was a nonlinear relationship between cumulative radiation dose and effects, and once the functional alterations became clinically evident, the disease progressed with little further increase in dose

  17. On the actual state of industrial quality assurance procedures with regard to 106Ru ophthalmic plaques

    In the year 2002, Bebig updated, among other things, the ASMW (GDR) calibration of the dose rate of the 106Ru ophthalmic plaques from the years 1987-1989 by a calibration of the NIST (USA). The current NIST calibration, together with the new equipment for the measurement of the depth dose curves, led to the consequence that the new NIST 2001 dose rate values show, in the mean, a deviation of 0.75 times (plaque type CCC) up to 2.06 times (plaque types CCX, CCY, and CCZ) compared to the dose rate values that had been indicated so far in Bebig's certificate, based on the ASMW 1987 calibration. For the 95% confidence interval, Bebig estimated the measurement uncertainty to be ± 25%. If one takes into consideration the minimal and maximal values in such 95% confidence intervals, it follows that the new NIST 2001 dose rate values deviate between 0.56 times (plaque type CCC) and 2.58 times (plaque types CCX, CCY, and CCZ) from the Bebig certificate (ASMW calibration 1987). As regards leakage, no objections arose in the case of the 106Ru ophthalmic plaques produced according to the new quality standards. (orig.)

  18. Biological effects of repeated inhalation exposure of beagle dogs to aerosols of 144Ce in fused clay particles I

    This experiment was initiated to study the biological behavior and long-term effects of repeated inhalation exposures to 144Ce in fused clay particles compared with those seen in Beagle dogs that received a single exposure as young adults. The 36 dogs, divided into four equal groups, are exposed every 8 weeks to achieve the following: to maintain lung burdens of 9 and 4.5 μCi 144Ce/kg body weight in the first and second groups, respectively; to increase the lung burden by 2.5 μCi 144Ce/kg body weight in the third group with each exposure and to expose controls (fourth group) to fused clay containing stable cerium. With these exposure sequences, the 144Ce-exposed dogs will receive increasing or maintained β dose rates in contrast to the steadily decreasing dose rate seen after a single inhalation exposure. Exposures to the first and third groups will produce a cumulative absorbed dose to lung of approximately equal to 35,000 rads and those to the second group will yield approximately equal to 17,000 rads within 2 yr after the first exposure. Single exposure dogs that had died with pulmonary neoplasia when this experiment was initiated had cumulative doses to death of 29,000 to 61,000 rads. Six of the planned 13 exposures have been completed to date. All exposed dogs are surviving and will be maintained for lifespan observation. (U.S.)

  19. Assessment, modelization and analysis of 106 Ru experimental transfers through a freshwater trophic system

    Experiments are carried out in order to study 106 RU transfers through a freshwater ecosystem including 2 abiotic compartments (water and sediment) and 3 trophic levels (10 species). Experimental results are expressed mathematically so as they can be included into a global model which is then tested in two different situations. The comparison of the available data concerning the in situ measured concentrations to the corresponding calculated ones validates the whole procedure. Analysis of the so validated results lightens ruthenium distribution process in the environment. The rare detection of this radionuclide in organisms living in areas contaminated by known meaningful releases can be explained by a relativity high detection limit and by a slight role of the sediment as a secondary contamination source. (author). 78 figs., 18 tabs

  20. Responses of different dosemeters in beta dosimetry of 106Ru/106Rh ophthalmic applicators

    This work presents the TL response of three kinds of dosimeters from different manufacturing characteristics under irradiation of 106 Ru / 106 Rh sealed sources used in ophthalmic brachytherapy. They are: Ca SO4:Dy + teflon (D- Ca SO4:Dy -0,4), LiF:Mg, Ti (TLD-100) and Ca SO4:Dy (TLD-900). Some of reports accepted by scientific community (NCS report 14 e ICRU report 72) as reference in the quality control of beta applicators dosimetry recommend that the absorbed dose standard uncertainties can be kept below 20%. The TLD Ca SO4:Dy + teflon presented proper sensibility and high precision comparing with the others. Considering the similar dimensions of ophthalmic tumors and aside critical structures it is relevant to reduce undesirable effects due to the irradiation of these structures. Therefore, the quality control in the beta dosimetry using this kind of source is a constant challenge. (author)

  1. Accurate estimation of dose distributions inside an eye irradiated with 106Ru plaques

    Background: Irradiation of intraocular tumors requires dedicated techniques, such as brachytherapy with 106Ru plaques. The currently available treatment planning system relies on the assumption that the eye is a homogeneous water sphere and on simplified radiation transport physics. However, accurate dose distributions and their assessment demand better models for both the eye and the physics. Methods: The Monte Carlo code PENELOPE, conveniently adapted to simulate the beta decay of 106Ru over 106Rh into 106Pd, was used to simulate radiation transport based on a computerized tomography scan of a patient's eye. A detailed geometrical description of two plaques (models CCA and CCB) from the manufacturer BEBIG was embedded in the computerized tomography scan. Results: The simulations were firstly validated by comparison with experimental results in a water phantom. Dose maps were computed for three plaque locations on the eyeball. From these maps, isodose curves and cumulative dose-volume histograms in the eye and for the structures at risk were assessed. For example, it was observed that a 4-mm anterior displacement with respect to a posterior placement of a CCA plaque for treating a posterior tumor would reduce from 40 to 0% the volume of the optic disc receiving more than 80 Gy. Such a small difference in anatomical position leads to a change in the dose that is crucial for side effects, especially with respect to visual acuity. The radiation oncologist has to bring these large changes in absorbed dose in the structures at risk to the attention of the surgeon, especially when the plaque has to be positioned close to relevant tissues. Conclusion: The detailed geometry of an eye plaque in computerized and segmented tomography of a realistic patient phantom was simulated accurately. Dose-volume histograms for relevant anatomical structures of the eye and the orbit were obtained with unprecedented accuracy. This represents an important step toward an optimized

  2. Monte Carlo calculation of dose to water of a 106Ru COB-type ophthalmic plaque

    The concave eye applicators with 106Ru/106Rh or 90Sr/90Y beta-ray sources are worldwide used in brachytherapy for treating intraocular tumors. It raises the need to know the exact dose delivered by beta radiation to tumors but measurement of the dose to water (or tissue) is very difficult due to short range of electrons. The Monte Carlo technique provides a powerful tool for calculation of the dose and dose distributions which helps to predict and determine the doses from different shapes of various types of eye applicators more accurately. The Monte Carlo code MCNPX has been used to calculate dose distributions from a COB-type 106Ru/106Rh ophthalmic applicator manufactured by Eckert and Ziegler BEBIG GmbH. This type of a concave eye applicator has a cut-out whose purpose is to protect the eye nerve which makes the dose distribution more complicated. Several calculations have been performed including depth dose along the applicator central axis and various dose distributions. The depth dose along the applicator central axis and the dose distribution on a spherical surface 1 mm above the plaque inner surface have been compared with measurement data provided by the manufacturer. For distances from 0.5 to 4 mm above the surface, the agreement was within 2.5% and from 5 mm the difference increased from 6% up to 25% at 10 mm whereas the uncertainty on manufacturer data is 20% (2s). It is assumed that the difference is caused by nonuniformly distributed radioactivity over the applicator radioactive layer

  3. Effect of fasting on the transit time of 144Ce in the mouse gut

    Our work with G.I. absorption of actinide elements indicates greater absorption by fasted animals than by animals on regular diets (Weiss and Walburg, undated). Residence time of a metallic compound in the gut may be an important factor influencing G.I. absorption. Cerium-144 (III) chloride was administered by gavage to fasted mice and to mice on regular feed. The G.I. tract was excised, cut into sections, and the activity of each section determined as a function of time after dosing. Our results indicate rapid transit of 144CeCl3 along the empty mouse gut. One hour after dosing, about half the Ce is in the cecal contents; about 40% remains in stomach contents. Twelve hours after dosing, only about 2% remains in the cecum; by 16 hours, almost the entire dose has been cleared from the intestine. Transit times in mice with stomach and intestines containing food were 12 hours longer than in fasted mice. These results lead to the conclusion that factors other than G.I. residence time determine G.I. absorption of actinides in mice

  4. Effect on canine lymphocyte function of 144Ce inhaled in fused clay particles

    Beagle dogs exposed by inhalation to 144Ce in fused clay particles develop a persistent lymphopenia and the remaining peripheral lymphocytes in these dogs show a depressed in vitro response to plant mitogens. These studies were designed to evaluate the cellular basis for this defect. The survival and growth of lymphocytes from irradiated and control dogs were evaluated through 96 hours of culture. Many irradiated lymphocytes that were viable in vivo died within 24 hours in vitro. The remaining lymphocytes appeared to grow normally indicating that the early in vitro death was responsible for at least a portion of the difference between irradiated and control lymphocyte cultures. A second experiment was designed to determine if any humoral factors in plasma of irradiated dogs were responsible for the poor response of the lymphocytes. Lymphocytes from irradiated and control dogs were grown with plasma from both types of animals. Heterologous plasma had no apparent effect on lymphocyte growth, indicating that humoral factors were not involved. (U.S.)

  5. Process optimization for effective column separation of 106Ru from aqueous waste associated with spent reprocessing solvent in storage tanks

    The present work deals with another waste stream resulting from reprocessing operations, viz. the aqueous solution present in substantial quantities as the bottom layer in tanks storing spent TBP-dodecane solvent. The effective separation of 106Ru from aqueous waste streams generated during reprocessing of spent nuclear fuel is difficult because of its complex aqueous chemistry

  6. Biological effects of repeated inhalation exposure of Beagle dogs to relatively insoluble aerosols of 144Ce. VI

    Beagle dogs were exposed repeatedly to a relatively insoluble form of 144Ce (in fused aluminosilicate particles) to study the deposition, retention and long-term biological effects for comparison with data from dogs that were exposed only once to a similar aerosol. Four groups of nine dogs each were exposed once every 8 weeks for 2 years (13 exposures) to achieve specified exposure goals. These goals were: to increase the lung burden by 2.5 μCi 144Ce/kg body weight with each exposure; to reestablish lung burdens of 9 or 4.5 μCi 144Ce/kg body weight and to expose controls to fused aluminosilicate particles containing nonradioactive cerium. With these exposure sequences, the 144Ce-exposed dogs received increasing or relatively constant beta radiation dose rates in contrast to the steadily decreasing dose rate seen after a single inhalation exposure. Following completion of the exposure series, the dogs are being observed for the development of long-term biological effects. To date, 11 dogs have died or were euthanized, nine exposed dogs and two controls. Although pulmonary hemangiosarcomas were a prominent finding in dogs exposed once to the same aerosol at a level that led to cumulative doses to lung similar to these repeatedly exposed dogs, only one has been observed in the repeatedly exposed dogs. Other effects of note to date include three pulmonary carcinomas, two hemangiosarcomas of the tracheobronchial lymph nodes and one splenic hemangiosarcoma. Observations are continuing on the surviving 18 exposed and seven control dogs

  7. Kinetic study of the deposition of 144Ce, 143Pr and 147Nd on a platinum anode

    Investigation of the electrodeposition of radioactive rare earth metal isotopes confirm that, depending on the conditions of electrolysis, they can be deposited on the platinum either cathodically or anodically. The anodic deposition of these isotopes can take place with electrochemical oxidation or electrosorption without electron-transfer, depending on the lanthanide(III-IV) oxidation potentials. The present paper reports the results of the investigation connected with the anodic deposition of 144Ce, 143Pr and 147Nd. (author)

  8. 129I, 60Co, and 106Ru measurements on water samples from the Hanford project environs

    Groundwater flow and contamination patterns beneath the Hanford project reservation have been studied since the early days of the project. The measurement of radioactive materials at concentrations much below those required for radiation protection are useful for tracing groundwater movement and detection of potential contamination problems before they are apt to occur. Groundwater samples from a number of wells on or near the Hanford reservation have been analyzed for 129I by neutron activation analysis and for gamma radioactivity by low-level coincidence gamma-ray spectrometry. The major radionuclides in addition to natural radioactivity detected in the underground waters by gamma-ray spectrometry were 106Ru and 60Co. Local river and rain water samples were also analyzed for 129I and long-lived radionuclides. Special sample collection methods were developed to prevent contamination of the water samples during collection. Anions travel farther than cations in underground water systems since soils are primarily cation exchangers and retain the cations. Anion exchange techniques were used in the field and the laboratory to recover the desired radionuclides. Sample sizes ranged up to several thousand liters. This paper discusses the sample collection methods,analysis methods, and results obtained. The methods used were found to provide high sensitivity for groundwater studies. (auth)

  9. Use of 141Ce as a particulate digesta flow tracer in ruminants. II. Behavior of the tracer at the duodenum and in the feces

    A ration of 600 g chopped hay and 150 g ground sorghum is given twice daily to sheep fitted with a rumen cannula and a duodenal reentrant cannula. 141Ce flow rate at the duodenum and in the feces is compared to flow rate of stained hay particles after ingestion of a single labelled meal. After an adaptation period during which both daily meals are labelled, variations in 141Ce concentration are then measured in the duodenal and fecal dry matter. The tracer is used to estimate dry mater digestibility indirectly. Duodenal data show that the mean retention time of 141Ce in the rumen is about 15% less than that of stained particles. The meal after the radioactive one momentarily depresses 141Ce excretion rate while it accelerates that of the stained particles. Mean retention time in the whole gastro-intestinal tract of a meal of 600 g chopped hay 150 g ground sorghum is 40.4+-3.8 h or 32.4+-3.7 h, depending on whether stained particles or 141Ce is used. All the 141Ce ingested is recovered in the feces. Mean recovery of 141Ce in the feces excreted during 200 hours after dosage is 100.2+-5.0%. After a period of adaptation where all meals are radioactive, feces of 2 sheep are sampled either by total collection or directly in the rectum. Dry matter digestibility does not differ whether calculated from total collection or by the indirect method using 141Ce

  10. Decontamination of 60Co and 144Ce. low-activity liquid wastes with the Fe3+ /OH- /Ca2+ /PO-4-3- system

    The influence of reaction time, concentrations of Fe3+ and PO-4-3+, temperature and agitation velocity in the efficiency of decontamination of 60Co and 144Ce low-activity liquid wastes using the Fe3+ /OH-/Ca2+ /PO-4-3+ precipitator system was stud ied in this paper. The mathematical models of this process were obtained for 60Co and 144Ce. The best conditions for the decontamination we re calculated using the optimization program

  11. Studies on the chemical behaviour of 106Ru in sea water and its uptake by marine organisms

    In the previous paper, the author represented that the concentration factor of 106Ru was relatively high for marine algae in comparison with the other organisms such as fish and mollusca. The concentration seemed to be attributable to the effect of adsorption on the surface of the marine algae. And it is well known that the surface substance is quite different according to the species of marine algae. Then uptake behaviour of the ionic species obtained from 106RuNO.Cl sub(x) were investigated in relation to the species of marine algae and the surface substances extracted from them. The cationic complex species represented the highest concentration factors for the two species except red algae. The order of the concentration factors among these was as follows: brown algae (Hizikia fusiforme) > green algae (Ulva pertusa) > red algae (Porphyra tenera). (auth.)

  12. Assessment of ocular beta radiation dose distribution due to 106Ru/106Rh brachytherapy applicators using MCNPX Monte Carlo code

    Nilseia Aparecida Barbosa

    2014-08-01

    Full Text Available Purpose: Melanoma at the choroid region is the most common primary cancer that affects the eye in adult patients. Concave ophthalmic applicators with 106Ru/106Rh beta sources are the more used for treatment of these eye lesions, mainly lesions with small and medium dimensions. The available treatment planning system for 106Ru applicators is based on dose distributions on a homogeneous water sphere eye model, resulting in a lack of data in the literature of dose distributions in the eye radiosensitive structures, information that may be crucial to improve the treatment planning process, aiming the maintenance of visual acuity. Methods: The Monte Carlo code MCNPX was used to calculate the dose distribution in a complete mathematical model of the human eye containing a choroid melanoma; considering the eye actual dimensions and its various component structures, due to an ophthalmic brachytherapy treatment, using 106Ru/106Rh beta-ray sources. Two possibilities were analyzed; a simple water eye and a heterogeneous eye considering all its structures. Two concave applicators, CCA and CCB manufactured by BEBIG and a complete mathematical model of the human eye were modeled using the MCNPX code. Results and Conclusion: For both eye models, namely water model and heterogeneous model, mean dose values simulated for the same eye regions are, in general, very similar, excepting for regions very distant from the applicator, where mean dose values are very low, uncertainties are higher and relative differences may reach 20.4%. For the tumor base and the eye structures closest to the applicator, such as sclera, choroid and retina, the maximum difference observed was 4%, presenting the heterogeneous model higher mean dose values. For the other eye regions, the higher doses were obtained when the homogeneous water eye model is taken into consideration. Mean dose distributions determined for the homogeneous water eye model are similar to those obtained for the

  13. Biological alterations resulting from chronic lung irradiation. I. The pulmonary lipid composition, physiology, and pathology after inhalation by beagle dogs of 144Ce-labeled fused clay aerosols

    Three groups of four beagle dogs inhaled a 144Ce-labeled fused clay aerosol; two additional dogs per group, exposed to a stable cerium-labeled fused clay aerosol, were used as controls. At monthly intervals, one diaphragmatic lobe of each of two dogs exposed to 144Ce and one control animal from each group was lavaged with isotonic saline. The recovered lavage solutions were centrifuged to isolate lung cells (mostly macrophages) and surfactant for lipid analyses. The groups were sacrificed at 2, 4, and 6 mo after exposure, when the lungs of the dogs exposed to 144Ce had average cumulative radiation doses of 23, 36, and 59 krad, respectively. Chronic irradiation of the lung resulted in a progressive radiation pneumonitis which was assessed clinically and pathologically at various intervals. At sacrifice, the lungs were analyzed for 144Ce and the right apical and diaphragmatic lobes were minced and lyophilized and the lipids were extracted. Total lipids from all lung samples were determined gravimetrically and individual compounds were identified, isolated, and quantitated. The quantities of lipid in lung tissue, in pulmonary cells, and in surfactant increased as a function of time and radiation dose. Neutral lipids (sterol esters and triglycerides) accounted for most of the increase. (U.S.)

  14. Assessment, modelization and analysis of {sup 106} Ru experimental transfers through a freshwater trophic system; Evaluation, modelisation et analyse des transferts experimentaux du {sup 106}Ru au sein d`un reseau trophique d`eau douce

    Vray, F.

    1994-11-24

    Experiments are carried out in order to study {sup 106} RU transfers through a freshwater ecosystem including 2 abiotic compartments (water and sediment) and 3 trophic levels (10 species). Experimental results are expressed mathematically so as they can be included into a global model which is then tested in two different situations. The comparison of the available data concerning the in situ measured concentrations to the corresponding calculated ones validates the whole procedure. Analysis of the so validated results lightens ruthenium distribution process in the environment. The rare detection of this radionuclide in organisms living in areas contaminated by known meaningful releases can be explained by a relativity high detection limit and by a slight role of the sediment as a secondary contamination source. (author). 78 figs., 18 tabs.

  15. Responses of different dosemeters in beta dosimetry of {sup 106}Ru/{sup 106}Rh ophthalmic applicators;Respostas de diferentes dosimetros termoluminescentes na dosimetria beta de aplicadores oftalmicos de {sup 106}Ru/{sup 106}Rh

    Ferreira, D.F.P.; Daros, K.A.C.; Segreto, R.A.; Medeiros, R.B. [Universidade Federal de Sao Paulo (UNIFESP), Sao Paulo, SP (Brazil)

    2009-07-01

    This work presents the TL response of three kinds of dosimeters from different manufacturing characteristics under irradiation of 106 Ru / 106 Rh sealed sources used in ophthalmic brachytherapy. They are: Ca SO{sub 4}:Dy + teflon (D- Ca SO{sub 4}:Dy -0,4), LiF:Mg, Ti (TLD-100) and Ca SO{sub 4}:Dy (TLD-900). Some of reports accepted by scientific community (NCS report 14 e ICRU report 72) as reference in the quality control of beta applicators dosimetry recommend that the absorbed dose standard uncertainties can be kept below 20%. The TLD Ca SO{sub 4}:Dy + teflon presented proper sensibility and high precision comparing with the others. Considering the similar dimensions of ophthalmic tumors and aside critical structures it is relevant to reduce undesirable effects due to the irradiation of these structures. Therefore, the quality control in the beta dosimetry using this kind of source is a constant challenge. (author)

  16. Process for the removal of 106Ru traces from NH4NO3 effluent generated during recycling of sintered depleted uranium fuel pellets

    Several chemical treatment formulations were tested for the effective removal of very low levels of 106Ru activity from NH4NO3 effluent generated during wet processing of rejected sintered depleted uranium (DU) fuel pellets. Based on the results, a simple process involving precipitation of cobalt sulphide along with ferric hydroxide was selected and further optimization of process variables was carried out. The optimized process has been found to be highly efficient in reducing 106Ru activity down to extremely low levels. (author)

  17. Separation and purification of 106Ru from effluent streams of ion exchange cycle used for Pu purification in PUREX process

    Present paper describes the separation and purification of extracted fraction of Ru using separation techniques namely solvent extraction and extraction chromatography. The feed solution used is ion exchange effluent solution collected from Plant that contained 106Ru activity of ∼ 100 mCi/L level along with 95Nb (∼ 0.29 mCi/L) and Pu (∼ 1.5mg/L) at 7.1 M HNO3. In the initial step, the feed solution is contacted ice with 30% TBP in n-dodecane at organic to aqueous phase ratio of 2:1. The raffinate from this step shows that the free acidity of the solution is reduced from 7.1 to 4.2 M without loosing the Ru activity in the feed

  18. Energy deposition by a 106Ru/106Rh eye applicator simulated using LEPTS, a low-energy particle track simulation

    The present study introduces LEPTS, an event-by-event Monte Carlo programme, for simulating an ophthalmic 106Ru/106Rh applicator relevant in brachytherapy of ocular tumours. The distinctive characteristics of this code are the underlying radiation-matter interaction models that distinguish elastic and several kinds of inelastic collisions, as well as the use of mostly experimental input data. Special emphasis is placed on the treatment of low-energy electrons for generally being responsible for the deposition of a large portion of the total energy imparted to matter. - Highlights: → We present the Monte Carlo code LEPTS, a low-energy particle track simulation. → Carefully selected input data from 10 keV to 1 eV. → Application to an electron emitting Ru-106/Rh-106 plaque used in brachytherapy.

  19. Suppression of the pulmonary clearance of Staphylococcus aureus in mice that had inhaled either 144CeO2 or 239PuO2

    The rate of pulmonary clearance of inhaled Staphylococcus aureus in mice was determined at intervals after inhalation exposure to either 144CeO2 or 239PuO2. In mice with mean initial lung burdens between 0.6 and 4.7 μCi 144Ce the pulmonary clearance of S. aureus was suppressed up to 12 weeks after inhalation of 144CeO2. In mice with mean initial lung burdens between 1.3 and 29.0 μCi 239Pu the pulmonary clearance of S. aureus was suppressed up to 26 weeks after inhalation of 239PuO2. The suppressed pulmonary clearance of S. aureus appeared to correlate with the radiation dose rate to the lungs at the time of exposure to bacteria but not with the cumulative radiation dose to the lungs. The changes in bacterial clearance did not appear to be correlated with changes in body weight, hematological parameters, or radiation-induced histopathological changes. Altered bacterial clearance may be related to radiation damage to pulmonary macrophages. It was concluded that irradiation of the lung from radionuclides inhaled in relatively insoluble forms may result in increased bacterial invasion of the lungs

  20. Multidimensional dosimetry of {sup 106}Ru eye plaques using EBT3 films and its impact on treatment planning

    Heilemann, G., E-mail: gerd.heilemann@meduniwien.ac.at; Kostiukhina, N. [Department of Radiation Oncology/Comprehensive Cancer Center, Medical University of Vienna/AKH Vienna, Vienna 1090 (Austria); Nesvacil, N.; Georg, D. [Department of Radiation Oncology/Comprehensive Cancer Center, Medical University of Vienna/AKH Vienna, Vienna 1090, Austria and Christian Doppler Laboratory for Medical Radiation Research for Radiation Oncology, Vienna 1090 (Austria); Blaickner, M. [Health and Environment Department Biomedical Systems, Austrian Institute of Technology GmbH, Vienna 1220 (Austria)

    2015-10-15

    Purpose: The purpose of this study was to establish a method to perform multidimensional radiochromic film measurements of {sup 106}Ru plaques and to benchmark the resulting dose distributions against Monte Carlo simulations (MC), microdiamond, and diode measurements. Methods: Absolute dose rates and relative dose distributions in multiple planes were determined for three different plaque models (CCB, CCA, and COB), and three different plaques per model, using EBT3 films in an in-house developed polystyrene phantom and the MCNP6 MC code. Dose difference maps were generated to analyze interplaque variations for a specific type, and for comparing measurements against MC simulations. Furthermore, dose distributions were validated against values specified by the manufacturer (BEBIG) and microdiamond and diode measurements in a water scanning phantom. Radial profiles were assessed and used to estimate dosimetric margins for a given combination of representative tumor geometry and plaque size. Results: Absolute dose rates at a reference depth of 2 mm on the central axis of the plaque show an agreement better than 5% (10%) when comparing film measurements (MCNP6) to the manufacturer’s data. The reproducibility of depth-dose profile measurements was <7% (2 SD) for all investigated detectors and plaque types. Dose difference maps revealed minor interplaque deviations for a specific plaque type due to inhomogeneities of the active layer. The evaluation of dosimetric margins showed that for a majority of the investigated cases, the tumor was not completely covered by the 100% isodose prescribed to the tumor apex if the difference between geometrical plaque size and tumor base ≤4 mm. Conclusions: EBT3 film dosimetry in an in-house developed phantom was successfully used to characterize the dosimetric properties of different {sup 106}Ru plaque models. The film measurements were validated against MC calculations and other experimental methods and showed a good agreement with

  1. Use of 141Ce as a particulate digesta flow tracer in ruminants. I. Determination of uptake on feed and behavior in rumen digesta in vivo

    The suitability of 141Ce as a particulate digesta flow tracer is studied in sheep. The amount and the factors of cerium uptake on feed particles by incubating alfalfa hay and sorghum seeds in water containing 141Ce in solution are determined. After soaking one hour, 80% radioactivity is retained on the hay 17% on the sorghum. Incubation time is the main factor determining uptake rate. This uptake is solid on the hay and more fragile on the sorghum. The evolution of 141Ce distribution among the different physical constituents of rumen digesta is studied on two sheep given a single radioactive meal (10μCi). These sheep are fitted with a rumen cannula and fed twice daily with hay (80%) and sorghum (20%). There is little 141Ce in solution in the supernatant liquid after centrifugation of digesta. At the end of the 'labelled' meal, specific radioactivity (RAS) of liquid-phase digesta, separated by filtering on two layers of gauze, is equal to or higher than the RAS of the solid phase. It increases up to the next unlabelled meal and then decreases. Microorganisms may cause this transfer of liquid-phase radioactivity to the large particles. Specific radioactivity of the microorganisms remains very high after the 'labelled' meal as compared to that of different granulometric fractions of solid digesta

  2. Determination of 106Ru, 134/137Cs, and 241Am concentrations and Action Level in the Foodstuffs Consumed by Inhabitants of Iraq

    *H. N. Majeed

    2013-03-01

    Full Text Available The specific activity concentrations of (106Ru, 134/137Cs, and 241Am nuclides in 40 imported foodstuffs which collected randomly in January 2012 from all Iraqi cities markets were studied. The rang of specific activity concentrations of 106Ru varies from (37.930±6.16 Bq kg-1 (S No. :17: Turkey Kidney bean to 99.735±9.99 Bq kg-1 (S No.:32: Egypt Broad bean, with average value 71.667±8.47 Bq kg-1. For 134Cs varies from 0.200±0.45 Bq kg-1 (S No. :19 : Ukraine Chick-pea to 2.365±1.54 Bq kg-1 (S No. :33 : Peru Broad bean with average value (0.988±0.99 Bq kg-1.The activity concentrations of 137Cs varies from 0.164±0.40 Bq kg-1 (S No.:19 : Ukraine Chick-pea to 5.291±2.30 Bq kg-1 ( S No.: 39: Uzbekistan Mung bean with average value 1.460±1.21, then for 241Am the activity concentrations varies from 0.029±0.17 Bq kg-1 (S No.:23 : Iran Chick-pea to 1.248±1.12 Bq kg-1 (S No.:40: Canada Green peas with average value 0.399±0.63. All the values were less than the World average concentrations [15,17]. The high contributor for 106Ru, 134/137Cs, and 241Am radionuclides were in Broad bean and other foodstuffs (which contained Brown grit, White grit, Mung bean and Green peas as a 12%, Broad bean as 14%, corn as a 19% and other foodstuffs with 15% respectively The lowest contributor of 106Ru, 134/137Cs, and 241Am radionuclides in the studied foodstuffs were 6% in cowpea, 7% in semolina, 5% in lentil and 4% in lentil respectively. The action level of the 106Ru, 134/137Cs, and 241Am radionuclide’s for three age groups have been calculated and the foodstuffs were within the range permitted and free of any radiation and thus there was no seriousness in dealing with.

  3. Evolution of gamma artificial radioactivity in coastal sediments of the English Channel during the years 1976, 1977 and 1978

    During 1976-1977, a state of equilibrium was found to prevail for 106Ru and 144Ce, especially in the North-West Cotentin and the Norman-Breton gulf, where reconcentration of both radionuclides was observed with preferential enrichment of the latter over the former. Levels of 125Sb and 137Cs were found to be low but were difficult to interpret, because of the particular physico-chemical behavior of 125Sb and the long half-life of 137Cs. The results obtained for 103Ru, 141Ce, 95Zr may be explained entirely by the contribution of atmospheric fallout. 144Ce and 106Ru levels in the Norman-Breton gulf may be for the most part ascribed to La Hague disposals, radionuclide dispersal from the emissary being characterized by an eastward transfer of the soluble fraction and a westward transfer of the particulate fraction, with transit times which may last up to 2 years. The boundary between the areas submitted respectively to the twofold impact of fallout and industrial waste, and to fallout alone would appear to lie between the mouth of the Trieux river and Morlaix Bay. From a graphic representation of the relationship between radionuclides, empiric distribution laws for 106Ru and 137Cs were established from 144Ce level parameters characteristic of the areas considered (years 1976-1977)

  4. Nondestructive analysis of RA reactor fuel burnup, Program for burnup calculation base on relative yield of 106Ru, 134Cs and 137Cs in the irradiated fuel

    Burnup of low enriched metal uranium fuel of the RA reactor is described by two chain reactions. Energy balance and material changes in the fuel are described by systems of differential equations. Numerical integration of these equations is base on the the reactor operation data. Neutron flux and percent of Uranium-235 or more frequently yield of epithermal neutrons in the neutron flux, is determined by iteration from the measured contents of 106Ru, 134Cs and 137Cs in the irradiated fuel. The computer program was written in FORTRAN-IV. Burnup is calculated by using the measured activities of fission products. Burnup results are absolute values

  5. Quantitative analysis of fission products by γ spectrography

    The activity of the fission products present in treated solutions of irradiated fuels is given as a function of the time of cooling and of the irradiation time. The variation of the ratio (144Ce + 144Pr activity)/ 137Cs activity) as a function of these same parameters is also given. From these results a method is deduced giving the 'age' of the solution analyzed. By γ-scintillation spectrography it was possible to estimate the following elements individually: 141Ce, 144Ce + 144Pr, 103Ru, 106Ru + 106Rh, 137Cs, 95Zr + 95Nb. Yield curves are given for the case of a single emitter. Of the various existing methods, that of the least squares was used for the quantitative analysis of the afore-mentioned fission products. The accuracy attained varies from 3 to 10%. (author)

  6. Energy deposition by a {sup 106}Ru/{sup 106}Rh eye applicator simulated using LEPTS, a low-energy particle track simulation

    Fuss, M.C. [Instituto de Fisica Fundamental, Consejo Superior de Investigaciones Cientificas (CSIC), Serrano 113-bis, 28006 Madrid (Spain); Munoz, A.; Oller, J.C. [Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas (CIEMAT), Avenida Complutense 22, 28040 Madrid (Spain); Blanco, F. [Departamento de Fisica Atomica, Molecular y Nuclear, Universidad Complutense de Madrid, Avenida Complutense, 28040 Madrid (Spain); Williart, A. [Departamento de Fisica de los Materiales, Universidad Nacional de Educacion a Distancia, Senda del Rey 9, 28040 Madrid (Spain); Limao-Vieira, P. [Laboratorio de Colisoes Atomicas e Moleculares, Departamento de Fisica, CEFITEC, FCT-Universidade Nova de Lisboa, Quinta da Torre, 2829-516 Caparica (Portugal); Borge, M.J.G.; Tengblad, O. [Instituto de Estructura de la Materia, Consejo Superior de Investigaciones Cientificas (CSIC), Serrano 113-bis, 28006 Madrid (Spain); Huerga, C.; Tellez, M. [Hospital Universitario La Paz, Paseo de la Castellana 261, 28046 Madrid (Spain); Garcia, G., E-mail: g.garcia@iff.csic.es [Instituto de Fisica Fundamental, Consejo Superior de Investigaciones Cientificas (CSIC), Serrano 113-bis, 28006 Madrid (Spain); Departamento de Fisica de los Materiales, Universidad Nacional de Educacion a Distancia, Senda del Rey 9, 28040 Madrid (Spain)

    2011-09-15

    The present study introduces LEPTS, an event-by-event Monte Carlo programme, for simulating an ophthalmic {sup 106}Ru/{sup 106}Rh applicator relevant in brachytherapy of ocular tumours. The distinctive characteristics of this code are the underlying radiation-matter interaction models that distinguish elastic and several kinds of inelastic collisions, as well as the use of mostly experimental input data. Special emphasis is placed on the treatment of low-energy electrons for generally being responsible for the deposition of a large portion of the total energy imparted to matter. - Highlights: > We present the Monte Carlo code LEPTS, a low-energy particle track simulation. > Carefully selected input data from 10 keV to 1 eV. > Application to an electron emitting Ru-106/Rh-106 plaque used in brachytherapy.

  7. CeLAND: search for a 4th light neutrino state with a 3 PBq 144Ce-144Pr electron antineutrino generator in KamLAND

    Gando, A; Hayashida, S; Ikeda, H; Inoue, K; Ishidoshiro, K; Ishikawa, H; Koga, M; Matsuda, R; Matsuda, S; Mitsui, T; Motoki, D; Nakamura, K; Oki, Y; Otani, M; Shimizu, I; Shirai, J; Suekane, F; Suzuki, A; Takemoto, Y; Tamae, K; Ueshima, K; Watanabe, H; Xu, B D; Yamada, S; Yamauchi, Y; Yoshida, H; Cribier, M; Durero, M; Fischer, V; Gaffiot, J; Jonqueres, N; Kouchner, A; Lasserre, T; Leterme, D; Letourneau, A; Lhuillier, D; Mention, G; Rampal, G; Scola, L; Veyssiere, Ch; Vivier, M; Yala, P; Berger, B E; Kozlov, A; Banks, T; Dwyer, D; Fujikawa, B K; Han, K; Kolomensky, Yu G; Mei, Y; O'Donnell, T; Decowski, P; Markoff, D M; Yoshida, S; Kornoukhov, V N; Gelis, T V M; Tikhomirov, G V; Learned, J G; Maricic, J; Matsuno, S; Milincic, R; Karwowski, H J; Efremenko, Y; Detwiler, A; Enomoto, S

    2013-01-01

    The reactor neutrino and gallium anomalies can be tested with a 3-4 PBq (75-100 kCi scale) 144Ce-144Pr antineutrino beta-source deployed at the center or next to a large low-background liquid scintillator detector. The antineutrino generator will be produced by the Russian reprocessing plant PA Mayak as early as 2014, transported to Japan, and deployed in the Kamioka Liquid Scintillator Anti-Neutrino Detector (KamLAND) as early as 2015. KamLAND's 13 m diameter target volume provides a suitable environment to measure the energy and position dependence of the detected neutrino flux. A characteristic oscillation pattern would be visible for a baseline of about 10 m or less, providing a very clean signal of neutrino disappearance into a yet-unknown, sterile neutrino state. This will provide a comprehensive test of the electron dissaperance neutrino anomalies and could lead to the discovery of a 4th neutrino state for Delta_m^2 > 0.1 eV^2 and sin^2(2theta) > 0.05.

  8. A Brief Review of Past INL Work Assessing Radionuclide Content in TMI-2 Melted Fuel Debris: The Use of 144Ce as a Surrogate for Pu Accountancy

    D. L. Chichester; S. J. Thompson

    2013-09-01

    This report serves as a literature review of prior work performed at Idaho National Laboratory, and its predecessor organizations Idaho National Engineering Laboratory (INEL) and Idaho National Engineering and Environmental Laboratory (INEEL), studying radionuclide partitioning within the melted fuel debris of the reactor of the Three Mile Island 2 (TMI-2) nuclear power plant. The purpose of this review is to document prior published work that provides supporting evidence of the utility of using 144Ce as a surrogate for plutonium within melted fuel debris. When the TMI-2 accident occurred no quantitative nondestructive analysis (NDA) techniques existed that could assay plutonium in the unconventional wastes from the reactor. However, unpublished work performed at INL by D. W. Akers in the late 1980s through the 1990s demonstrated that passive gamma-ray spectrometry of 144Ce could potentially be used to develop a semi-quantitative correlation for estimating plutonium content in these materials. The fate and transport of radioisotopes in fuel from different regions of the core, including uranium, fission products, and actinides, appear to be well characterized based on the maximum temperature reached by fuel in different parts of the core and the melting point, boiling point, and volatility of those radioisotopes. Also, the chemical interactions between fuel, fuel cladding, control elements, and core structural components appears to have played a large role in determining when and how fuel relocation occurred in the core; perhaps the most important of these reaction appears to be related to the formation of mixed-material alloys, eutectics, in the fuel cladding. Because of its high melting point, low volatility, and similar chemical behavior to plutonium, the element cerium appears to have behaved similarly to plutonium during the evolution of the TMI-2 accident. Anecdotal evidence extrapolated from open-source literature strengthens this logical feasibility for

  9. The study of the effect of gamma radiation on the ionic and collodial solutions of 144Ce/III/ at trace concentration by the method of self-diffusion and centrifugation

    Gamma irradiation of a solution of trace concentration of 144Ce/III/ at pH 3.0 causes an increase in the self-diffusion coefficient of 144Ce/III/ and small decrease in its centrifugable fraction. The significant increase in the self-diffusion coefficient is observed after irradiation at pH 9.0 and 11.0 and on the centrifugation of these solutions an increased susceptibility of particles containing 144Ce/III/ to the coagulation accurs. The measurements were performed by a method of the open end capillary immersed into the excess of inactive solution and the self-diffusion coefficient calculated as described earlier. The solutions were irradiated either directly in the capillaries for the self-diffusion measurment fixed in the glass tubes or in borosilicate Sial glass sample tubes with subsequent pipetting into the capillaries. The dose rate of 60Co γ-radiation was about 0.4 Mrad. hour-1, the time of irradiation was 1.5 to 15 hours. The period between the end of the irradiation and the beginning of the self-diffusion measurement amounted to about 15 to 30 min. (F.G.)

  10. Does escalation of the apical dose change treatment outcome in β-radiation of posterior choroidal melanomas with 106Ru plaques?

    Purpose: To show the results of treating posterior uveal melanomas with 106Ru plaque β-ray radiotherapy and to review and discuss the literature concerning the optimal apical dose prescription (100 vs. 160 Gy). Methods and Materials: Forty-eight patients with uveal melanomas (median height 3.85 mm + 1 mm sclera) were treated with ruthenium plaques. The median apical dose was 120 Gy, the median scleral dose 546 Gy. Results: After 5.8 years of follow-up, the overall 5-year survival rate was 90%, the disease specific 5-year survival rate was 92% (3 patients alive with metastasis). Six percent received a second ruthenium application, 10% of the eyes had to be enucleated. Local control was achieved in 90% of the patients with conservative therapy alone. Central or paracentral tumors showed 50% of the pretherapeutic vision after 4 years, and 80% of the vision was preserved in those with peripheral tumors. The main side effects were mostly an uncomplicated retinopathy (30%); macular degeneration or scarring led to poor central vision in 30% of cases. Conclusion: Brachytherapy with ruthenium applicators is an effective therapy for small- and medium-size posterior uveal melanomas. Our results are comparable to other series. The treatment outcome does not seem to be capable of improvement by increasing the apical dose. An internationally accepted model for defining the dosage in brachytherapy is needed

  11. Studies on treatment of low level radioactive liquid waste for removal of anionic species of 125Sb, 99Tc and 106Ru. Contributed Paper RD-14

    The treatment of intermediate level waste at Waste Immobilization Plant generates low level radioactive waste which would require further management before discharge to sea. This waste is expected to contain polymeric oxo anions of 125Sb, 99Tc, 106Ru in addition to cationic species like 137Cs, 90Sr etc. Chemical treatment takes care of the major contributors to radioactivity viz 137Cs, 90Sr etc but traces of activity due to anionic species remain in the treated waste effluent. Novel composite anionic exchanger namely Polyurethane foam coated with Hydrous Zirconium Oxide was developed for removal of these anionic species. This material was successfully employed for removal of anionic 125Sb from radioactive waste effluent at Waste Management Division, Trombay. Based on our experience with Sb removal using the above material it was decided to assess the ability of the exchanger in removal of other anionic species bearing Ru and Tc. It was observed that in addition to complete removal of Sb, 50% Ru removal and 40% Tc could also be removed using this material from radioactive waste effluents. In lab experiments, similar results were obtained with simulated low level waste bearing inactive Ru. Among several hydrous oxides tried in a batch study, Hydrous Zirconium Oxide showed a maximum removal of 40% for Tc in actual waste generated from reprocessing plant. Based on the above it has been planned to set up an anion exchange column with Hydrous Zirconium Oxide coated Polyurethane foam for final treatment of chemically treated waste effluent prior to discharge as a prime step towards achieving our goal of minimum discharge to Sea. (author)

  12. Radiochemical methods used by the IAEA's laboratories at Siebersdorf for the determination of 90Sr, 144Ce and Pu radionuclides in environmental samples collected for the International Chernobyl Project

    During the IAEA's International Chernobyl Project to assess the radiological consequences of the nuclear reactor accident, the Agency's Laboratories at Seibersdorf participated in the collection and analyses of environmental samples from the Soviet Union. Under Task 2 of this effort, the determination of the activity concentrations of 90Sr and the alpha-emitting Pu radionuclides was important for the corroboration of the official USSR environmental contamination maps. The present paper describes in detail the sampling methods and radiochemical procedures used for the 90Sr, 144Ce, 238Pu and 239,240Pu analyses in these samples with emphasis on the grass and soil treatments. (Author)

  13. Determination of absorbed dose distribution in water for COC ophthalmic applicator of {sup 106}Ru/{sup 106}Rh using Monte Carlo code-MCNPX; Determinacao da distribuicao de dose absorvida na agua para o aplicador oftalmico COC de {sup 106}Ru/{sup 106}Rh utilizando o codigo de Monte Carlo - MCNPX

    Barbosa, Nilseia A.; Rosa, Luiz A. Ribeiro da, E-mail: nilseia@ird.gov.br, E-mail: lrosa@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ),Rio de Janeiro, RJ (Brazil); Braz, Delson, E-mail: delson@nuclear.ufrj.br [Coordenacao dos programas de Pos-Graduacao em Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

    2014-07-01

    The COC ophthalmic applicators using beta radiation source of {sup 106}Ru/{sup 106}Rh are used in the treatment of intraocular tumors near the optic nerve. In this type of treatment is very important to know the dose distribution in order to provide the best possible delivery of prescribed dose to the tumor, preserves the optic nerve region extremely critical, that if damaged, can compromise the patient's visual acuity, and cause brain sequelae. These dose distributions are complex and doctors, who will have the responsibility on the therapy, only have the source calibration certificate provided by the manufacturer Eckert and Ziegler BEBIG GmbH. These certificates provide 10 absorbed dose values at water depth along the central axis applicator with the uncertainties of the order of 20% isodose and in a plane located 1 mm from the applicator surface. Thus, it is important to know with more detail and precision the dose distributions in water generated by such applicators. To this end, the Monte Carlo simulation was used using MCNPX code. Initially, was validated the simulation by comparing the obtained results to the central axis of the applicator with those provided by the certificate. The different percentages were lower than 5%, validating the used method. Lateral dose profile was calculated for 6 different depths in intervals of 1 mm and the dose rates in mGy.min{sup -1} for the same depths.

  14. Assessment of selected fission products in the Savannah River Site environment

    Most of the radioactivity produced by the operation of a nuclear reactor results from the fission process, during which the nucleus of a fissionable atom (such as 235U) splits into two or more nuclei, which typically are radioactive. The Radionuclide Assessment Program (RAP) has reported on fission products cesium, strontium, iodine, and technetium. Many other radionuclides are produced by the fission process. Releases of several additional fission products that result in dose to the offsite population are discussed in this publication. They are 95Zr, 95Nb, 103Ru, 106Ru, 141Ce, and 144Ce. This document will discuss the production, release, migration, and dose to humans for each of these selected fission products

  15. Appendix to Health and Safety Laboratory environmental quarterly, March 1, 1976--June 1, 1976. [Tabulated data on content of lead in surface air and /sup 7/Be, /sup 95/Zr, /sup 137/Cs, /sup 144/Ce, and /sup 90/Sr in surface air, milk, drinking water, and foods sampled in USA

    Hardy, E.P. Jr.

    1976-07-01

    Tabulated data are presented on: the monthly deposition of /sup 89/Sr and /sup 90/Sr at some 100 world land sites; the content of lead and /sup 7/Be, /sup 95/Zr, /sup 137/Cs, and /sup 144/Ce in samples of surface air from various world sites; and the content of /sup 90/Sr in samples of milk, drinking water, and animal and human diets collected at various locations throughout the USA. (CH)

  16. Reconstruction of the composition of the Chernobyl radionuclide fallout and external radiation absorbed doses to the population in areas of Russia

    The results of reconstruction of the radionuclide composition of the Chernobyl fallout in the territories of Russia is presented. Reconstruction has been carried out by means of statistical analysis of the gamma spectrometry data on 2867 soil samples collected in the territories of Ukraine, Byelarus and Russia from 1986 to 1988. To verify the data, aggregated estimates of the fuel composition of the 4th block at the moment of the accident (available from the literature) have been used, as well as the estimates of activity released to the atmosphere. As a result, correlation and regression dependences have been obtained between the activities of the radionuclides most contributing to the dose (137Cs, 134Cs, 131I, 140Ba, 140La, 95Zr, 95Nb, 103Ru, 106Ru, 141Ce, 144Ce, 125Sb). Statistically significant regression relations between different pairs of radionuclides (including analysis of the 'noise' contribution to the data) depending on the distance between the point of sample collection and the power station are presented for the 'north-east track' - the northern part of the 30 km zone and southern part of the Gomel 'district (Byelarus) and the Briansk, Kaluga, Tula and Orel districts (Russia). A methodology is also described for reconstructing space-time characteristics of the contamination of the territories by major dose-forming radionuclides released from the Chernobyl NPP 4th unit. (Author)

  17. Radioactivity in surface air and precipitation in Japan after the Chernobyl accident

    Radioactive plumes from the Chernobyl reactor accident first passed over Japan on 3 May 1986. Measurements of 103Ru, 131I and 137Cs in rainfall and airborne dust collected at Chiba near Tokyo show that, in fact, at least two or more kinds of plume arrived during May. Their altitudes were calculated to be about 1500 m in early May and 6300 m in late May. Radionuclides detected in 33 precipitation samples collected by the network of radiation monitoring stations from 1 to 22 May were 7Be, 89Sr, 90Sr, 95Zr, 95Nb, 103Ru, 106Ru, sup(110m)Ag, 125Sb, sup(129m)Te, 131I, 132Te, 132I, 134Cs, 136Cs, 137Cs, 140Ba, 140La, 141Ce and 144Ce. The radiation was characterized by higher levels of the volatile nuclides, such as 103Ru, 132Te, 131I and 137Cs, than fallout levels in nuclear weapons testing, and by activity ratios of 0.48 and 14 for, respectively, 134Cs/137Cs and 89Sr/90Sr, as on 26 April. the fallout activity was higher in Northwestern Japan, the average depositions of 90Sr and 137Cs in Japan from 1 May (or 30 April) to 22 May being 1.4 Bq m-2 and 95 Bq m-2, inventories which are 14 and 550 times higher than the pre-Chernobyl values. (author)

  18. Monte Carlo modeling of beta-radiometer device used to measure milk contaminated as a result of the Chernobyl accident

    This paper presents results of Monte Carlo modeling of the beta-radiometer device with Geiger-Mueller detector used in Belarus and Russia to measure the radioactive contamination of milk after the Chernobyl accident. This type of detector, which is not energy selective, measured the total beta-activity of the radionuclide mix. A mathematical model of the beta-radiometer device, namely DP-100, was developed, and the calibration factors for the different radionuclides that might contribute to the milk contamination were calculated. The estimated calibration factors for 131I, 137Cs, 134Cs, 90Sr, 144Ce, and 106Ru reasonably agree with calibration factors determined experimentally. The calculated calibration factors for 132Te, 132I, 133I, 136Cs, 89Sr, 103Ru, 140Ba, 140La, and 141Ce had not been previously determined experimentally. The obtained results allow to derive the activity of specific radionuclides, in particular 131I, from the results of the total beta-activity measurements in milk. Results of this study are important for the purposes of retrospective dosimetry that uses measurements of radioactivity in environmental samples performed with beta-radiometer devices.

  19. Biological effects of radiation: The induction of malignant transformation and programmed cell death

    In the Chernobyl explosions and fire, powderized nuclear fuel was released from the reactor core, causing an unexpected fallout. X-ray analysis and scanning electron microscopy showed that the isolated single particles were essentially pure uranium. These uranium aerosols contained all of the nonvolatile fission products, including the b-emitters, 95Zr, 103Ru, 106Ru, 141Ce, and 144Ce. The hot particles are extremely effective in inducing malignant transformation in mouse fibroblast cells in vitro. The major factor responsible for this effect is focus promotion caused by a wound-mediated permanent increase in cell proliferation (mitogenesis associated with mutagenesis). Transformed foci were analysed for the activation of c-abl, c-erb-A, c-erb-B, c-fms, c-fos, c-myb, c-myc, c-Ha-ras, c-Ki-ras, c-sis, and c-raf oncogenes at the transcriptional level. The pattern of oncogene activation was found to vary from focus to focus. Long interspersed repeated DNA (L1 or LINE makes up a class of mobile genetic elements which can amplify in the cell genome by retroposition. This element is spontaneously transcriptionally activated at a critical population density and later amplified in rat chloroleukaemia cells. UV light and ionizing radiation induce this activation prematurely, and the activation is followed by programmed cell death (apoptosis) in a sequence of events identical to that seen in LIRn activation occurring spontaneously

  20. Standard test method for gamma energy emission from fission products in uranium hexafluoride and uranyl nitrate solution

    American Society for Testing and Materials. Philadelphia

    2005-01-01

    1.1 This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C 787 and C 996 and uranyl nitrate specification C 788. 1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background. 1.3 The nuclides to be measured are106Ru/ 106Rh, 103Ru,137Cs, 144Ce, 144Pr, 141Ce, 95Zr, 95Nb, and 125Sb. Other gamma energy-emitting fission nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives. 1.4 This standard does not purport to address all of the safety concerns, if any, associated with its us...

  1. Particle size distribution of radioactive aerosols after the Fukushima and the Chernobyl accidents

    Following the Fukushima accident, a series of aerosol samples were taken between 24th March and 13th April 2011 by cascade impactors in the Czech Republic to obtain the size distribution of 131I, 134Cs, 137Cs, and 7Be aerosols. All distributions could be considered monomodal. The arithmetic means of the activity median aerodynamic diameters (AMADs) for artificial radionuclides and for 7Be were 0.43 and 0.41 μm with GDSs 3.6 and 3.0, respectively. The time course of the AMADs of 134Cs, 137Cs and 7Be in the sampled period showed a slight decrease at a significance level of 0.05, whereas the AMAD pertaining to 131I increased at a significance level of 0.1. Results obtained after the Fukushima accident were compared with results obtained after the Chernobyl accident. The radionuclides released during the Chernobyl accident for which we determined the AMAD fell into two categories: refractory radionuclides (140Ba, 140La 141Ce, 144Ce, 95Zr and 95Nb) and volatile radionuclides (134Cs, 137Cs, 103Ru, 106Ru, 131I, and 132Te). The AMAD of the refractory radionuclides was approximately 3 times higher than the AMAD of the volatile radionuclides; nevertheless, the size distributions for volatile radionuclides having a mean AMAD value of 0.51 μm were very close to the distributions after the Fukushima accident. -- Highlights: • AMADs after the Fukushima and Chernobyl accidents in the Czech Rep. were determined. • The mean value of AMADs of the monitored nuclides from the NPP Fukushima was 0.43 μm. • Nuclides from the NPP Chernobyl fell into two categories – refractory and volatile. • The mean value of AMADs of volatile nuclides from the NPP Chernobyl was 0.51 μm. • AMADs of volatile nucl. from the NPP Chernobyl were 3× smaller than of the refractory radionuclides

  2. Environmental and health consequences in Japan due to the accident at Chernobyl nuclear reactor plant

    A comprehensive review was made on the results of national monitoring program for environmental radioactivity in Japan resulting from the accident at the Chernobyl nuclear power plant in USSR. Period of monitoring efforts covered by the present review is from 30th of April 1986 to 31st of May 1987. A radioactive cloud released from the Chernobyl nuclear reactor initially arrived in Japan on 30th of April 1986 as indicated by the elevated level of 131I, 137Cs and 134Cs activity in the total deposition on 30th of April and also by the increased 137Cs body burden noted on 1st of May. Almost all the radioactive nuclides detected in the European countries were also identified in Japan. For example, the observed nuclides were: 95Zr, 95Nb, 99mTc, 103Ru, 106Ru, 110mAg, 111Ag, 125Sb, 127Sb, 129mTe, 131I, 132Te, 132I, 133I, 134Cs, 136Cs, 137Cs, 140Ba, 140La, 141Ce and 144Ce. Among the above radionuclides, the country average concentration was determined for 131I, 137Cs and 134Cs in various environmental materials such as air, fresh water, soil, milk, leafy and root vegetables, cereals, marine products and other foodstuffs. In contrast to the sharp decline of 131I which was negligible after a few months, 137Cs showed a tendency to maintain its activity in foodstuffs at an appreciable level one year later. Collective effective dose equivalent and dose equivalent to thyroid in Japanese population due to 137Cs, 134Cs and 131I were estimated to be around 590 man Sv and 4760 man Sv, respectively. Corresponding values for the per caput dose equivalent are 5 μSv for whole body and 40 μSv for thyroid, respectively. (author)

  3. Radionuclide accumulation by aquatic biota exposed to contaminated water in artificial ecosystems before and after its passage through the ground

    This study was designed to investigate the comparative accumulation of radionuclides from contaminated water in artificial ecosystems before and after the water's passage through the ground. Fish, clams, algae, and an emergent vascular plant were experimentally exposed to mixtures of radionuclides in three aqueous streams. Two streams consisted of industrial water discharged directly into a leaching trench, and the same water after it had migrated through the ground for a distance of 260 meters. The third stream was river water, which served as a background or control. Biota exposed to river water in the control stream had very low concentrations of 60Co, less than 3 pCi per gram dry weight (pCi/g DW). Other radionuclides were essentially unmeasurable. Biota exposed to trench water accumulated very high relative concentrations of 60Co. Biota exposed to trench water also had measurable concentrations of 155Eu, 144Ce, 141Ce, 125Sb, 124Sb, 103Ru, 106Ru, 137Cs, 95Zr, 95Nb, 58Co, 54Mn, 59Fe, 65Zn, 90Sr, /sup 239,240/Pu, and 238Pu. Biota exposed to ground water had concentrations of 60Co that ranged between 50 and 1200 pCi/g DW. Fish flesh had the lowest concentration of 60Co and algae the highest. Strontium-90 was measured in the tissues of aquatic biota at concentrations ranging between 360 pCi/g DW in clam flesh to 3400 pCi/g DW in leaves and stems of Veronica. Leaves and fruits of tomato plants rooted in the ground water accumulated 90Sr at concentrations of 160 pCi in fruits and 4200 pCi in leaves. Data indicate that 60Co and 90Sr migrated through the ground along with ground-water flow and were available to all classes of aquatic biota and tomato plants rooted in the water via root uptake, sorption, and food chain transfers. 8 refs., 4 figs., 6 tabs

  4. Pollution of atmospheric air with toxic and radioactive particulate matter investigated by means of nuclear techniques

    The application of spectrometric methods of nuclear techniques to the investigations of atmospheric air pollution by toxic and radioactive elements and results of these investigations conducted in the highly industrialized and urbanized regions of Poland have been presented. The method of precipitation of the samples, the measurements and analysis of radiation spectra of alpha and gamma radiation emitted by isotopes present in the samples have been described. The concentrations of toxic metal dust in the air have been evaluated by neutron activation and X-ray fluorescence analysis. Appropriate methods of measurement, calibration of instrument and the discussion of results have been presented. The work presents the results of investigations performed in Siersza within the years 1973-1974 and in Warsaw in the period of 1975-1977, which have permitted to estimate the mean monthly values of concentration in the atmospheric air of the following radioisotopes: 7Be, 54Mn, 95Zr, 103Ru, 106Ru, 125Sb, 131I, 137Cs, 140Ba, 141Ce, 144Ce, 226Ra, Th-nat, U-nat and the following stable elements: Sc, Cr, Fe, Co, Zn, As, Se, Sb, W, Pb. The analysis of changes in concentration of each particular artificial radioisotope in the air for the region of Poland in connection with Chinese nuclear explosions have been given. On the basis of the performed environmental investigations the method of analysis of relations between the concentrations of particular elements present in the dust has been discussed. The applications of this method have been presented. The hazard to the population and the environment caused by the radioactive and toxic dust present in the atmospheric air has been estimated. (author)

  5. Separation of plutonium from uranium and fission products in the zirconium pyrophospate column

    Distribution coefficients were of the following ions were determined in the system zirconium pyrophosphate - aqueous solution HNO3 : Pu3+, Pu4+, PuO22+, UO22+, 234Th2+, 95Zr, 95Nb, 106Ru, 144Ce3+, 90Sr2+, 137Cs+, 59Fe3+ and 59Fe2+. According to the distribution coefficients it can be concluded that the separation of some cations is possible. This was proved by using separation columns. The following successful separations were completed: 90Sr2+ from 90I3+, 90Sr2+ from 90I3+ and 1'37Cs+, UO2+ from 234Th4+, Pu4+ from UO22+, 95Zr, 95Nb, 106Ru, 144Ce3+, 90Sr2+, 137Cs+. Decontamination factors of plutonium from the mentioned cations were determined. It was found that the sorption of Cs+ and Sr2+ is based on ion exchange

  6. Yield-Energy Dependence for 147Nd and 144Ce Under Strong Neutron Field

    QIAN; Jing; LIU; Ting-jin; SUN; Zheng-jun; SHU; Neng-chuan

    2012-01-01

    <正>The data of the fission product yield play an important role in the nuclear science technology and nuclear engineering because they are the key data in the calculation of the decay heat, shield design, nuclear verification, radiochemistry reprocessing and nuclear safety, etc. Especially, it is the essential data in fission power estimation for a fission device. It is well known that there exists a consecutive neutron spectrum with the energy from 1 keV to 15 MeV for a fission-fusion device. So in order to estimate the

  7. Sorption of radionuclides from Pb-Bi melt. Report 1

    Results of laboratory investigations of sorption and interfacial distribution of 54Mn, 59Fe, 60Co, 106Ru, 125Sb, 137Cs, 144Ce, 154,155Eu and 235,238U radionuclides in the system Pb-Bi melt - steel surface are analyzed. It is shown that 106Ru and 125Sb are concentrated in Pb-Bi melt and other radionuclides with higher oxygen affinity are sorbed on oxide deposits on structural materials. Temperature dependences of sorption efficiency of radionuclides are studied. It is shown that there is sharp increase of this value for all radionuclides near the temperature range 350-400 deg C. Recommendations are given on the use of 106Ru and 125Sb as a reference for fuel element rupture detection system with radiometric monitoring of coolant melt samples and 137Cs, 134Cs, 134mCs with radiometric monitoring of sorbing samples

  8. Radionuclides contamination of fungi after accident on the Chernobyl NPP

    Zarubina, Nataliia E.; Zarubin, Oleg L. [Institute for Nuclear Research of National Academy of Sciense, 03680, pr-t Nauki, 47, Kiev (Ukraine)

    2014-07-01

    Accumulation of radionuclides by the higher fungi (macromycetes) after the accident on the Chernobyl atomic power plant in 1986 has been studied. Researches were spent in territory of the Chernobyl alienation zone and the Kiev region. Our research has shown that macromycetes accumulate almost all types of radionuclides originating from the accident ({sup 131}I, {sup 140}Ba /{sup 140}La, {sup 103}Ru, {sup 106}Ru, {sup 141}Ce, {sup 144}Ce, {sup 95}Nb, {sup 95}Zr, {sup 137}Cs and {sup 134}Cs). They accumulate the long-living {sup 90}Sr in much smaller (to 3 - 4 orders) quantities than {sup 137}Cs. We have established existence of two stages in accumulation of {sup 137}Cs by higher fungi after the accident on the Chernobyl NPP: the first stage resides in the growth of the concentration, the second - in gradual decrease of levels of specific activity of this radionuclide. Despite reduction of {sup 137}Cs specific activity level, the content of this radionuclide at testing areas of the 5-km zone around the Chernobyl NPP reaches 1,100,000 Bq/kg of fresh weight in 2013. We investigated dynamics of accumulation of Cs-137 in higher fungi of different ecological groups. One of the major factors that influence levels of accumulation of {sup 137}Cs by fungi is their nutritional type (ecological group). Fungi that belong to ecological groups of saprotrophes and xylotrophes accumulate this radionuclide in much smaller quantities than symbio-trophic fungi. As a result of the conducted research it has been established that symbio-trophic fungi store more {sup 137}Cs than any other biological objects in forest ecosystems. Among the symbio-trophic fungi species, species showing the highest level of {sup 137}Cs contamination vary in different periods of time after the deposition. It is connected with variability of quantities of these radio nuclides accessible for absorption at the depth of localization of the main part of mycelium of each species in a soil profile. Soil contamination

  9. [Comparative analysis of the radionuclide composition in fallout after the Chernobyl and the Fukushima accidents].

    Kotenko, K V; Shinkarev, S M; Abramov, Iu V; Granovskaia, E O; Iatsenko, V N; Gavrilin, Iu I; Margulis, U Ia; Garetskaia, O S; Imanaka, T; Khoshi, M

    2012-01-01

    The nuclear accident occurred at Fukushima Dai-ichi Nuclear Power Plant (NPP) (March 11, 2011) similarly to the accident at the Chernobyl NPP (April 26, 1986) is related to the level 7 of the INES. It is of interest to make an analysis of the radionuclide composition of the fallout following the both accidents. The results of the spectrometric measurements were used in that comparative analysis. Two areas following the Chernobyl accident were considered: (1) the near zone of the fallout - the Belarusian part of the central spot extended up to 60 km around the Chernobyl NPS and (2) the far zone of the fallout--the "Gomel-Mogilev" spot centered 200 km to the north-northeast of the damaged reactor. In the case of Fukushima accident the near zone up to about 60 km considered. The comparative analysis has been done with respect to refractory radionuclides (95Zr, 95Nb, 141Ce, 144Ce), as well as to the intermediate and volatile radionuclides 103Ru, 106Ru, 131I, 134Cs, 137Cs, 140La, 140Ba and the results of such a comparison have been discussed. With respect to exposure to the public the most important radionuclides are 131I and 137Cs. For the both accidents the ratios of 131I/137Cs in the considered soil samples are in the similar ranges: (3-50) for the Chernobyl samples and (5-70) for the Fukushima samples. Similarly to the Chernobyl accident a clear tendency that the ratio of 131I/137Cs in the fallout decreases with the increase of the ground deposition density of 137Cs within the trace related to a radioactive cloud has been identified for the Fukushima accident. It looks like this is a universal tendency for the ratio of 131I/137Cs versus the 137Cs ground deposition density in the fallout along the trace of a radioactive cloud as a result of a heavy accident at the NPP with radionuclides releases into the environment. This tendency is important for an objective reconstruction of 131I fallout based on the results of 137Cs measurements of soil samples carried out at

  10. Radionuclides contamination of fungi after accident on the Chernobyl NPP

    Accumulation of radionuclides by the higher fungi (macromycetes) after the accident on the Chernobyl atomic power plant in 1986 has been studied. Researches were spent in territory of the Chernobyl alienation zone and the Kiev region. Our research has shown that macromycetes accumulate almost all types of radionuclides originating from the accident (131I, 140Ba /140La, 103Ru, 106Ru, 141Ce, 144Ce, 95Nb, 95Zr, 137Cs and 134Cs). They accumulate the long-living 90Sr in much smaller (to 3 - 4 orders) quantities than 137Cs. We have established existence of two stages in accumulation of 137Cs by higher fungi after the accident on the Chernobyl NPP: the first stage resides in the growth of the concentration, the second - in gradual decrease of levels of specific activity of this radionuclide. Despite reduction of 137Cs specific activity level, the content of this radionuclide at testing areas of the 5-km zone around the Chernobyl NPP reaches 1,100,000 Bq/kg of fresh weight in 2013. We investigated dynamics of accumulation of Cs-137 in higher fungi of different ecological groups. One of the major factors that influence levels of accumulation of 137Cs by fungi is their nutritional type (ecological group). Fungi that belong to ecological groups of saprotrophes and xylotrophes accumulate this radionuclide in much smaller quantities than symbio-trophic fungi. As a result of the conducted research it has been established that symbio-trophic fungi store more 137Cs than any other biological objects in forest ecosystems. Among the symbio-trophic fungi species, species showing the highest level of 137Cs contamination vary in different periods of time after the deposition. It is connected with variability of quantities of these radio nuclides accessible for absorption at the depth of localization of the main part of mycelium of each species in a soil profile. Soil contamination by 137Cs is one of the principal abiotic influences on the accumulation of this radionuclide by fungi

  11. Oral Zn-DTPA therapy for reducing 141Ce retention in suckling rats

    In neonatal rats DTPA reduced the intestinal retention of cerium ingested as an additive in its chloride form to milk. It also reduced retention of absorbed cerium. A similar decrease of cerium retention in gut and whole body was obtained after simultaneous or 24 hours' delayed DTPA administration. (author)

  12. Fission product release from ZrC-coated fuel particles during postirradiation heating at 1600 C

    Release behavior of fission products from ZrC-coated UO2 particles was studied by a postirradiation heating test at 1600 C (1873 K) for 4500 h and subsequent postheating examinations. The fission gas release monitoring and the postheating examinations revealed that no pressure vessel failure occurred in the test. Ceramographic observations showed no palladium attack and thermal degradation of ZrC. Fission products of 137Cs, 134Cs, 106Ru, 144Ce, 154Eu and 155Eu were released from the coated particles through the coating layers during the postirradiation heating. Diffusion coefficients of 137Cs and 106Ru in the ZrC coating layer were evaluated from the release curves based on a diffusion model. 137Cs retentiveness of the ZrC coating layer was much better than that of the SiC coating layer. ((orig.))

  13. Measurement of leaching from simulated nuclear-waste glass using radiotracers

    The use of radiotracer spiking as a method of measuring the leaching from simulated nuclear-waste glass is shown to give results comparable with other analytical detection methods. The leaching behavior of 85Sr, 106Ru, 133Ba, 137Cs, 141Ce, 152Eu, and other isotopes is measured for several defense waste glasses. These tests show that radiotracer spiking is a sensitive, multielement technique that can provide leaching data, for actual waste elements, that are difficult to obtain by other methods. Additionally, a detailed procedure is described that allows spiked glass to be prepared with a suitable distribution of radionuclides

  14. Three-dimensional plume dynamics in the vadose zone: PORFLO-3 modeling of a defense waste leak at Hanford

    In 1973, approximately 450 m3 of liquid containing radioactive and chemical wastes leaked from the 241-T-106 single-shell tank into the vadose zone at the US Department of Energy's Hanford Site in south-central Washington State. The extent of the 137Cs, 144Ce, and 106Ru contaminant plumes in the vadose zone was estimated in 1973 and 1978 by gamma spectrometry in monitoring wells. Using site data and the PORFLO-3 computer model, a three-dimensional, transient plume migration model was developed for 106Ru and 137Cs. The model was calibrated to the 1973 measured plumes of 106Ru and 137Cs. The calibrated model was then used to study plume migration up to 1990. The simulated 106Ru distribution for 1978 extended deeper than reported values. The simulated distribution of 137Cs for 1978 approximated the measured distribution; the 1973 and 1978 137Cs distributions are similar because of the long half-life and high sorption coefficient of 137Cs. 8 figs., 15 refs

  15. Influence of complex formation on extraction of some fission products by sorption on inorganic sorbents

    Sorption of fission products of radionuclides 137Cs, 89,90Sr, 90,91Y, 86Rb, 133Ba, 95Zr+95Nb, 95Nb, 103,106Ru, 141,144Ce, 115mCd, 113Sn, 125Sb by hydroxides Fe(III), Mn(IV) on the background of 1 mol/l of NaNO3 at the pretense of ions SO42-, C2O42- at a wide ph range (1+14) is studied in present work. Optimal conditions of extraction of each radionuclide by sorption on inorganic sorbents are defined.

  16. Behaviour of solid fission products in the HTGR coated fuel particles

    Results of profile measurements for volume concentrations of 134,137Cs, 144Ce, 155Eu, 106Ru and fissionable material in the HTGR coated fuel particles which have been subjected to standard tests in the temperature range of 1273-2133 K and at burnup up to 17% fima are presented. Values of the effective coefficients of cesium diffusion in kern and protective coating of fuel particles which were subjected to standard in-pile tests in spherical fuel elements at the temperature of 1273 K and the burnup up to 15% fima as well as the value of relative release of solid fission products from the samples studied are given

  17. Proposed Search for a Fourth Neutrino with a PBq Antineutrino Source

    Several observed anomalies in neutrino oscillation data can be explained by a hypothetical fourth neutrino separated from the three standard neutrinos by a squared mass difference of a few eV2. We show that this hypothesis can be tested with a PBq (ten kilocurie scale) 144Ce or 106Ru antineutrino beta source deployed at the center of a large low background liquid scintillator detector. In particular, the compact size of such a source could yield an energy-dependent oscillating pattern in event spatial distribution that would unambiguously determine neutrino mass differences and mixing angles.

  18. 1. Quarterly progress report 1984

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, sewage water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 54Mn, 58Co, 60Co, 90Sr, 95Nb, 106Ru, 110Ag, 125Sb, 131I, 134Cs, 137Cs, 144Ce, 226Ra, U, K, T and Rn). This report exposes also the state of surveillance and assistance operations on work sites and, the state of incidents along the three months; a bibliographic selection is also presented

  19. Dynamics of contents and organic forms of radionuclide compounds in the liquid phase of forest soils in the zone of contamination from the Chernobyl Nuclear Power Plant

    In the profile of forest soils in a 30-km zone around the Chernobyl nuclear power plant (NPP), in areas characterized by different positions in relation to the source of emission, the authors determined the relative contents of long-lived radionuclides 106Ru, 134,137Cs, and 144Ce in soil solutions (as of 1987). On the example of 137Cs, they consider the dynamics (1987-1990) of relative contents and forms in which the radionuclide is found in the liquid phase of soils in the zone of radioactive contamination from the Chernobyl NPP

  20. Silviculture-ecological consequences of forest pollution due to radioactive effluents

    Radioactive contamination effect on the forest areas of Pripyat' Polessie is considered. Radiation processes in damaged pinetree plantations are characterized. Radionuclide migration dependent on soil types and tree stocks is analyzed. The data analysis has shown the evidence of 144Ce, 1'37Cs, 134Cs, 106Ru in 3 years after radioactive contamination in the controlled area. By the end of the third year a significant radionuclide migration had occurred between the forest floor and lower aquifers. refs. 2; figs. 2; tabs. 8

  1. A Dosimetry of 106-Ru - 106- Rh Electron-Photon Field with LiF TLD-100 'Microcubes'

    Background and purpose: Ru-Rh eye applicators are used for the radiotherapy of eye malignancies such as melanomas. The producer (BEBIG GmbH) declares ±30% dose uncertainty in the applicator certificate. There is an obvious need to overcome this large imprecision. Our goal is to establish a method that is fast and reliable and which reduces dose uncertainty to below ±10%. Materials and methods: A pleksiglas phantom containing spherical calottes was constructed for this purpose. It allows measurements of surface homogeneity, absolute surface dose rates and depth doses in 2 mm steps, on and off the symmetry axis. Very small, 1x1x1 mm3 thermoluminescent dosimeters (TLD) were chosen as dosimeters. They have to be calibrated adequately for Ru-Rh dosimetry. To do that, 60Co/electron field response ratio of TLDs was investigated and correction factors were established. Doses to the base of optic nerve were considered. Results: The 60Co/electron beam response ratio of TLDs is in agreement with measured and calculated results reported by other authors (for LiF TLD-100 of different dimensions). The measurements of surface dose rate homogeneity show deviations of up to 15% of the mean surface dose rate. However, surface inhomogeneities average out deeper in the phantom. Absolute surface dose rates were found lower than those declared by the producer by 6.2%, averaged over 8 applicators investigated. On and off axis depth doses are highly uniform over angle θ=40 degrees from symmetry axis, up to 6 mm in depth. Therefore, depth doses form spherical isodose surfaces within stated angle, spanning at least 1.47 steradians. Depth dose functions were interpolated to the measured data for practical routine use. Conclusions: The method developed here has overall combined uncertainty <±6%, and therefore reduces significantly uncertainty declared by the producer. Also, it proved to be stable on repeated measurements. (author)

  2. Characterization of Inner Tracker silicon prototype sensors using a 106 Ru-source and a 1083 nm laser system

    Bauer, C; Pugatch, V; Schmelling, M; Schwingenheuer, B; Sievers, P

    2001-01-01

    Silicon strip sensors will be used as technology for the LHCb Inner Tracker. The signal-to-noise ratio (S/N) and the charge division among two neighbouring strips are important sensor parameters. In order to investigate the charge sharing between two adjacent strips, measurements with a 1083 nm laser were performed. Minimum ionizing electrons from a ruthenium-source were used to study the S/N-performance of the silicon sensors. The S/N-measurements were also performed with sensors after irradiation with 24 GeV protons up to a fluence of 1.7*10^14 cm^-2, corresponding to more than 10 years of LHCb Inner Tracker operation in the most irradiated zones.

  3. Measurement of dose rate from 106Ru/106Rh ophthalmic applicators by means of alanine-polymer foils

    Ophthalmic applicators are used in radiotherapy for the treatment of malignant choroidal melanomas. The applicators are positioned on the eye at the base of the tumor for a period of a few days up to 2 weeks. They are commercially available in the form of caps of a spherical radius of 12 or 13 mm. Two or three fixing lugs are used for suturing the applicator to the eye. The applicators are made of silver. The active layer is covered with 0.1 mm silver in the concave direction, and 0.9 mm silver in the convex direction. The β-radiation emitted from the concave side may be used for treatment, to a depth up to 5 mm. Measurements of dose rate by means of ESR/alanine dosimetry and TLD are described. It is concluded that ESR/dosimetry and TLD are well suited for this application. (author)

  4. Concentration and depuration of some radionuclides present in a chronically exposed population of mussels (Mytilus edulis)

    Factors are described which affect the concentration (p Ci g-1 dry wt) and loss of 241 Am, 239+240Pu, 238Pu, 144Ce, 137Cs, 134Cs, 106Ru, 95Zr and 95Nb in an exposed population of mussels Mytilus edulis L. from Ravenglass on the Esk estuary, Cumbria, UK which receives radioeffluents from the British Nuclear Fuels Ltd. (BNFL) plant at Sellafield, some 10 km to the north. Tidal position and mussel body size have a negligible influence on the concentration of 241Am, 137Cs and 106Ru in the total soft tissue, but variation in soft tissue weight throughout the year has a considerable influence on the apparent concentration and depuration times of these radionuclides. Apart from the clearance (tsub(1/2) biol, 1 to 3 h) of sediment-associated activity from the digestive tract, the depuration rate profiles follow a single component clearance curve with a biological half-life in excess of 200 d for 241 Am, 239+240Pu, 238Pu and 144Ce, and of 40 d for 137Cs. The clearance of 106Ru is more complex and consists of a 3 component depuration profile with biological half-lives of 6 h, 12 d and 260 d. The depuration profiles presented in this work are for chronically ingested isotopes under natural conditions; acute exposure will most likely result in different profiles, especially those derived from laboratory spiking experiments. Isotope ratio data support the hypothesis that the main route of entry into the mussel for the majority of the radionuclides studied is from the water. (orig./WL)

  5. Development of removal methods of radioactive ruthenium by using the column packed with cell materials

    Ruthenium is an element of various valencies and present in many chemical species of nitro-nitrosyl complexes in nitric acid or in solutions containing nitrates. Since radioactive ruthenium (103Ru, 106Ru) of those chamical species is contained in the wastes occurred on the fuel reprocessing by Purex method and others, it is one of the nuclides which are most difficult to be removed by the conventional methods of the radioactive waste treatments. It was found that this nuclide was effectively removed by passing the waste solution through a column packed with the mixture of powder of anode and cathode materials and depolarizers used in the electric cells. The typical mixtures were zinc-charcoal, zinc.palladium-charcoal, zinc-manganese dioxide.charcoal and zinc-carbon fluoride.charcoal. These column methods showed a surpassing removel efficiency for 106Ru complexes and fisson products. The decontamination factors of radioactive ruthenium were 104 for all kinds of ruthenium complexes and 102 for the species not easily removed by the conventional methods. It was also found that the concentrations of 239Pu, U, 144ce, 155Eu, and 125Sb in the waste could be decreased to that below the limits of detection by the cell material columns. Because 106Ru of chemical species which was difficult to be removed by conventional methods could be efficiently separated from the waste solutions, it was concluded that the columns packed with cell materials are valuable tools in the radioactive waste treatments. (author)

  6. Behaviour of the radionuclides 125J, 85Sr, 134Cs and 144Ce in three typical sands of Northern Germany under conditions of water-unsaturated flow

    The investigations described in this study help to explain the migration of radionuclides, being in the seepage water, in the upper soil layers. We investigated the behaviour of the radionuclides of the elements J, Sr, Cs and Ce in three types of loose rocks taken from the C-horizon of characteristic soils existing in the surroundings of Gorleben (Lower Saxony). These loose rocks are medium- and fine-grained sands. In the laboratory we performed Batch and column experiments under the conditions of water-unsaturated flow. For these investigations we used an experimental rainwater, which we had prepared on the basis of the analytic mean values obtained for the rainwater of the Gorleben surroundings. (orig./RW)

  7. Studies on inorganic exchangers - manganese dioxide

    As a part of investigation of separation processes for long lived fission products from fuel reprocessing solution, manganese dioxide has been studied as an ion exchanger for cerium using 137Cs, 106Ru, 141Ce, sup(85,89)Sr, 95Zr and 95Nb as tracers. For different concentrations of HNO3, distribution ratios and breakthrough capacities were determined. Cerium was eluted by manganese sulphate and nitric acid. Results show that : (1) at all acidities cerium is adsorbed with almost no uptake of other rare earths, sodium, uranium and plutonium, (2) Ce (IV) gives better adsorption than Ce(III), (3) a combination of manganese sulphate (1 mg/ml) and 3M nitric acid elutes 99% cerium in 5-6 column volumes and (4) as for effect of absorption-elution cycles on MnO2 column, initially there is a decrease in capacity of cerium uptake but thereafter the capacity remains constant. (M.G.B.)

  8. The Chernobyl fallout in Greece and its effects on the dating of archaeological materials

    The effects of the fallout from the nuclear reactor accident at Chernobyl have been monitored at various sites in Greece. Here we present the first estimates of gamma dose rates, an essential parameter in the dating of archaeological materials by thermoluminescence (TL) and ESR methods. The dose rates are derived from the long-lived radionuclides of 137Cs, 134Cs, 106Ru and 144Ce (with t1/2 ≥ 1 yr). The present dose rates vary between 30 and 60 mrad/yr, but maximum values of around 811 mrad/yr have also been recorded, for ground-surface exposures. These dose rate values must be regarded as very significant to TL and ESR dating of samples from now on and a correction factor should be applied. (orig.)

  9. Measurements of fission product concentrations in surface air at Bombay, India, during the period 1975-1981

    Measurements on airborne fallout radioactivity for the period 1975 up to the middle of 1981 are given. Normally, these measurements are confined to Bombay, but after nuclear tests, some of the other stations where these measurements were carried out in previous years are operated for some time to study the levels of fresh activity. The levels of the long-lived fission products 144Ce, 106Ru and 137Cs, and the short-lived fission products 95Zr and 140Ba, were measured, whenever they could be detected following nuclear tests, and tabulated. The data indicate that the activity varies by large factors from tests of similar yield, depending on the meteorological and other conditions. It was determined that the travel time for the Chinese test debris from Lop Nor, China to the West-coast of India is 14 to 16 days

  10. Preparative electrophoresis of industrial fission product solutions

    The aim of this work is to contribute to the development of the continuous electrophoresis technique while studying its application in the preparative electrophoresis of industrial fission product solutions. The apparatus described is original. It was built for the purposes of the investigation and proved very reliable in operation. The experimental conditions necessary to maintain and supervise the apparatus in a state of equilibrium are examined in detail; their stability is an important factor, indispensable to the correct performance of an experiment. By subjecting an industrial solution of fission products to preparative electrophoresis it is possible, according to the experimental conditions, to prepare carrier-free radioelements of radiochemical purity (from 5 to 7 radioelements): 137Cs, 90Sr, 141+144Ce, 91Y, 95Nb, 95Zr, 103+106Ru. (author)

  11. Game as a bioindicator of the radiocontamination

    Natural and artificially produced radionuclides were determined in meat and bones of deer, boar and wild hare on hunting areas in Vojvodina (Serbia). Seven natural radionuclides and three fission products (235U, 238U, 232Th, 7Be, 144Ce, 40K, 106Ru, 134Cs, 137Cs, 90Sr) were identified in the investigated game samples. The highest contents of the radionuclides were found in bones and meat of boars and the lowes in the bones of fallow-deer. The predominant radionuclides were 40K and 90Sr, for all of the investigated animals and their contents depended strongly upon the game species, organ type and the age of the animal. The examined breeding sites did not appear to have any effect on the radionuclide contents in game, which indicates that the radionuclides were uniformly distributed over the habitat. (author) 5 refs.; 3 tabs

  12. Calculated activities of some isotopes in the RA reactor highly enriched fuel significant for possible environmental contamination - Operational report

    This report contains calculation basis and obtained results of activities for three groups of isotopes in the RA reactor 80% enriched fuel element. The following isotopes are included: 1) 85mKr, 87Kr, 88Kr, 131J, 132J, 133J, 134J, 135J, 133Xe, 138Xe i 138Cs, 2) 89Sr, 90Sr, 91Sr, 92Sr, 95Zr, 97Zr, 103Ru, 105Ru, 106Ru, 129mTe, 134Cs, 137Cs, 140Ba, 144Ce, kao i 3) 238Pu, 239Pu i 240Pu. It was estimated that the fuel is exposed to mean neutron flux. The periodicity of reactor operation is taken into account. Calculation results are given dependent on the time of exposure. These results are to be used as source data for Ra reactor safety analyses

  13. Transuranic elements and strontium-90 in samples from forests in Poland

    Enhanced levels of non-volatile nuclides;141,144Ce, 95Zr, 95Nb, 103,106Ru, 238,239,240,241Pu, 241Am, 242,243,244Cm and 154,155Eu were observed in the samples from north-western Poland. This was considered to be a result of finding in sample ''hot particle''. Investigations conducted in the Institute of Nuclear Physics allowed us to conclude that on this area a non typical isotopic composition of Chernobyl fallout was very common. The enhanced activities (up to 100% above the global fallout value) of 90Sr, 238,239,240Pu and 241Am were observed. The presence of 243,244Cm and 154,155Eu was confirmed. It seems that the quasi-continuous fallout of huge numbers of small 'hot particles' occurred there from the high altitude radioactive cloud, which moved toward Scandinavia on 26-th of April, 1986. (author)

  14. 4. Quaterly progress report 1983

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, sevrage water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 58Co, 60Co, 75Se, 103Ru, sup(110m)Ag, 124Sb, 125Sb, 134Cs, 137Cs, 144Ce, 90Sr, 95Nb, 106Ru, 226Ra, 54Mn, U, K and T). This report exposes also the state of surveillance and assistance operations on work sites and, the state of incidents along the three months; a bibliographic selection is also presented

  15. Application of the radiochemical - and the direct gamma ray spectrometry method to the burnup determination of irradiated uranium oxide

    The burn up of natural U3O8 that occurs by the action of thermal neutrons was determined, using the radioisotopes 144Ce, 137Cs, 103Ru, 106Ru and 95Zr as monitors. The determination of the burn up was made using both destructive and non-destructive methods. In the non-destructive method, the technique of direct gamma-ray spectrometry was used and the radioisotopes mentioned were simultaneously counted in a Ge-Li detector. In the radiochemical method the same radioisotopes were isolated one from the other and from all other fission products before counting. The solvent extraction technique was used for the radiochemical separation of uranium, cerium, cesium and ruthenium. To separate zirconium and niobium, adsorption in silica-gel was used. The extraction agent employed to isolate cesium was dipycrilamine and for the separation of the other radioisotopes Di-(2-Ethyl Hexyl) Phosphoric acid (HDEHP) was used. (Author)

  16. Influence of the complexones on the ionic transfer through cell membranes and the level of radionuclides-metals accumulation in water plants

    The influence of the complexones diethylenetriaminepentaacetic acid (DTPA), ethylenediaminetetraacetic acid (EDTA) and hydroxyethylidenediphosphonic acid (HEDP) with relatively low concentrations (from 0.1 to 50 mg/l) on ionic permeability of cell membranes of Nitellopsis obtusa algae, as well as on the accumulation levels of the radionuclides 144Ce, 106Ru, 90Sr and 137Cs in different species of water plants has been studied. It has been shown that complexones under study (with the concentrations up to 50 mg/l) may reduce accumulation levels of three- and four-valent metals and their radionuclides in water plants. For the plants in natural as well as in artificial nutrient medium, however, the complexones increase the availability of metals, forming with the readibly soluble, mobile complex compounds

  17. Critical pathway studies for selected radionuclides. Part of a coordinated programme on environmental monitoring for radiological protection in Asia and the Far East

    The programme carried out critical pathway studies for selected radionuclides (60Co, 63Ni, 59Fe, 54Mn, sup(110m)Ag, 106Ru and 144Ce) and assessed population exposure in the vicinity of Tarapur Atomic Power Station. The following topics are covered under the programme. (i) Demographic study of dietary habits and consumption data for Tarapur population. (ii) Concentration and accumulation of radionuclides in food products. (iii) Determination of radionuclides in sea water, silt, marine algae and marine organisms at Tarapur Atomic Power Station (TAPS) Site. (iv) Behaviour of radionuclides released to marine environment. (v) Evaluation of critical exposure pathway. (vi) Population exposure in the vicinity of Tarapur Atomic Power Station

  18. Radiation accidents on human in the nuclear installations and their medical emergency procedures, (1)

    Present nuclear installations are one of the safest installations among industrial facilities, being equipped with various safety instruments. Since X-ray was discovered in 1895, however, many radiation injuries of various degrees and kinds occurred. Among dangerous nuclides often observed as radioactivity pollutions in nuclear installations, the exposure to β-ray such as 90Sr, 106Ru, 95Zr, 131I, 144Ce, etc, is considered to be serious problems. When they affect wounds or are inhaled into lungs, only symptomatic treatment is practicable at present, and usually nothing can be depended upon, but spontaneous eliminating ability. As the mass inhalation of α nuclides, especially transuranium nuclides, is quite dangerous, the treatment by lung-irrigation now under development is most effective as the emergency treatment. When trans-uranium nuclides were accidentally observed from wounds, they should be eliminated by the injection of chelating agent. (Kobatake, H.)

  19. Batch extraction studies for the recovery of 233U from thoria irradiated in PHWR

    Batch equilibrium studies were carried out to optimise the extraction parameters for the recovery of 233U from thoria irradiated in PHWR. The thorium concentration and the acidity of the feed was adjusted to ca. 100 g/l and 4 M nitric acid respectively. The concentration of uranium was in the range of 1.4 g/L and it contained long lived fission product like 144Ce-144Pr, 134Cs, 137Cs, 106Ru-106Rh, 105Eu, 154Eu, 90Sr-90Y and 125Sb. 3% TBP in dodecane was used as the solvent. Four stages of batch extraction was followed by a single scrub stage of 4 M nitric acid. The scrubbed organic was stripped with 0.01 M HNO3 thrice. The stripped product was concentrated by evaporation and passed through a cation exchanger to remove the residual thorium. The results of the studies are discussed in detail. (author)

  20. Specific processes in solvent extractiotn of radionuclide complexes

    The doctoral thesis discusses the consequences of the radioactive beta transformation in systems liquid-liquid and liquid-ion exchanger, and the effect of the chemical composition of liquid-liquid systems on the distribution of radionuclide traces. A model is derived of radiolysis in two-phase liquid-liquid systems used in nuclear chemical technology. The obtained results are used to suggest the processing of radioactive wastes using the Purex process. For solvent extraction the following radionuclides were used: 59Fe, 95Zr-95Nb, 99Mo, sup(99m)Tc, 99Tc, 103Pd, 137Cs, 141Ce, 144Ce-144Pr, 234Th, and 233Pa. Extraction was carried out at laboratory temperature. 60Co was used as the radiation source. Mainly scintillation spectrometry equipment was used for radiometric analysis. (E.S.)

  1. Characterization of gaseous and particulate effluents from the nuclear vitrification project

    Samples were taken during the second high-level liquid waste vitrification campaign associated with the NWVP. Sample analysis established the following total average emission levels in the undiluted vitrification off-gas stream: 3H - 1.2 μCi/m3, 14C - 0.2 μCi/m3, 129I - 1 nCi/m3, NO/sub x/ - 0.5%, 99Tc - 1.6 pCi/m3, and γ-emitters - 105(γ/s)/m3. The aerosol size distribution is composed almost entirely of particles exhibiting smaller diameters than the minimum value for which absolute filters are rated, with an empirical geometric mean diameter of 0.13 μm and a particle mass concentration of 84.7 pg/cm3. The particulate matter was composed of 106Ru, 125Sb, /sup 125m/Te, 134Cs, 137Cs, 144Ce, 154155Eu and 241Am. The particulate emission levels in the undiluted process off-gas stream were: 106Ru - 44 nCi/m3, 125Sb - 0.52 nCi/m3, /sup 125m/Te - 1.7 nCi/m3, 134Cs - 7.8 nCi/m3, 137Cs - 52 nCi/m3, 144Ce - 0.8 μCi/m3, 154Eu - 0.3 nCi/m3, 155Eu - 0.18 nCi/m3, and 241Am - 0.19 nCi/m3. All these environmental gaseous and airborne emissions level liquid waste were well within PNL waste management guidelines

  2. Cycling of radionuclides and impact of operational releases in the near-shore ecosystem off the west coast of India

    Radioecology of the near-shore environment was investigated at Bombay and Tarapur on the west coast of India. The major radionuclides released from the processing plant at Bombay were 137Cs, 144Ce and 106Ru and were discharged through a pipeline to Bombay Harbour bay. At Tarapur the major radionuclides discharged were 131I, 134Cs, 137Cs and 60Co. After dilution with condenser-coolant sea water, releases were carried out through open channels along the shoreline to the sea. Studies on radionuclide cycling in clam-bed sediment, the indicator type benthic organism Anadara granosa, and the fish gobiid mudskipper in Bombay Harbour bay showed that the effective half-life of 137Cs is short compared with the physical half-life (30 years). This is attributable to the desorption of 137Cs from sediment and the fact that the benthic organism readily equilibrates with its environment. The dose to the benthic organism was calculated to be about 0.06 to 3μGy/h. Desorption of 144Ce and 106Ru was not observed. Investigations at Tarapur showed the effective distribution of radionuclides in sea water, sediment, seaweed and marine organisms. It was observed that the radionuclides discharged were mainly confined to a region 2 km from the outfall. The highest activity found in these matrices was only 7% of the derived maximum permissible concentration. The highest thyroid dose due to 131I by fresh seafood intake was 3% of the permissible dose and the highest whole-body dose due to other radionuclides was only 1% of the permissible dose. (author)

  3. The accumulation of radionuclides by Dreissena polymorpha molluscs - The Accumulation of Radionuclides from Water and Food in the Dreissena polymorpha Mollusks

    Jefanova, O.; Marciulioniene, D. [Nature Research Centre, Akademijos str. 2, LT-08412 Vilnius, Lietuva (Lithuania)

    2014-07-01

    The specific activity of {sup 137}Cs, {sup 60}Co, {sup 54}Mn, {sup 90}Sr was measured in mollusks Dreissena polymorpha samples from lake Drukshiai that is the cooling pond of the Ignalina NPP. Item the accumulation of {sup 137}Cs, {sup 90}Sr, {sup 144}Ce, {sup 106}Ru in the mollusks from water and from phytoplankton which is a part of their diet was evaluated under laboratory conditions. The data of long-term (1991-2009) studies conducted at six monitoring stations of lake Drukshiai show that in 1991 {sup 137}Cs in mollusks Dreissena polymorpha was found only in that lake's area which was influenced by the effluent that got into lake from the industrial drainage channel of Ignalina NPP. In later periods of the investigation the {sup 137}Cs specific activity was detected in mollusks samples which had been collected at other monitoring stations (the aquatory of lake Drukshiai). Meanwhile {sup 60}Co and {sup 54}Mn in Dreissena polymorpha were detected only in that lake's area which was impacted by the industrial drainage channel. The data of long-term investigation show that the major amount of radionuclides has come into lake Drukshiai through the industrial drainage system of Ignalina NPP. Albeit {sup 137}Cs, {sup 90}Sr, {sup 144}Ce, {sup 106}Ru get into the mollusks through a large amount of the water rather than from the food (phytoplankton), therefore the food can also be the main source of radionuclides in the organism of these mollusks in aquatic environment when there are low levels of specific activities of these radionuclides. (authors)

  4. Studies of environmental radioactivity in Cumbria

    Five stations collecting samples of atmospheric deposition were set up in north Cumbria along a line running inland from the coast for about 17 km. Sampling was continuous from September 1980 to September 1981. Monthly samples were analysed for 106Ru, 137Cs, 144Ce, 238Pu, sup(239,240)Pu, 241Am, 7Be and stable Na, Cl and Al. The objective of the work was to measure the deposition of radionuclides as a function of distance from the sea. By estimating the contributions to the deposition of nuclear weapon test material and of the atmospheric discharges from the British Nuclear Fuels plc works at Sellafield, the effects of the transfer to air and land of radionuclides in the sea could be established. The marine radionuclides were due to the discharges to sea from the Sellafield works. The measurements showed that the deposition was largely due to the sea-to-land transfer process. The highest depositions observed were at 20 m from high water mark, the annual values (rounded, in Bq m-2) being 106Ru, 500; 137Cs, 650; plutonium, 70; 241Am, 30. The highest concentrations in rainwater for the radionuclides studied were less than 3 per cent of the fresh water limits (drinking only) GDL values. The highest estimated accumulations in soil due to atmospheric deposition were less than 1 per cent of the limits. (author)

  5. Release behavior of metallic fission products from pyrocarbon-coated uranium-dioxide particles at extremely high temperatures

    Hayashi, Kimio; Fukuda, Kousaku (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment)

    1990-04-01

    Uranium-dioxide particles coated by pyrocarbon (BISO), which were irradiated at 1,300 {approx} 1,400degC to burnups of ca. 1% FIMA, were heated isochronally and isothermally at temperatures between 1,600 and 2,300degC. Release fractions of {sup 137}Cs, {sup 155}Eu and {sup 106}Ru were larger than 10{sup -2} after heating at 2,000degC for 2 h; the results were in contrast to much smaller release fractions from TRISO particles with intact silicon-carbide (SiC) coating. The release of {sup 137}Cs and {sup 144}Ce from the BISO particle was controlled by diffusion in the dense pyrocarbon layer at temperatures between 1,600 and 2,300degC, while that of {sup 155}Eu and {sup 106}Ru was controlled by diffusion in the fuel kernel above 1,800degC. These results can be used as reference data on release behavior of the fission products from TRISO particles with defective SiC layers. (author).

  6. Release behavior of metallic fission products from pyrocarbon-coated uranium-dioxide particles at extremely high temperatures

    Uranium-dioxide particles coated by pyrocarbon (BISO), which were irradiated at 1,300 ∼ 1,400degC to burnups of ca. 1% FIMA, were heated isochronally and isothermally at temperatures between 1,600 and 2,300degC. Release fractions of 137Cs, 155Eu and 106Ru were larger than 10-2 after heating at 2,000degC for 2 h; the results were in contrast to much smaller release fractions from TRISO particles with intact silicon-carbide (SiC) coating. The release of 137Cs and 144Ce from the BISO particle was controlled by diffusion in the dense pyrocarbon layer at temperatures between 1,600 and 2,300degC, while that of 155Eu and 106Ru was controlled by diffusion in the fuel kernel above 1,800degC. These results can be used as reference data on release behavior of the fission products from TRISO particles with defective SiC layers. (author)

  7. Health risks from radionuclides released into the Clinch River

    The purpose of this work is to estimate off-site radiation doses and health risks (with uncertainties) associated with the release of radionuclides from the X-10 site. Following an initial screening analysis, the exposure pathways of interest included fish ingestion, drinking water ingestion, the ingestion of milk and meat, and external exposure from shoreline sediment. Four representative locations along the Clinch River, from the White Oak Creek Embayment to the city of Kingston, were chosen. The demography of the lower Clinch River supplied information dealing with land use that aided in the determination of sites on which to focus efforts. The locations that proved to be the most significant included Jones Island at Clinch River Mile (CRM) 20.5, Grassy Creek and K-25 (CRM 14), Kingston Steam Plant (CRM 3.5), and the city of Kingston (CRM 0). These areas of interest have historically been and are still primarily agricultural and residential areas. Reference individuals were determined with respect to the pathways involved. The primary radionuclides of interest released from the X-10 facility into the Clinch River via White Oak Creek were identified in the initial screening analysis as 137Cs, 90Sr, 60Co, 106Ru, 144Ce, 131I, 95Zr, and 95Nb. Of these radionuclides, 137Cs, 60Co, 106Ru, 90Sr, 144Ce, 95Zr, and 95Nb were evaluated for their contribution to the external exposure pathway. This study utilized an object-oriented modeling software package that provides an alternative to the spreadsheet, providing graphical influence diagrams to show qualitative structure of models, hierarchical models to organize complicated models into manageable modules, and intelligent arrays with the power to scale up simple models to handle large problems. The doses and risks estimated in this study are not significant enough to cause a detectable increase in health effects in the population. In most cases, the organ does are well below the limits of epidemiological detection (1 to 30

  8. Position of sediments in transfer of radionuclides released into coastal sea to human beings

    A great portion of radionuclides released into coastal sea is adsorbed into marine sediments and the adsorbed radionuclides causes the radioactive contamination of marine organisms and then transferred to human beings who consume them. In order to make a quantitative evaluation of this route, the transfer of 9 kinds of radionuclides from sediments to benthic organisms such as algae, bivalve and worm was observed. Then it was compared with the radioactivity in these organisms from radioactively contaminated sea water (Concentration factor). It was observed that the influence of sea water was larger than that of sediments as it was 104 times larger for 54Mn, 103 times larger for 59Fe, 60Co, 95Zr-95Nb, 106Ru-106Rh and 144Ce-144Pr, 102 times larger for 65Zn and 10-102 times larger for 115mCd and 137Cs. Consequently, sea water can be considered as the main route and sediments as the secondary in the case of quantitative comparison of the effect on the accumulation of radionuclides by marine organisms and in the transfer of radionuclides to human beings

  9. Measurement of radionuclides in bricks made from refuse ash of sewage sludge

    Since people spend about 80% of their time in buildings, in order to estimate the radiation exposure dose of nation, it is necessary to grasp indoor dose level. It has been known that as for indoor radiation exposure dose, it is different according to the types of buildings, and generally it is low in wooden houses, and high in concrete and brick buildings. This difference is due to the shielding of environmental radiation by building material and the radiation emitted from building materials themselves. In this study, the radionuclides in the bricks made of sewage slude-incinerated ash and red bricks for the reference were investigated. The radiation emitted from the bricks was measured with a thermoluminescence dosimeter (TLD). The sampling and pretreatment, the measuring method, the measurement of the radiation dose on the bricks, and the results are reported. As for the natural radionuclides in the bricks, 7Be was detected in most sludge bricks, and the concentration varied largely according to the data of sampling. It was not detected in red bricks. 40K, 214Bi and 228Ac were detected in all the sludge and red bricks. Artificial radionuclides such as 54Mn, 60Co, 106Ru, 131I, 134Cs and 144Ce were not detected in all the sludge and red bricks. The radiation dose on the sludge and red bricks was 20.5 - 21.7 mR, and constant regardless of the data of sampling. (K.I.)

  10. Application of radiochemical-and direct gamma ray spectrometry methods for the determination of the burnup of irradiated uranium oxide

    The burn-up of U3O8 (natural uranium) samples was determined by using both destructive and non-destructive methods, and comparing the results obtained. The radioisotopes 144Ce, 103Ru, 106Ru, 137Cs and 95Zr were chosen as monitors. In order to isolate the radioisotopes chosen as monitors, a separation scheme has been established in which the solvent extraction technic is used to separate cerium, cesium, and ruthenium one from the other and from uranium. The separation between zirconium and niobium and of both from the others was accomplished by means of adsorption on a silica-gel column. When the non-destructive method was used, the radioactivity of each nuclide of interest was measured in the presence of all others. For this purpose, use was made of gamma-ray spectrometry and a Ge-Li detector. The comparison of burn-up values obtained by both destructive and non-destructive methods was made by means of Student's 't' test, and it has shown that the averages of results obtained in each case are equal. (Author)

  11. Development of a CMPO based extraction process for partitioning of minor actinides and demonstration with genuine fast reactor fuel solution (155 GWd/Te)

    Antony, M.P.; Kumaresan, R.; Suneesh, A.S. [Indira Gandhi Centre for Atomic Research, Kalpakkam (IN). Fuel Chemistry Div.] (and others)

    2011-07-01

    A method has been developed for partitioning of minor actinides from fast reactor (FR) fuel solution by a TRUEX solvent composed of 0.2 M n-octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide (CMPO)-1.2 M tri-n-butylphosphate (TBP) in n-dodecane (n-DD), and subsequently demonstrated with genuine fast reactor dissolver solution (155 GWd/Te) using a novel 16-stage ejector mixer settler in hot cells. Cesium, plutonium and uranium present in the dissolver solution were removed, prior to minor actinide partitioning, by using ammonium molybdophosphate impregnated XAD-7 (AMP-XAD), methylated poly(4-vinylpyridine) (PVP-Me), and macroporous bifunctional phosphinic acid (MPBPA) resins respectively. Extraction of europium(III) and cerium(III) from simulated and real dissolver solution, and their stripping behavior from loaded organic phase was studied in batch method using various citric acid-nitric acid formulations. Based on these results, partitioning of minor actinides from fast reactor dissolver solution was demonstrated in hot cells. The extraction and stripping profiles of {sup 154}Eu, {sup 144}Ce, {sup 106}Ru and {sup 137}Cs, and mass balance of {sup 241}Am(III) achieved in the demonstration run have been reported in this paper. (orig.)

  12. Development of a CMPO based extraction process for partitioning of minor actinides and demonstration with genuine fast reactor fuel solution (155 GWd/Te)

    A method has been developed for partitioning of minor actinides from fast reactor (FR) fuel solution by a TRUEX solvent composed of 0.2 M n-octyl(phenyl)-N,N-diisobutylcarbamoyl-methylphosphine oxide (CMPO)-1.2 M tri-n-butylphosphate (TBP) in n-dodecane (n-DD), and subsequently demonstrated with genuine fast reactor dissolver solution (155 GWd/Te) using a novel 16-stage ejector mixer settler in hot cells. Cesium, plutonium and uranium present in the dissolver solution were removed, prior to minor actinide partitioning, by using ammonium molybdophosphate impregnated XAD-7 (AMP-XAD), methylated poly(4-vinylpyridine) (PVP-Me), and macroporous bifunctional phosphinic acid (MPBPA) resins respectively. Extraction of europium(III) and cerium(III) from simulated and real dissolver solution, and their stripping behavior from loaded organic phase was studied in batch method using various citric acid-nitric acid formulations. Based on these results, partitioning of minor actinides from fast reactor dissolver solution was demonstrated in hot cells. The extraction and stripping profiles of 154Eu, 144Ce, 106Ru and 137Cs, and mass balance of 241Am(III) achieved in the demonstration run have been reported in this paper. (orig.)

  13. Waste/Rock Interactions Technology Program. Status report on LWR spent-fuel leach tests

    Spent fuels with burnups of 9000, 28,000 and 54,500 MWd/MTU have been leach tested at 250C. Three leach-test procedures (Paige, IAEA and static) were used. IAEA and static tests were conducted in five different solutions: deionized water, sodium bicarbonate, sodium chloride, calcium chloride and Waste Isolation Pilot Plant B brine solutions. Elemental leach data are reported based on the release of 90Sr+90Y, 106Ru, 137Cs, 144Ce, 154Eu, 239+240Pu, 125Sb, 244Cm, 129I, 99Tc, and total uranium. This is the first report on 129I and 99Tc from spent fuel. Termination of the Paige test showed that the plateout (radionuclide adsorption) on the test apparatus had negligible effect on the leach rate of cesium and plutonium, but a major (up to a factor of 50 times) effect on the curium leach rate. Three-hundred additional days of leach testing by the IAEA procedure, from 467 to 769 d, showed a continuation of the leaching trends observed during the first 467 d. Results from the first two static leach test series, 2 and 8 d, gave the 129I and 99Tc release numbers

  14. Extrapolation of experimental data on late effects of low-dose radionuclides in man

    The situation of living of population on radionuclide contamination areas was simulated in the experimental study using white strainless rats of different ages. The significance of age for late stochastic effects of internal radionuclide contamination with low doses of 131I, 137Cs, 144Ce and 106Ru was studied. Some common regularities and differences in late effects formation depending on age were found. Results of the study showed that the number of tumors developed increased in groups of animals exposed at the youngest age. The younger animal at the moment of internal radionuclide contamination, the higher percentage of malignant tumors appeared. It was especially so for tumors of endocrine glands (pituitary, suprarenal,- and thyroid). Differences in late effects formation related to different type of radionuclide distribution within the body were estimated. On the base of extrapolation the conclusion was made that human organism being exposed at early postnatal or pubertal period could be the most radiosensitive (1.5-2.0 or sometimes even 3-5 times higher than adults). Data confirmed the opinion that children are the most critical part of population even in case of low dose radiation exposure. (author)

  15. A study of the decontamination effect of commercial detergents on the skin

    Titanium dioxide paste is generally used as the radiological skin decontaminant in the radiation control area at Japan Nuclear Cycle Development Institute (JNC) Tokai works. It is a typical and proven skin decontaminant in the nuclear industry, but there is a disadvantage in that it has a short shelf life. Recently, many detergents applicable as skin decontaminants have become available in non-nuclear industries such as cosmetics and sanitation. They are easily acquired and have an advantage in that stimulus to the skin is mild, because these products have been developed for the human body. In this study, the decontamination factor of the commercial detergents for each nuclide was examined using imitation skin. Sheets of raw pig skins were contaminated with a nitric-acid solution containing 144Ce, 137Cs, 106Ru or 60Co, and then washed with various detergents such as a neutral detergent, cleansing cream and orange oil. The nuclide removal rates of some of the commercial detergents examined were nearly equal to that of titanium dioxide, thus proving that they show satisfactory decontamination performance as a skin decontaminant. (author)

  16. Reconstruction of radionuclide releases from the Hanford Site, 1944-1972

    Historic releases of key radionuclides were estimated as a first step in determining the radiation doses that results from Hanford Site operations. The Hanford Site was built in southcentral Washington State during World War II to provide plutonium for the U.S. nuclear weapons program. As part of the Hanford Environmental Dose Reconstruction (HERD) Project, releases to the Columbia River of 24Na, 32P, 46Sc, 51Cr, 56Mn, 65Zn, 72Ga, 76As, 90Y, 131I, 239Np, and nonvolatile gross beta activity from operation of eight Hanford single-pass production reactors were estimated. Releases of 90Sr, 103Ru, 106Ru, 131I, 144Ce, and 239Pu to the atmosphere from operation of chemical separation facilities were also estimated. These radionuclides and the atmospheric and Columbia River pathways were selected for study because scoping studies showed them to be the largest contributors to dose from Hanford operations. The highest doses resulted from releases to the atmosphere of 131I from chemical separations plants in the pre-1950 period. Prior to 1950, the technology for limiting iodine releases had not been developed. Hence, a very detailed reconstruction of the hourly 131I release history was achieved for 1944-1949 using Monte Carlo methods. Atmospheric releases of the other radionuclides were estimated on a monthly basis for 1944-1972 using deterministic calculations. Monthly releases to the Columbia River for 1944-1971 were based on Monte Carlo methods

  17. Interaction of radionuclides with geomedia associated with the Waste Isolation Pilot Plant (WIPP) site in New Mexico

    A survey of the potential of geological media from the vicinity of the Waste Isolation Pilot Plant site in Southeastern New Mexico for retardation of radionuclide migration in an aqueous carrier was conducted. The survey included the measurement of sorption coefficients (Kd) for twelve radionuclides between three natural water simulants and ten samples from various geological strata. The nuclides included 137Cs, 85Sr, 131I, 99Tc, 125Sb, 144Ce, 152Eu, 153Gd, 106Ru, 243Am, 244Cm, and 238Pu. The compositions of the simulant solutions were those expected of water in contact with potash minerals or halite deposits in the area and in a typical groundwater found in the Delaware Basin. The geological samples were obtained from potential aquifers above and below the proposed repository horizons and from bedded salt deposits in the repository horizons. In brine solutions, Tc and I were not significantly adsorbed by any of the minerals and Cs and Sr showed minimal adsorption (Kd's 103 and Ru and Sb Kd's varied in the range of 25 to > 103. In the groundwater simulant, Tc and I showed the same behavior, but the Kd's of the other nuclides were generally higher. Some initial parametric studies involving pH, trace organic constituents in the simulant solutions, and radionuclide concentrations were carried out. Significant differences in the observed Kd's can result from varying one or more of these solution parameters

  18. Innovative separation method for advanced spent fuel reprocessing based on tertiary pyridine resin

    Radiochemical separation experiments have been performed in order to realize a novel reprocessing method based on chromatography techniques using a novel pyridine resin. The newly synthesized tertiary pyridine resin with two functions of ion exchanger and soft-donor was dedicated to the experiments, where highly irradiated mixed oxide fuel from the experimental fast reactor JOYO was used as a reference spent fuel. With a 3-step separation, pure Am and Cm were individually obtained as minor actinide products, and 106Ru group, lanthanides with 137Cs group and Pu group were fractionated, respectively. The decontamination factor of 137Cs and trivalent lanthanides (155Eu, 144Ce) against the Am product exceeded 3.9 x 104 and 1.0 x 105, respectively. The decontamination factor as the mutual separation of 243Cm was larger than 2.2 x 103 against the Am product. Moreover, the content of 137Cs, trivalent lanthanides and 243Cm in Am product did not exceed 2 ppm. The tertiary pyridine resin method is a candidate separation system for an 'advanced ORIENT process', where enhanced separation, transmutation and utilization of actinides, long-lived fission products and rare metal fission product would be oriented. (author)

  19. Chemical and physical considerations of the use of nuclear fuel spikants for deterrence

    Selle, J. E.

    1978-10-01

    One proposed method of inhibiting the diversion of nuclear fuel for clandestine purposes is to add to the fuel a highly gamma-active material of such intensity that remote handling equipment is necessary in all stages of handling and reprocessing. This is called spiking for deterrence. The present work sought to identify candidate spikants and identify potential materials problems that might occur as the result of incorporation of these spikants with the fuel. Potential spikants were identified and thermodynamic analysis was performed to determine their chemical and physical states. Phase relationships between spikants (and their decay products) and the fuel constituents were surveyed. According to criteria defined in this report, /sup 60/Co, /sup 106/Ru, and /sup 144/Ce appear to have the greatest potential as spikants. Cerium should be present as the oxide, soluble in the fuel, while cobalt and ruthenium should be present in the metallic state with very low solubility in the fuel. Experimental work on the distribution of fission products and their interactions with cladding was also surveyed to provide information on the distribution of spikants in the fuel and describe the probable effects of spikants on the fuel. Cobalt, ruthenium, and cerium should not present any problems due to reaction with stainless steel cladding.

  20. Neutron cross sections of 28 fission product nuclides adopted in JENDL-1

    This is the final report concerning the evaluated neutron cross sections of 28 fission product nuclides adopted in the first version of Japanese Evaluated Nuclear Data Library (JENDL-1). These 28 nuclides were selected as being most important for fast reactor calculations, and are 90Sr, 93Zr, 95Mo, 97Mo, 99Tc, 101Ru, 102Ru, 103Rh, 104Ru, 105Pd, 106Ru, 107Pd, 109Ag, 129I, 131Xe, 133Cs, 135Cs, 137Cs, 143Nd, 144Ce, 144Nd, 145Nd, 147Pm, 147Sm, 149Sm, 151Sm, 153Eu and 155Eu. The status of the experimental data was reviewed over the whole energy range. The present evaluation was performed on the basis of the measured data with the aid of theoretical calculations. The optical and statical models were used for evaluation of the smooth cross sections. An improved method was developed in treating the multilevel Breit-Wigner formula for the resonance region. Various physical parameters and the level schemes, adopted in the present work are discussed by comparing with those used in the other evaluations such as ENDF/B-IV, CEA, CNEN-2 and RCN-2. Furthermore, the evaluation method and results are described in detail for each nuclide. The evaluated total, capture and inelastic scattering cross sections are compared with the other evaluated data and some recent measured data. Some problems of the present work are pointed out and ways of their improvement are suggested. (author)

  1. Gamma spectrometrical analyses of annual deposition samples collected in Romania in 1987-1989

    The dynamics of artificial radionuclide concentrations in deposition samples in the years 1987-1989 is presented in this paper. High resolution gamma spectrometrical analyses have been performed on wet and dry deposition samples from the following stations of the National Environmental Radioactivity Surveillance Network: Cluj-Napoca, Satu-Mare, Constanta, Ceahlau-Tosca, lasi and Craiova. In order to determine small concentrations of low level artificial radionuclides (having an appropriate half life) yearly samples obtained by cumulating daily samples were measured. The following gamma emitting radionuclides were identified in these samples: 106Ru, 110mAg, 125Sb, 134Cs, 137Cs, 144Ce. It can be seen that the level of radionuclide activities in deposition samples at any time is dependent on the 'initial' deposition of May 1986. An environmental half life of 137Cs in deposition can be assessed. For a particular case the evolution during 1987-1989 of 137Cs and 7Be specific activities in monthly samples is also presented. (author)

  2. Chernobyl radionuclides in a Black Sea sediment trap.

    Buesseler, K O; Livingston, H D; Honjo, S; Hay, B J; Manganini, S J; Degens, E; Ittekkot, V; Izdar, E; Konuk, T

    The Chernobyl nuclear power station accident released large quantities of vaporized radionuclides, and, to a lesser extent, mechanically released small (less than 1-10 micron) aerosol particles. The total release of radioactivity is estimated to be out of the order of 1-2 x 10(18) Bq (3-5 x 10(7) Ci) not allowing for releases of the xenon and krypton gases. The 137Cs releases of 3.8 x 10(16) Bq from Chernobyl can be compared to 1.3 x 10(18) Bq 137Cs released due to atmospheric nuclear weapons testing. Chernobyl-derived radionuclides can be used as transient tracers to study physical and biogeochemical processes. Initial measurements of fallout Chernobyl radionuclides from a time-series sediment trap at 1,071 m during June-September 1986 in the southern Black Sea are presented. The specific activities of 137Cs, 144Ce and 106Ru in the trap samples (0.5-2, 4-12 and 6-13 Bq g-1) are independent of the particle flux while their relative activities reflect their rates of scavenging in the order Ce greater than Ru greater than Cs. PMID:3670387

  3. Burn-up determination of irradiated uranium oxide by means of direct gama spectrometry and by radiochemical method

    The burn-up of thermal neutrons irradiated U3O8 (natural uranium) samples has been determined by using both direct gamma spectrometry and radiochemical methods and the results obtained were compared. The fission products 144Ce, 103Ru, 106Ru, 137Cs and 95Zr were chosen as burn-up monitors. In order to isolate the radioisotopes chosen as monitors, a radiochemical separation procedure has been established, in which the solvent extraction technique was used to separate cerium, cesium and ruthenium one from the other and all of them from uranium. The separation between zirconium and niobium and of both elements from the other radioisotopes and uranium was accomplished by means of adsorption on a silica-gel column, followed by selective elution of zirconium and of niobium. When use was made of the direct gamma-ray spectrometry method, the radioactivity of each nuclide of interest was measured in presence of all others. For this purpose use was made of gamma-ray spectrometry and of a Ge-Li detector. Comparison of burn-up values obtained by both methods was made by means of Student's 't' test, and this showed that results obtained in each case are statistically equal. (Author)

  4. Experimental study on biokinetics of radionuclides in age groups

    In the aftermath of the Chernobyl accident, it becomes evident that dose coefficients for members of the public are necessary. International Commission on Radiological Protection (ICRP) established a task group of Committee 2 charged with the assessment of dose coefficients as a function of an individual's age. However, little data is available on the biokinetics of radionuclides in juvenile and is a need to develop age-dependent biokinetic models, such as for the gastrointestinal tract. The present paper reviewed an outline on characteristics of biokinetics of radionuclides in juvenile animals focusing on the previous experimental data. The following radionuclides are discussed: 54Mn, 60Co, 65Zn, 75Se, 106Ru, 110mAg, 115Cd, 125Sb, 137Cs, 141Ce, 203Hg and 3H. Generally, intestinal absorption and whole-body retention of radionuclides in Juveniles were higher than that of adult. In the case of sucklings, it is very important to study how radionuclides are transferred through the placenta and milk. The transfer rate of radionuclides through the placenta and milk is dependent on the period of gestation at the time of dosing. The IDES (Internal Dose Estimation System) which is based on the ICRP model was used for dose calculation. We modified the IDES using the biokinetic data which was gained by animal experiment. The IDES is flexible because the absorbed dose can be calculated by substituting arbitrary physical and physiological parameters and also substituting ingested dose coefficients not only for the ICRP Reference Man, but also for Japanese of 1 year old, 5 years old, 10 years old, 15 years old and the adult, respectively. (author)

  5. Biokinetics and dose assessment of radionuclides in juveniles

    In the aftermath of the Chernobyl accident, it becomes evident that dose coefficients for members of the public are necessary. International Commission on Radiological Protection (ICRP) established a task group of Committee 2 charged with the assessment of dose coefficients as a function of an individual's age. However, little data is available on the biokinetics of radionuclides in juvenile and there is a need to develop age-dependent biokinetic models, such as for the gastrointestinal tract. The present paper reviewed an outline on characteristics of biokinetics of radionuclides in juvenile animals focusing on the previous experimental data. The following radionuclides are discussed: 54Mn, 60Co, 65Zn, 75Se, 106Ru, 110mAg, 115mCd, 125Sb, 137Cs, 141Ce, 203Hg and 3H. Generally, intestinal absorption and whole-body retention of radionuclides in juveniles were higher than that of adult. In the case of sucklings, it is very important to study how radionuclides are transferred through the placenta and milk. The transfer rate of radionuclides through the placenta and milk is dependent on the period of gestation at the time of dosing. The IDES(Internal Dose Estimation System) which is based on the ICRP model was used for dose calculation. We modified the IDES using the biokinetic data which was gained animal experiment. The IDES is flexible because the absorbed dose can be calculated by substituting arbitrary physical and physiological parameters and also substituting ingested dose coefficients not only for the ICRP Reference Man, but also for Japanese of 1 year old, 5 years old, 10 years old, 15 years old and the adult, respectively. (author)

  6. Passive gamma analysis of the boiling-water-reactor assemblies

    Vo, D.; Favalli, A.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S.; Trellue, H.; Vaccaro, S.

    2016-09-01

    This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies from a boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden's Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative-Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay (NDA) measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins, (3) estimate the plutonium mass, (4) estimate the decay heat, and (5) determine the reactivity of spent fuel assemblies. The final objective of this project is to quantify the capability of several integrated NDA instruments to meet the aforementioned goals using the combined signatures of neutrons, gamma rays, and heat. This report presents a selection of the measured data and summarizes an analysis of the results. Specifically, trends in the count rates measured for spectral lines from the following isotopes were analyzed as a function of the declared burnup and cooling time: 137Cs, 154Eu, 134Cs, and to a lesser extent, 106Ru and 144Ce. From these measured count rates, predictive algorithms were developed to enable the estimation of the burnup and cooling time. Furthermore, these algorithms were benchmarked on a set of assemblies not included in the standard assemblies set used by this research team.

  7. Status report on LWR spent fuel IAEA leach tests

    Spent light-water-reactor (LWR) fuel with an average burnup of 28,000 MWd/MTU was leach-tested at 250C using a modified version of the International Atomic Energy Agency procedure. Leach rates were determined from tests conducted in five different solutions: deionized water, sodium chloride (NaCl), sodium bicarbonate (NaHCO3), calcium chloride (CaCl2) and Waste Isolation Pilot Plant B brine solutions. Elemental leach rates are reported based on the release of 90Sr + 90Y, 106Ru, 137Cs, 144Ce, 154Eu, /sup 239 + 240/Pu, 244Cm and total uranium. After 467 days of cumulative leaching, the elemental leach rates are highest in deionized water. The elemental leach rates uin the different solutions generally decreased from deionized water to the 0.03M NaCl solution to the WIPP B brine solution to the 0.03M NaHCO3 solution and was a factor of 20 lower in 0.015M CaCl2 solution than in deionized water. The leach rates of spent fuel and borosilicate waste-glass were also compared. In sodium bicarbonate solution, the leach rates of the two waste forms were nearly equal, but the glass was increasingly more resistant than spent fuel in calcium chloride solution, followed by sodium chloride solution, WIPP B brine solution and deionized water. In deionized water the glass, based on the elemental release of plutonium and curium, was 50 to 400 times more leach resistant than spent fuel

  8. Transfer of nuclides from the water phase to the sediments during normal and extraordinary hydrological cycles

    Atucha I and Atucha II nuclear power plants are located on the right margin of the Parana de las Palmas river. This river belongs to the Cuenca del Plata, whose 1982-1983 hydrologic cycle registered the greatest freshets of the century. Works and studies previously fixed had to be altered and investigations were adapted to the possibilities and the particular hydric conditions verified. Considerations on the transfer of nuclides between water and sediments are presented. The floods reduce the water-sediments contact time on the bed of the river. In outer areas, the waters labelled by the nuclear power plant effluent discharge favor the infiltration in alluvial soils, as well as the exchange with the sediments. The investigations carried out for the phase near to the discharge of liquid effluents (related to the critical group) made possible to prove the characteristics of the path of the liquid wastes released, the distribution coefficient and the fixation or penetrability of some nuclides in soils of the floody valley. In this manner, a balance of radioactive nuclides incorporated to soils and sediments from the neighbourhood of Atucha and the water-course of Parana de las Palmas river is obtained. The presence of 60Co and 137Cs in the floody soils on the right margin of this river was detected and measured during the greatest flood of the century. On the other hand, 144Ce, 51Cr, 106Ru and 90Sr have not been detected. The detection of artificial radioisotopes turns out to be impossible in normal hydrological years, even in the sorroundings of the nuclear power plant or the critical group (from the point of view of the surface waters, The Fishing Club, 3 km down stream). (M.E.L.)

  9. Estimation of 90Sr activity in reprocessed uranium from the PUREX process

    90Sr estimation in reprocessed uranium was carried out by a series of solvent extraction and carrier precipitation techniques using strontium and lanthanum carriers. Fuming with HClO4 was used to remove 106Ru as RuO4. Three step solvent extraction with 50% tri-n-butyl phosphate in xylene in presence of small amounts of dibutyl phosphate and thenoyl trifluoro acetone was carried out to eliminate uranium, plutonium, thorium and protactinium impurities. Lanthanum oxalate precipitation in acid medium was employed to scavenge the remaining multivalent ions. Strontium was precipitated as strontium oxalate in alkaline pH and 137Cs was removed by washing the precipitate with water. A strontium recovery well above 70% was obtained. Final estimation was carried out by radiometry using end window GM counter after drying the precipitate under an infra red lamp. The same procedure was extended to the estimation of 90Sr in a diluted sample of the actual spent fuel solution. An additional lanthanum oxalate precipitation step was required to remove the entire 144Ce impurity from this sample. This modified procedure was employed in the determination of 90Sr in a number of reprocessed uranium samples and the over all precision of the method was found to be well within ±10%. An additional barium chromate precipitation step was necessary for the analysis of reprocessed uranium samples from high burnup fuels to eliminate trace amounts of short lived 224Ra produced during the decay of 232U and its daughters as they interfere in the estimation of 90Sr. (author)

  10. Determining initial enrichment, burnup, and cooling time of pressurized-water-reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

    Favalli, A.; Vo, D.; Grogan, B.; Jansson, P.; Liljenfeldt, H.; Mozin, V.; Schwalbach, P.; Sjöland, A.; Tobin, S. J.; Trellue, H.; Vaccaro, S.

    2016-06-01

    The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. The NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). One purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity's behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. The results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.

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

    Mokrov, Yury G

    2003-10-01

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

  12. Oceanographic Survey. 3. Radiological survey of marine environment in Ibaraki Prefecture: marine sediment survey

    Radioactivity in marine environment of Ibaraki Prefecture has been monitored since 1965. This report briefly describes the radiological survey data of marine sediments. The concentrations of radionuclides in marine water were determined yearly 4 times for 3H and twice for 54Mn, 60Co, 90Sr, 95Zr, 95Nb, 106Ru, 137Cs and 144Ce. The concentrations of 90Sr, 137Cs and 239+240Pu were hardly changed and those of 90Sr and 137Cs were near the limit of identification. The annual excretion of radionuclides from major nuclear plants in Ibaraki Prefecture including JAERI (Tokai and Oarai), Japan Atomic Power Co., etc. were determined for 3H, 14C, 90Sr, 137Cs, 60Co, 129I and 239+240Pu. Based on the results, dose equivalent for the intake of marine animals and algae was estimated to be as low as 0-4.4 μSv. This level was extremely lower than the limit of annual dose equivalent; 1000 μSv and it was kept nearly constant if the operators of those facilities were not discontinued for a long. To elucidate the factors related to the transfer of radionuclides into marine sediments, the depth dose distribution in marine sediments were investigated as well as the relation between radionuclide level and granular size. An elevation of 137Cs level was found for the sediments composed of fine granules, which were rich in the sediments of offshore region. The 239+240Pu level was positively correlated to the content of organic compounds in the sea. (M.N.)

  13. Forage: A sensitive indicator for airborne radioactivity

    As a part of the radiological environmental monitoring program at the Joseph M. Parley Nuclear Plant to meet the requirements of NRC Regulations 10 CRF 50, Appendix I, routine sampling of forage was implemented. Indicator plots of forage (grass) were established at the plant site boundary in the two Meteorological sectors having the highest X/Q values for ground-level dispersion of airborne radioactivity. Likewise, a control plot was established in a sector having a significantly lower X/Q value at a distance of 18 miles. Procedures for maintenance of the grass plots, sampling of forage, and sample preparation for measurement of gamma radioactivity with a Ge (Li) detector were developed during the reported three year measurement period. Three atmospheric nuclear tests by the Peoples Republic of China in 1976 and 1977 has proven forage sampling to be convenient, sensitive, and in the judgement of the authors gives results which are superior to most other media sampled for airborne radioactivity. Typical measured levels of radioactivity from 150 to greater than 10,000 pCi/kg (dry weight) were obtained for the principal fission products in the Chinese bomb fallout, which included 95Zr-95Nb, 103Ru, 131I, 140Ba-140La, 141Ce, and 144Ce. On a unit weight basis the level of radioactivity measured was consistently higher for forage than for green leafy vegetables. This was attributed to the higher surface area for the forage. For comparison, plots of airborne concentrations for gross beta and particulate gamma emitters are shown during the time periods that include the Chinese nuclear tests. (author)

  14. Revascularization of calvarial, mandibular, tibial, and iliac bone grafts in rats

    Pinholt, E M; Solheim, E; Talsnes, O;

    1994-01-01

    area of harvest of bone graft is important regarding early revascularization, but the results do not support the theory that different embryological mode of development is the cause since mandibula (high 141Ce index) and calvaria (low 141Ce index) are of membranous origin and iliac bone (high 141Ce...... index) and tibia (low 141Ce index) are of endochondral origin. The difference in revascularization between the different grafts may be explained by differences in quantity of cancellous bone since cancellous bone is revascularized faster than cortical bone....

  15. Assessment of doses to biota in the river system

    Doses to aquatic biota in the hydrological system Techa - Ob are estimated.The following water bodies with different levels of radioactive contamination are considered: industrial reservoirs, Techa, Iset, Tobol and Irtysh Rivers. Doses to biota are calculated using the observed data on the content of radionuclides in various environmental components, with consideration for geometric characteristics of the organisms and the exposure sources. The following groups of the river biota are considered: aquatic plants, mollusks and fish. Simplified geometric models (ellipsoids) are used in the internal dose calculations for fish and mollusks. Aquatic plants are approximated either with spheres or with a layer of finite depth. For the external doses assessment the water was considered as an infinite source with the uniform distribution of radionuclides. Sediments were represented as a source with the uniformly distributed activity. Concentration factor of scattered radiation was taken into account for gamma emitters. Sources and levels of radioactive contamination of the Techa - Ob system are analyzed. Data on the activity concentration of radionuclides in water, bottom sediments and aquatic biota are used for the dose assessment. Assessment of doses to biota in the Techa -Ob river system in the period from 1949 to the present time are performed.The highest doses (over 0.01 Gy/day) were received by aquatic organisms in the upper reaches of the Techa River in the period of maximum discharges of radionuclides (1950-1951). In that period, a major contribution to the dose to aquatic organisms was due to the incorporated radionuclides: 89 Sr, 90 Sr, 106 Ru,137 Cs, 144 Ce and others. During 1950-1951, the doses to aquatic organisms were estimated, on average, at 0.003-0.1 Gy/day. After the cessation of intensive radioactive discharges and the construction of a system of protective water bodies, the doses to aquatic biota noticeably decreased. Current levels of exposure to fish in

  16. Solid phase extraction of actinides using polymeric beads impregnated with TODGA

    137Cs is one of the major radionuclides contributing to the activity of the high level waste (HLW) and its separation facilitates the safe disposal of the latter in deep geological repository as vitrified mass. The global inventory of 137Cs was estimated to be around 3.7x1014 kBq in 2010. Due to its long half-life and reasonable gamma energy (661 keV), 137Cs it has potential application as a radiation source in gamma irradiators in the environmental pollution control, food preservation and sterilization of medical accessories. It is, therefore, required to develop efficient separation methods for its recovery from HLW. We have recently reported that solvent system containing calix(4)arene-crown-6 ligands in FS-13 have yielded much improved extraction of radio-cesium as compared to analogous solvent systems containing nitrobenzene as the diluents. Our studies involving four different calix-bis-crown-6 and calix-mono-crown-6 ligands have indicated that calix(4)arene-dibenzo-bis-crown-6 (CBC) ligands were better suited due to more favourable extraction of Cs(I) and radiolytic stability of the ligand. In the present study, we have tried use the developed solvent system for the recovery of radio-cesium (137Cs and 134Cs) from actual high level waste (HLW). The HLW, containing a total activity of 100 Ci/L also contained 3.85 g/L U and 7.09 mg/L Pu which were removed by contacting the waste solution twice with 30% TBP in n-dodecane in a hot-cell facility. The raffinate from the TBP extraction step contained negligible amounts of the actinides and was subsequently contacted four times with 1.0x10-3 M CBC in FS-13 (each time with fresh organic phase) in the hot-cell facility and the extraction results indicated 137Cs to remain in the raffinate out of 15.88 Ci/L suggesting ∼ 97% extraction in 4 stages. Quantitative extraction can be done by increasing the number of stages. It was interesting to note that none of the other radionuclides, such as 144Ce, 106Ru, 95Zr, 95Nb, 90Y

  17. Reconstruction of radionuclide contamination of the Techa River caused by liquid waste discharge from radiochemical production at the Mayak Production Association

    , rather than relying on a more uncertain reconstruction of quantities released at the point of discharge. Radionuclides considered include 90Sr, 106Ru, 137Cs, and 144Ce. Estimated concentrations of selected radionuclides at various times are presented

  18. Reconstruction of radionuclide contamination of the Techa River caused by liquid waste discharge from radiochemical production at the Mayak Production Association

    Mokrov, Y.; Glagolenko, Y.; Napier, B.

    2000-07-01

    river, rather than relying on a more uncertain reconstruction of quantities released at the point of discharge. Radionuclides considered include {sup 90}Sr, {sup 106}Ru, {sup 137}Cs, and {sup 144}Ce. Estimated concentrations of selected radionuclides at various times are presented.

  19. Reconstruction of radionuclide contamination of the Techa River caused by liquid waste discharge from radiochemical production at the Mayak Production Association.

    Mokrov, Y; Glagolenko, Y; Napier, B

    2000-07-01

    than relying on a more uncertain reconstruction of quantities released at the point of discharge. Radionuclides considered include 90Sr, 106Ru, 137Cs, and 144Ce. Estimated concentrations of selected radionuclides at various times are presented. PMID:10855774

  20. Results For The Third Quarter 2009 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminant Results

    This report details the chemical and radionuclide contaminant results for the characterization of the 2009 Third Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC). Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. Recently, a review of the radionuclide inventory in Saltstone Vaults 1 and 4 identified several additional radionuclides, not currently in the WAC, which require quantification (40K, 108mAg, 133Ba, 207Bi, 227Ac, 228Ra, 228Th, 231Pa, 247Cm, 249Cf, 251Cf). In addition, several of the radionuclides previously reported with minimum detection limits below the requirements listed in the WAC required analysis with reduced detection limits to support future inventory reporting requirements (22Na, 26Al, 59Ni, 94Nb, 106Ru, 144Ce, 152Eu, 155Eu, 226Ra). This added scope was formally requested in a revision to the standing Technical Task Request for CY2009 Saltstone support and is further discussed in several supporting documents. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants are less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for 59Ni, 94Nb, 247Cm, and 249Cf are above the limits requested by LWO; however, they are below the achievable limits established by Analytical Development (AD). (3) The reported detection limit of isopropanol is lower than its WAC Limit for accident analysis in Appendix 8.1, but higher than its WAC concentration given in Table 4 for vault flammability. The higher detection limit is expected based on current analytical capabilities and is documented in the Task

  1. 106Ruthenium Brachytherapy for Retinoblastoma

    Purpose: To evaluate the efficacy of 106Ru plaque brachytherapy for the treatment of retinoblastoma. Methods and Materials: We reviewed a retrospective, noncomparative case series of 39 children with retinoblastoma treated with 106Ru plaques at the Jules-Gonin Eye Hospital between October 1992 and July 2006, with 12 months of follow-up. Results: A total of 63 tumors were treated with 106Ru brachytherapy in 41 eyes. The median patient age was 27 months. 106Ru brachytherapy was the first-line treatment for 3 tumors (4.8%), second-line treatment for 13 (20.6%), and salvage treatment for 47 tumors (74.6%) resistant to other treatment modalities. Overall tumor control was achieved in 73% at 1 year. Tumor recurrence at 12 months was observed in 2 (12.5%) of 16 tumors for which 106Ru brachytherapy was used as the first- or second-line treatment and in 15 (31.9%) of 47 tumors for which 106Ru brachytherapy was used as salvage treatment. Eye retention was achieved in 76% of cases (31 of 41 eyes). Univariate and multivariate analyses revealed no statistically significant risk factors for tumor recurrence. Radiation complications included retinal detachment in 7 (17.1%), proliferative retinopathy in 1 (2.4%), and subcapsular cataract in 4 (9.7%) of 41 eyes. Conclusion: 106Ru brachytherapy is an effective treatment for retinoblastoma, with few secondary complications. Local vitreous seeding can be successfully treated with 106Ru brachytherapy

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

    The biological effects of inhaled β-emitting radionuclides, 90Y, 91Y, 144Ce and 90Sr, are being investigated in beagle dogs that received single acute exposures at 12 to 14 months of age. The aerosols studied have included 91YC13,144CeC13, 90SrC12, and 90Y, 91Y, 144Ce or 90Sr in aluminosilicate particles. Thus, 91YCl3, 144CeCl3 and the aluminosilicate containing radionuclide particles all resulted in significant exposures to lung; 91YC13, 144CeC13 an 90SrC12 resulted in significant exposures to bone; 91YC13 and 144 CeC13 resulted in significant exposures to liver. The higher initial doserate exposures have been more effective than low dose-rate exposures on a per-rad basis in producing early effects. To date (144CeO2, it was observed that, on a μCi initial lung burden per kilogram body weight basis, mice did not develop pulmonary tumours whereas beagle dogs did. To fid out the reason for this observation mice have been repeatedly exposed by inhalation to 144CeO2 to maintain lung burdens of 144Ce that resulted in radiation dose rates similar to that observed in beagle dogs. Several of the repeatedly exposed mice developed malignant pulmonary tumours. Thus, with similar dose rates and cumulative doses to the lung, mice and dogs responded in a similar manner to chronic β radiation

  3. Separation and recovery of ruthenium from radioactive liquid waste for specific medical applications - wealth from waste

    In recent past, 106Ru has emerged as one of the promising β- emitting radionuclide used in brachytherapy for the treatment of choroidal melanoma and retinoblastoma due to its favorable nuclear decay characteristics. A plaque with low amount of 106Ru activity of the order of 12 - 26 MBq (0.3 - 0.7 mCi ) is suitable for the above treatment and can be used for an adequate duration of 1-2 years due to suitable half-life (T1/2 = 1.02 y). In order to undertake the preparation of 106Ru plaque, an indigenous availability of this radionuclide with acceptable purity was explored from radioactive liquid waste having wide spectrum of fission products in line with wealth from waste strategy. Process methodology has been developed and standardized at Process Control Laboratory of Waste Immobilization Plant (WIP), Trombay for separation of 106Ru from radioactive liquid waste for intended medical application. (author)

  4. Accumulation of transuranic elements in the aquatic biota of the Belarusian sector of contaminated area near the Chernobyl nuclear power plant - Accumulation of transuranic elements in aquatic biota of Belarusian sector of contaminated area of Chernobyl nuclear power plant

    Golubev, Alexander; Mironov, Vladislav [International Sakharov Environmental University. Box 220070, 23 Dolgobrodskaya Street, Minsk, 220070 (Belarus)

    2014-07-01

    The evolution of nuclear contamination of Belarus territory after Chernobyl accident includes the four stages: 1. Iodine-neptunium stage, caused mainly by short-lived radionuclides {sup 131}I, {sup 239}Np and others with a half-life period of several weeks; II. Intermediate stage, caused by radionuclides with a half-life period of a year ({sup 144}Ce, {sup 106}Ru, {sup 134}Cs, etc.); III. Strontium-cesium stage, caused by {sup 90}Sr and {sup 137}Cs with a half-life period of about 30 years; IV. Plutonium-americium, caused by long-lived α-emitting radionuclides {sup 241}Am (period of half-life of 432 years) and {sup 239+240}Pu, having high radio and chemo-toxicity. According to forecasts, activity of {sup 241}Am to 2050 year will increase by 2.5 times and it will be the most important dose-related factor for the aquatic biota within the Chernobyl accident zone. In 2002 - 2008 years we have studied the accumulation of trans-uranic elements (TUE, {sup 241}Am, {sup 239+240}Pu) in basic components of water body ecosystems within the Chernobyl zone - non-flowing Perstok Lake, weak-flowing Borschevka flooding and small Braginka River. Among investigated components are water, bottom sediments, submerged macrophytes (Ceratophyllum submersum, Hydrocharis morsus-ranae, Lemna minor, Nuphar lutea, Stratiotes aloides), emergent macrophytes (Typha spp.), shellfish and fish. In the soil cover in the vicinity of the Perstok Lake activity of {sup 241}Am at present is equivalent to 300 - 600 Bq.kg{sup -1}, that is the basic source of its income to the lake. Radionuclides mobility in the water environment is higher than in the soil, that facilitates the rapid incorporation of {sup 241}Am to the trophic nets of water bodies and its removal by near-water animals in the terrestrial biotopes, including outside Chernobyl zone. Thus, the activity of {sup 241}Am in bottom sediments in the Perstok Lake and Borschevka flooding in 2008 year reach respectively 324 and 131 Bq.kg{sup -1}, and the

  5. Accumulation of transuranic elements in the aquatic biota of the Belarusian sector of contaminated area near the Chernobyl nuclear power plant - Accumulation of transuranic elements in aquatic biota of Belarusian sector of contaminated area of Chernobyl nuclear power plant

    The evolution of nuclear contamination of Belarus territory after Chernobyl accident includes the four stages: 1. Iodine-neptunium stage, caused mainly by short-lived radionuclides 131I, 239Np and others with a half-life period of several weeks; II. Intermediate stage, caused by radionuclides with a half-life period of a year (144Ce, 106Ru, 134Cs, etc.); III. Strontium-cesium stage, caused by 90Sr and 137Cs with a half-life period of about 30 years; IV. Plutonium-americium, caused by long-lived α-emitting radionuclides 241Am (period of half-life of 432 years) and 239+240Pu, having high radio and chemo-toxicity. According to forecasts, activity of 241Am to 2050 year will increase by 2.5 times and it will be the most important dose-related factor for the aquatic biota within the Chernobyl accident zone. In 2002 - 2008 years we have studied the accumulation of trans-uranic elements (TUE, 241Am, 239+240Pu) in basic components of water body ecosystems within the Chernobyl zone - non-flowing Perstok Lake, weak-flowing Borschevka flooding and small Braginka River. Among investigated components are water, bottom sediments, submerged macrophytes (Ceratophyllum submersum, Hydrocharis morsus-ranae, Lemna minor, Nuphar lutea, Stratiotes aloides), emergent macrophytes (Typha spp.), shellfish and fish. In the soil cover in the vicinity of the Perstok Lake activity of 241Am at present is equivalent to 300 - 600 Bq.kg-1, that is the basic source of its income to the lake. Radionuclides mobility in the water environment is higher than in the soil, that facilitates the rapid incorporation of 241Am to the trophic nets of water bodies and its removal by near-water animals in the terrestrial biotopes, including outside Chernobyl zone. Thus, the activity of 241Am in bottom sediments in the Perstok Lake and Borschevka flooding in 2008 year reach respectively 324 and 131 Bq.kg-1, and the activity of 241Am in macrophytes of the Perstok Lake at the same year was 1,0 - 3,7 Bq.kg-1. In

  6. Patterns of Cs-137 and Sr-90 distribution in conjugated landscape systems

    Korobova, E.

    2012-04-01

    The main goal of the study was to reveal spatial patterns of 137Cs and 90Sr distribution in soils and plants of conjugated landscapes and to use 137Cs as a tracer for natural migration and accumulation processes in the environment. The studies were based on presumptions that: 1) the environment consisted of interrelated bio- and geochemical fields of hierarchical structure depending on the level and age of factors responsible for spatial distribution of chemical elements; 2)distribution of technogenic radionuclides in natural landscapes depended upon the location and type of the initial source and radionuclide involvement in natural pathways controlled by the state and mobility of the typomorphic elements and water migration. Case studies were undertaken in areas subjected to contamination after the Chernobyl accident and in the estuary zones of the Yenisey and Pechora rivers. First observations in the Chernobyl remote zone in 1987-1989 demonstrated relation between the dose rate, 137Cs, 134Cs, 144Ce, 106Ru, 125Sb in soil cover and the location of the measured plot in landscape toposequence. Later study of 137Cs and 90Sr concentration and speciation confirmed different patterns of their distribution dependent upon the radioisotope, soil features and vegetation cover corresponding to the local landscape and landuse structure. Certain patterns in distribution and migration of 137Cs and 90Sr in soils and local food chain were followed in private farms situated in different landscape position [1]. Detailed study of 137Cs activity in forested site with a pronounced relief 20 and 25 years after the Chernobyl accident showed its stable polycentric structure in soils, mosses and litter which was sensitive to meso- and micro-relief features [2]. Radionuclide contamination of the lower Yenisey and Pechora studied along meridian landscape transects proved both areas be subjected to global 137Cs pollution while the Yenisey floodplain received additional regional contamination

  7. Langzeitergebnisse bei Aderhautmelanom nach 106Ruthenium-Brachytherapie

    Krause, Nona

    2015-01-01

    Introduction: 106Ruthenium-brachytherapy (106Ru-brachytherapy) is an established therapy for small and medium-sized uveal melanomas. The aim of this study was to examine the long-time results in regard to recurrence rate, complication rate, ocular preservation, metastasis rate and survival with malignant uveal and ciliary body melanoma, as well as relevant prognosis factors, subsequent to 106Ru-brachytherapy. Methodology: In this retrospective study of all cases with uveal or with ciliary ...

  8. Nasal carcinomas in beagle dogs after inhalatioon of relatively soluble forms of beta-emitting radionuclides

    Beagle dogs were exposed by inhalation to relatively soluble forms of three beta-emitting radionuclides and are being held for life span observation to evaluate hazards associated with nuclear power production. Dogs were exposed to graded activity levels of 91YCl3, 144CeCl3 or 90SrCl2. With 91YCl3 and 144CeCl3, significant radiation dose was delivered to liver, respiratory tract, and skeleton. With 90SrCl2, the dose was essentially to skeleton. Nasal cavity squamous cell carcinomas have been the most frequent neoplasms in the 91Y and one of the most frequent in the 144Ce study while relatively few have been seen after 90Sr exposure. Also one nasal cavity hemangiosarcoma was seen in the 144Ce study. The 90Sr-exposed dogs have survived longer after exposure and have higher skeletal radiation doses than do the dogs exposed to 91Y or 144Ce. The greater incidence of nasal carcinomas can be explained by the finding of high concentrations of the lanthanides, 91Y and 144Ce, associated with the nasal turbinate epithelium

  9. Effects of the purification techniques applied to industrial wastes on the chemical behaviour of ruthenium 106 in the marine environment. The case of La Hague reprocessing plant releases

    Since nuclear fuel reprocessing started at the La Hague plant in 1966, the efficiency of the purification techniques applied to radioactive wastes has been improved by a factor of 600. The chemical behaviour of 106Ru observed in the liquid releases into the sea and at two coastal sites near the outlet, shows time variations related to the evolution of the reprocessing techniques used. The ''wet chemical method'' based on 106Ru coprecipitation with cobalt sulphide has fulfilled the objectives of environmental protection and the requirements of industrial productivity. As a consequence, 106Ru behaves like the weakly reactive complexes formed during the nitric acid dissolution stage of the process. Since 1989, vitrification of the effluents mainly affected by these complexes and the optimization of the wet method have contributed to the reduction of 106Ru liquid releases into the sea. At the same time, the radionuclide chemical non-reactivity has been attenuated. Measurements of 106Ru activity carried out in the seaweed Fucus serratus show that the availability of nitrosylruthenium in seawater is closely related to hydrolysis of the complexes. Hydrolysis products are the main source of the chemical species available for exchange with the seaweed, its concentration factor being estimated at 500 ± 350. (authors). 26 refs., 10 tabs., 6 figs

  10. Validity of chalk and bentonite application in soil and water on reducing the absorption of ratio-strontium and radio-cerium by crop

    Effects of the chalk and bentonite application in soil and surface water respectively on reducing the absorption of 89Sr and 141Ce by crop (especially in the edible part of crop) were studied by using isotope tracer techniques. The results showed that the specific activity of 89Sr in the ryegrass and Chinese cabbage could be decreased significantly by chalk application in the soil. The reduced ratio of 89Sr absorption of Chinese cabbage and ryegrass reached 77.7% and 35.2% respectively with the chalk application of 20 g/kg soil. The specific activity of 89Sr in ryegrass and Chinese cabbage followed obvious negative linear correlation with the quantity of application chalk in the soil. The specific activity of 141Ce in surface water, chaff and brown rice decreased by application bentonite in the surface water, which led to the lower accumulation of 141Ce in paddy. However, the absorption and accumulation of 141Ce in root and straw could not be changed. The specific activity of 141Ce in soil followed a negative exponential relation with depth of soil profile

  11. Elimination of cerium-144 - physical and biological characteristics

    The decontamination efficiency of the preparation pentacyn (CaNa3-DTPA) with regard to radiocerium was evaluated. Investigated were not only physical parameters (radionuclide kinetics, absorbed doses decrease), but also morphological and biochemical indexes. Four groups of male Wistar rats were treated accordingly with 144Ce; 144Ce + pentacyn; external irrradiation + 144Ce; external irradiation + 144Ce + pentacyn. External gamma irradiation was performed with a dose of 260 cGy, 144Ce (1480 kBq/animal) was introduced intratarcheally 1 h after external irradiation. Pentacyn was administred according to the following scheme, ensuring maximal efficiency and minimal toxicity: intratracheally administration 30 min after radionuclide intake by 0.2 ml and subsequent intraperitoneally applications on days 1, 3, 5, 7, 10 and 17 by 0.5 ml. Determined were the following parameters characterizing the development of fibrous process: the quantity of oxyproline in collagen, the quantity of hexosamine in lung tissues, the changes in dry mass and heart camera index. It was concluded that biological criteria are important component of the decontamination efficiency evaluation

  12. Genetic effects induced by radionuclides in the populations of the chlorella and antimutagenic influence of the vitamins C and B12

    Genetic influence of 90Sr, 137Cs and 144Ce on the chlorella populations has been studied, as well as antimutagenic effect of C and B12 vitamins on the influenced by 90Sr and 144Ce chlorella populations. The radionuclides 90Sr, 137Cs and 144Ce have been determined to increase the number of lethal and mutant cells in the chlorella populations. It has been shown that according to the influence of the number of lethally injured cells the radionuclides under study (within the concentration range 3.7X104 - 3.7X106 Bk/l) may be presented by the sequence 144Ce>137Cs≥90Sr, while according to the influence of the number of mutant cells - by the reverse sequence 90Sr>137Cs≥144Ce. Such different effect of the radionuclides on the chlorella populations may, possibly, be explained by different physical-chemical state of these radionuclides in water medium, their different uptake mechanism in plant cells, and different localization in them. A conclusion is drawn that C and B12 vitamins reduce radiosensitivity of water organisms, especially their lethality. B12 vitamin is stornger a mutagen than vitamin C

  13. Physiological and genetic effects induced in the chlorella culture by radionuclides

    Radionulcides 90Sr. 137Cs and 144Ce suppress chlorella populations in 37-10-6-37X10-4 Bk/e copcentration range; they increase the amount of lethally damaged and mutant cells at that. Investigated radionuclides can be presented in the form of 144Ce > 137Cs > 90Sr series with respect to their effect on the intensity of chlorella population photosynthesis and amount of lethally damaged cells. as well as accumulation levels, and in the form of 90Sr 137Ce > 144Ce series with negative sequence with respect to the effect on cell density, especially on the amount of mutant cells. The inverse relationship betWeen the change of photosynthesis intensity and the amount of lethally damaged cells, as well as betWeen the change of cell density and the maount of mutant cells was observed during radionuclide effect on chlorella populations

  14. Combinative effect of medium physical and chemical factors on the penetration and localization of some radionuclides in water plant cells

    As a result of the experiments, carried out with the charophytes algae Nitellopsis obtusa, gathered from lake Drukshyaj (the North-East part of the Lithuanian SSR) in 1985, it has been determined that the 90Sr, 144Ce and 137Cs radionuclides accumulation by water plant cell constituents (wall, protoplasm, vacuole) is substantially influenced by the water temperature, the chemical substances, which change the water structure, as well as the combinative effect of these factors. An identical character of the changes of the accumulation factors of 90Sr and 137Cs, which are found in the water solutions in an ionic form, and slightly different character in the case of 144Ce, which exists by 85% in the form of colloid particles, have been noted. In the case of 144Ce the influence of the physical as well as chamical factors on the cell walls is felt stronger than on the inner cell membranes

  15. In situ responses of a biological indicator Mytilus edulis L. to the variations of radionuclide discharges from a fuel reprocessing plant

    The introduction of 10 lots of 100kg of mussels in La Hague waters made it possible to investigate the in situ uptake kinetics of 106Ru + 106Rh released by the fuel reprocessing plant of La Hague during 1 year. Equilibrium was reached within 1 - 3 months, whatever the time of introduction and the amounts released. The removal of the mussels labelled at La Hague to a remote aera made it possible to calculate the biological half-life of 106Ru + 106Rh, viz from 16 to 18 days

  16. Separation of radioactive substances by anodic electrolysis

    In experiments on the electrodeposition of radioisotopes on a platinum anode it was observed that the isotopes could be classified into: (1) those whose cations are deposited as oxides; and (2) those whose cations are only adsorbed on the anode. Under given conditions this difference can be used to separate ions of the two groups. In the present paper, experimental details are given of the separation of 144Ce from 140La. The separation of 144Ce from uranium fission products in the presence of uranyl ion is also discussed. (U.K.)

  17. Toxicity studies of inhaled beta-emitting radionuclides: status report

    The influence of total dose and dose rate on the effects of inhaled beta-emitting radionuclides is being studied in laboratory animals. The radionuclides are inhaled either in a relatively soluble form (90SrCl2, 144CeCl3, 91YCl3 or 137CsCl) or in a relatively insoluble form in fused aluminosilicate particles. The organs affected depend on the solubility and chemical characteristics of the radio isotopes. Studies with young adult dogs are complemented with comparable studies in other species (mice, rats and Syrian hamsters), with animals of different ages and with animals repeatedly exposed to 144Ce

  18. Toxicity studies of inhaled beta-emitting radionuclides - status report

    The influence of total dose and dose rate pattern on the effects of inhaled β-emitting radionuclides is being studied in laboratory animals. The inhaled radionuclides were either in a relatively soluble form (90SrCl2, 144CeCl3, 91YCl3, or 137CsCl), or in a relatively insoluble form in fused aluminosilicate particles. The organs affected depend on the solubility and chemical characteristics of the radionuclides. Studies with young adult dogs are complemented by comparable studies in other species (mice, rats, and Syrian hamsters), with animals of different ages and animals repeatedly exposed to 144Ce. 12 references, 2 figures, 2 tables

  19. Assessment of a cerium---praseodymium-144 inhalation case

    A case involving an acute exposure to a 144Ce-144Pr contaminated atmosphere is presented with a discussion of the treatment and evaluation of data collected out to 800 days post intake. Treatment included irrigation of the upper nasal passages with normal saline, nebulization with normal saline mist and DTPA therapy. Assessment of the deposition and the resulting dose commitment was based on in vivo measurements and excretion data. The initial pulmonary burden, which cleared with three distinct half times, was estimated at 2.1 μCi of 144Ce

  20. Assessment of a cerium-praseodymium-144 inhalation case

    A case involving an acute exposure to a 144Ce-144Pr-contaminated atmosphere is presented with a discussion of the treatment and evaluation of data collected up to 800 days post-intake. Treatment included irrigation of the upper nasal passages with normal saline, nebulization with normal saline mist, and intravenous DTPA therapy. Assessment of the deposition and the resulting dose commitment was based on in vivo measurements and excretion data. The initial pulmonary burden, which cleared with three distinct half-times, was estimated at 2.1 μCi of 144Ce. (author)

  1. Influences of marine sediment on the accumulation of radionuclides by green alga (Ulva pertusa)

    Distribution of radionuclides (60Co, 137Cs, 95Zr-95Nb and 106Ru-106Rh) among green alga (Ulva pertusa), sea water and marine sediment were examined by radioisotope tracer experiment in order to estimate the influence of sediment on the accumulation of radionuclides by the alga. By the application of the compartment model to the experimental results, exponential formulas of distributions were obtained. Through comparison of the transfer coefficients of radionuclides calculated from the exponential formulas, the influence of the sediment on the accumulation of the radionuclides by the green alga was determined to be the largest for 60Co, followed by 95Zr-95Nb, 106Ru-106Rh and 137Cs in this order. The activity ratios of 95Zr-95Nb and 106Ru-106Rh calculated from the transfer coefficients are larger for the alga than for the sediment, inversely those of 60Co and 137Cs show higher values for the sediment than for the alga. Especially, in the case of 60Co, the activity ratio for the sediment is approximately 20 times greater than that for the alga. Biological half lives in green alga estimated from the transfer coefficients were 10 days for 60Co, 7 days for 137Cs, 26 days for 95Zr-95Nb and 24 days for 106Ru-106Rh. (auth.)

  2. Impacts in groundwater of effluents arising in the nuclear industry

    The following topics are discussed: modes of entry of radioactive wastes into groundwater; movement of radionuclides in the ground; degradation processes; behavior of tritium, 90Sr, 137Cs, 106Ru and transuranic elements; potential pathways to man; and impact of releases of radioactive materials to the ground compared to radiation protection standards. (U.S.)

  3. Comparison of influences of sediments and sea water on accumulation of radionuclides by worms

    The accumulation and excretion of radionuclides by marine polychaete worms (Nereis japonica) were examined to learn the influence of contaminated sediments on the contamination of marine organisms. The concentration factors of 60Co, 95Zr-95Nb, 106Ru-106Rh and 137Cs for unfed worms were 6, 4, 6 and 6 respectively, and they were similar to the concentration factors for unfed worms. The biological half lives of 60Co, 95Zr-95Nb and 106Ru-106Rh for fed worms were similar to each other (37, 32 and 35 days, respectively) except that of 137Cs (6 days), and all of them were a little shorter than those for unfed worms. The transfer ratios of radionuclides from sediments to worms were 5 per cent for 60Co, 0.9 for 95Zr-95Nb, 0.6 for 106Ru-106Rh and 17.9 for 137Cs in cpm/g in regard to initial activity in sediments. These figures were compared with the concentration factors to estimate the influence of sediments on the contamination of marine organisms. The obtained figures, which we call the biological factor of the sediments, were 120, 440, 1000 and 30 for 60Co, 95Zr-95Nb, 106Ru-106Rh and 137Cs, respectively. (auth.)

  4. The relationship between revascularisation and osteogenesis in fresh or demineralised bone grafts

    Solheim, E; Pinholt, E M; Talsnes, O;

    2001-01-01

    Bone formation generally depends on adequate blood flow. Failure of bone grafts has been attributed to delayed revascularisation of the graft. We compared the relationship between revascularisation and osteogenesis, evaluated as entrapment of (141)Ce-labelled microspheres and uptake of (85)Sr, re...

  5. Revascularisation of fresh compared with demineralised bone grafts in rats

    Solheim, E; Pinholt, E M; Talsnes, O;

    2001-01-01

    Revascularisation of bone grafts is influenced by both the anatomical origin and the pre-implantation processing of the graft. We investigated the revascularisation by entrapment of 141Ce (cerium)-labelled microspheres in large, fresh and demineralised syngeneic grafts of predominantly cancellous...

  6. Comparison of the effects of inhaled alpha- and beta-emitting radionuclides on pulmonary function in the dog

    Alterations of pulmonary function in representative groups of dogs developing nonneoplastic lung disease, after single inhalation exposures to cerium-144 or plutonium-238 in relatively insoluble particulate forms, were compared. The inhaled particles had similar aerodynamic diameters and effective half-lives of retention in the lung. The mean initial lung burdens of the 144Ce- and 238Pu-exposed groups were 51 and 0.65 μCi/kg of body weight, respectively. Because of the respective ranges of the beta emissions from 144Ce and the alpha emissions from 238Pu, the lungs of the 144Ce-exposed dogs were relatively uniformly irradiated, whereas only approximately 6% of the lung tissue of rates to the 238Pu-exposed dogs was irradiated. The calculated average dose rates to the irradiated tissue were similar for both radionuclides. Pulmonary function was measured serially without sedation. Both groups developed progressive, restrictive lung disease, which ended in death from pulmonary failure. Dogs that inhaled 144Ce had an early reduction of CO diffusing capacity followed by a progressive mechanical and gas-exchange impairment similar to that reported for dogs and men exposed to external irradiation. Dogs that inhaled 238Pu had increased respiratory frequencies which often persisted for months before mechanical and gas-exchange abnormalities became evident

  7. Separation of cerium from high level waste solution of Purex origin

    A simple solvent extraction procedure for the separation of 144Ce from Purex high level waste (HLW) is described. 2-ethylhexyl 2-ethylhexyl phosphonic acid (KSM-17) has been used as extractant. About 10 mCi of cerium was separated from HLW using this technique. This method is amenable for automation and scale up. (author)

  8. Radiation-induced liver lesions in beagle dogs

    The risk for liver disease from internally deposited beta-emitting radionuclides is unknown because there are no human populations exposed to hepatotropic beta-emitting radionuclides available for study. In this report, we discuss the hepatic lesion in dogs exposed to a beta-emitting radionuclide, 144CeCl3, and held for their life spans

  9. Calculation of beta-ray dose distributions from ophthalmic applicators and comparison with measurements in a model eye

    Dose distributions throughout the eye, from three types of beta-ray ophthalmic applicators, were calculated using the EGS4, ACCEPT 3.0, and other Monte Carlo codes. The applicators were those for which doses were measured in a recent international intercomparison [Med. Phys. 28, 1373 (2001)], planar applicators of 106Ru-106Rh and 90Sr-90Y and a concave 106Ru-106Rh applicator. The main purpose was to compare the results of the various codes with average experimental values. For the planar applicators, calculated and measured doses on the source axis agreed within the experimental errors (106Ru-106Rh and 5 mm for 90Sr-90Y. At greater distances the measured values are larger than those calculated. For the concave 106Ru-106Rh applicator, there was poor agreement among available calculations and only those calculated by ACCEPT 3.0 agreed with measured values. In the past, attempts have been made to derive such dose distributions simply, by integrating the appropriate point-source dose function over the source. Here, we investigated the accuracy of this procedure for encapsulated sources, by comparing such results with values calculated by Monte Carlo. An attempt was made to allow for the effects of the silver source window but no corrections were made for scattering from the source backing. In these circumstances, at 6 mm depth, the difference in the results of the two calculations was 14%-18% for a planar 106Ru-106Rh applicator and up to 30% for the concave applicator. It becomes worse at greater depths. These errors are probably caused mainly by differences between the spectrum of beta particles transmitted by the silver window and those transmitted by a thickness of water having the same attenuation properties

  10. 4. Quarterly progress report, 1982

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 58Co, 60Co, 134Cs, 137Cs, 125Sb, 90Sr, 106Ru, K, 54Mn, U and T). A bibliographic selection is also presented

  11. Separation of valuable fission products from High Level Liquid Waste (HLLW)

    High Level Liquid Waste (HLLW) generated during spent fuel reprocessing (PUREX) is an important source of valuable fission products viz. 137Cs, 90Sr (and its daughter product 90Y), platinum group metals like 106Ru , Pd etc. We present a short overview of the work carried out in our laboratory on the separation of the valuable radionuclides from actual research reactor HLLW employing a host of separation techniques like solvent extraction, precipitation, liquid membrane etc. (author)

  12. Partitions of 4d Transition Metal Nuclei and Related Correlations Using the Core Cluster Model

    Mageed, K E Abd El

    2013-01-01

    In the present work we attempt to study the cluster model in the transition metal region. The spectrum fitting method is studied for the selected nuclei (88,90,92^Sr, 92,94^Zr, 98,100^Mo, 100,102,104, 106^Ru, 108,110^Pd and 112,114,116,118^Cd) with proton number (38 0+), the excitation energies and the product of valence nucleon numbers of the parent nuclei.

  13. 1. Quaterly progress report, 1980

    This quaterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are in tables (7Be, 131I, 137Cs, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  14. Preparation of ruthenium nitrosyl nitrate solutions and the extraction of ruthenium complexes by means of neutral organic phosphorus compounds

    A method is described for the preparation of solutions of nitrosyl nitrate complexes of ruthenium. Ruthenium chloride has been transformed into ruthenium tetroxide which reacted with nitrogen oxides in nitric acid and formed ruthenium nitrosyl nitrate. The solution has been labelled with 106Ru and spectrophotometrically investigated. The extraction behavior of the ruthenium complexes with neutral organic phosphorous compounds has been investigated as a function of the acid and salt concentration of the solution and compared with that of other fission products. (author)

  15. Application of multiple gamma-ray spectrum for analytical chemistry

    Hatsukawa, Yuichi; Hayakawa, Takehito; Shinohara, Noboru; Oshima, Masumi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2000-01-01

    Feasibility of application of the multi-gamma ray spectrum for analytical chemistry was examined. A specimen in which some minor fission products are included was measured at an array of ten germanium detectors with BGO Compton suppressors, GEMINI, and multiple gamma-ray spectra are measured. Even in very strong radiation fields from {sup 137}Cs isotope, some miner contents, {sup 106}Ru, {sup 125}Sb, {sup 144}Pr, {sup 207}Bi were detected by this method. (author)

  16. 2. Quarterly progress report, 1983

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 58Co, 60Co, 134Cs, 137Cs, 90Sr, 106Ru, K, 54Mn, U and T). A bibliographic selection is also presented

  17. 3. Quarterly progress report 1982

    This quarterly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 58Co, 60Co 134Cs, 137Cs, 90Sr, 106Ru, K, 54Mn, U and T). A bibliographic selection is also presented

  18. Acute toxicity of beta-emitting radionuclides that may be released in a reactor accident and ingested

    Suckling, weanling, and adult rats received 106Ru--106Rh by gavage and adult beagle dogs ingested 106Ru--106Rh to determine the toxicity of this high-energy (1.4 MeV av) β-emitting nuclide pair. The LD50's for suckling, weanling, and adult rats were 1.5, 18, and 9.0 mCi/kg, respectively. Adult rats were given 147Pm by gavage to determine if a low-energy (0.06 MeV av) β emitter could also cause death by damaging the bowel. The LD50 of 147Pm in rats was about 5 Ci/kg. The calculated radiation doses absorbed in the target cells at the LD50 level were approximately the same for the two radionuclides (3500 rad), although the doses at the mucosal surface differed widely. The LD50 for 106Ru--106Rh in dogs was about 3.5 mCi/kg. Dosimeters placed beneath the mucosa in dogs indicated that the radiation dose to the target cells that caused death from 106Ru--106Rh was about the same as it was for rats. The signs of intestinal injury, their duration, and the probabilities of tissue repair were much different in the dog than in the rat. The midcolon and lower colon of dogs were usually denuded at focal sites after ingestion of 2.5 to 4.0 mCi/kg, and frequently that damage was irreversible. The fatal consequence of severe mucosal damage was averted in two dogs by colectomy and an ileorectal anastomosis

  19. Effect of tropicamide on ocular blood flow in the rabbit

    Intracardiac injection of 15 microspheres labeled with 85Sr (strontium) and 141Ce (cerium) were used to determine ocular blood flow in seven rabbits before and 25 min after bilateral application of tropicamide to the cornea. By using two different isotopes distinguishable under gammaspectrometry, each animal served as its own control. After administration of two drops of 1% tropicamide, no significant difference in blood flow between treated and untreated eyes was observed

  20. Decontamination of a radioactive process waste water by adsorbing colloid flotation

    As a part of a research programme on the treatment of a radioactive process waste water by foam separation techniques, adsorbing colloid flotation was tested to remove 144Ce, 60Co, 65Zn and 89Sr from the waste water. Potassium oleate was used as the collector, and Fe(III) hydroxide, Al(III) hydroxide or Co(II) hydroxide as the coprecipitant. Under the optimal conditions; removals exceeding 99% could be achieved for 65Zn with any of the tested coprecipitants, for 144Ce with Fe(III) and Co(II) hydroxides and for 60Co with only Co(II) hydroxide. For 89Sr removals > 90% could be achieved with only Fe(III) hydroxide. The adsorbing colloid flotation process was compared with both chemical precipitation and ion exchange, and advantages of adsorbing colloid flotation were enumerated. (author)

  1. Decontamination of radioactive process waste water by adsorbing colloid flotation

    Adsorbing colloid flotation was tested to remove 144Ce, 60Co, 65Zn, and 89Sr from radioactive process waste water. Potassium oleate was used as the collector, and Fe(III) hydroxide, Al(III) hydroxide or Co(II) hydroxide as the coprecipitant. Under optimal conditions, removals exceeding 99% could be achieved for 65Zn with any of the tested coprecipitants, for 144Ce with Fe(III) and Co(II) hydroxides and for 60Co with only Co(II) hydroxide. For 89Sr removals of 90% could be achieved only with Fe(III) hydroxide. The adsorbing colloid flotation process was compared with both chemical precipitation and ion exchange. Advantages of adsorbing colloid flotation are discussed. (author)

  2. Placental transfer of ruthenium in rat and guinea-pig

    Ruthenium-106 in citrate solution was administered intravenously to rat at different stages of pregnancy and to guinea-pig either before conception or in late pregnancy. The results for rat showed that retention in the embryo/foetus measured at 3-5 days after administration increased from about 0.0002% of injected activity per embryo/foetus on day 12 of gestation to about 0.05% at birth. The relative concentrations of 106Ru in embryo/foetus and mother (Cf/Cm ratio) were about 0.1 in each case. Concentrations in the yolk sac on day 12 were about 1% g-1 compared with 0.01% g-1 kin the foetus/ Retention in the guinea-pig foetus in late gestation at 7 days after administration (days 50-57) was about 0.2% injected activity per foetus, corresponding to a Cf/Cm = 0.2. Retention in each foetoplacental unit was 2% of injected 106Ru with 50% in the yolk sac, 35% in the placenta and 10% in the foetus. For administration 4 weeks prior to conception, the level of 106Ru retained in the foetus on day 57 of gestation was two orders of magnitude lower than after short-term administration, with a Cf/Cm about 0.004. (author)

  3. Combining of some trace elements with constituent materials of marine algae

    Two radionuclides (137Cs and 106Ru-106Rh) were extracted from a brown alg a (Eisenta bicyclis) into 5 solvents (Ethyl ethel, 80% Ethyl alcohol, boiled water, 0.2% NaOH and 24% KOH) in different proportions, suggesting that both radionuclides do not combine with fats and pigments, and that 137Cs associates maybe with dextrans and monosaccharides, while, 106Ru-106Rh mainly combines with the cell wall polysaccharides such as alginic acid and fucoidan. In order to obtain information from extracts of algae, gel filtration was carried out on 2 species of algae (Ulva pertusa and Eisenia bicyclis) using Sephadex G-100 and G-25. Gel filtration profile gave only one peak for 137Cs, 2 for 106Ru-106Rh and 125I, and 3 for 60Co corresponding to positions where saccharides of the algae appeared. As the result, it was found that different radionuclides combined with different constituent materials of an alga, to some extent. Gel filtration profiles of 125I were compared with each other among several species of marine algae. They were different from one another among classes of green, brown and red algae, though they were similar in a class. Gel filtration profiles of 125I were also varied between 2 chemical forms of 125I (Na125I and Na125IO3). (J.P.N.)

  4. Development of A phantom for ophthalmic beta source applicator quality control using TL dosimetry

    Barbosa, N. A.; da Rosa, L. A. R.; Braz, D.

    2015-11-01

    Concave eye applicators with 90Sr/90Y and 106Ru/106Rh beta ray sources are usually used in brachytherapy for the treatment of superficial intraocular tumors as uveal melanoma with thickness up to 5 mm. The calculation of the dose delivered to the eye is carried out based on the data present in the beta source calibration certificate. Therefore, it would be interesting to have a system that could evaluate that dose. In this work, an eye phantom to be used with 106Ru/106Rh betatherapy applicators was developed in solid water. This phantom can hold nine micro-cube thermoluminescent (TL) dosimeters, TLD-100. The characteristics of the TL response of the dosimeters, namely reproducibility and individual sensitivity, were determined for a 60Co source. Using Monte Carlo code MCNPX, the dose to a water eye was determined at different depths. Exposing the eye phantom with TL dosimeters to the 106Ru/106Rh applicator, it is possible to assess calibration factors using the dose values obtained by Monte Carlo simulation to each depth. Using mean calibration factors, dose values obtained by TL dosimetry were compared to the data present in the applicators certificate. Mean differences for both applicators were lower than ±10%, maximum value 17% and minimum value 0.08%. Considering that the certificate values present an uncertainty of ±20%, the calibration procedure and the developed phantom are validated and can be applied.

  5. Accumulation and excretion of radionuclides by alga Chara tomentosa

    It has been found in the course of the study of accumulation and excretion of radionuclides by alga chara tomentosa that 55Fe, 60Co, 91Y are accumulated by living and dead components of alga chara tomentosa to a far greater extent and are stronger retained than 90Sr, 137Cs, 144Ce. The main part of the absorbed quantities of all investigated nuclides (80-92%) is fixed on the surface of the plant in the ''cortex'' layer

  6. Radio-isotope converter

    Due to the surface power density required for thermoelectric and thermionic converters, available radioactive sources are surveyed and listed. Curves of specific minimum diameter versus thermal flux density are given. 210Po and 242Cm appear to be suitable for direct thermionic when alpha emitters such as 238Pu and 244Cm are still suitable for thermoelectric conversion. This mode will also work with beta emitters 170Tm, 90Sr, 144Ce and 137Cs. Some thermoelectric radioisotope heated converters are suggested. (authors)

  7. Electrochemical investigation of rare earth amalgams

    Using the method of filtration of heterogeneous samarium amalgams, containing radioactive isotopes sup(144)Ce and sup(152)Eu, it has been shown that cerium is inserted into the solid phase of samarium amalgam, whereas europium does not cocrystallize with samarium. The solubility of praseodymium, neodymium, and gadolinium in mercury has been determined on the basis of the curves current VS time of decomposition of heterogeneous amalgams of these metals

  8. Comparison of the effects of inhaled alpha- and beta-emitting radionuclides on pulmonary function of the dog

    Pulmonary function changes of representative dogs after inhalation of a relatively insoluble form of 144Ce in fused aluminosilicate particles and 238PuO2 were compared. Both radionuclide forms had approximately the same effective half-life, but the 238PuO2 irradiated 11 percent of the lung while the 144Ce irradiated 100 percent. Both groups developed restrictive lung disease progressing to pulmonary failure but the sequence of functional changes differed. The first change in dogs that inhaled 144Ce was a reduced CO diffusing capacity followed later by changes in breathing pattern, lung compliance and alveolar-capillary O2 exchange. The first change in dogs that inhaled 238PuO2 was an increase in respiratory frequency which persisted for several months before nearly simultaneous changes in diffusing capacity, compliance and gas mixing. An impairment in alveolar-capillary O2 exchange occurred later in dogs that inhaled 238PuO2. Functional alterations of both groups in pulmonary failure were similar. The differences in the pattern of functional changes were thought to be related to differences in dose pattern, but the exact relationships are unknown

  9. Pulmonary carcinogenesis and chronic beta irradiation of lung

    Light water nuclear power reactor fuel cycles at various stages contain substantial quantities of β-emitting radionuclides. Thus, in the event of an accident, there is potential for inhalation exposure of man to various types and forms of β-emitting radionuclides. In order to study the biological effects of such potential exposures, a series of life span studies have been initiated in which beagle dogs have been exposed to inhalation to achieve graded lung burdens of a relatively insoluble fused clay form of β-emitting radionuclides. The specific radionuclides, 90Y, 91Y, 144Ce, or 90Sr, were selected on the basis of physical half-life to produce a variety of radiation-dose patterns to the lung. Early effects have been the development of radiation pneumonitis and progressive pulmonary fibrosis. In general, dogs which receive high- and rapidly-declining dose-rate exposure from 90Y or 91Y die earlier and at lower cumulative doses than dogs exposed to 144Ce or 90Sr. By contrast, the incidence of later-occurring malignant lung tumors and the degree of inflammatory response is greater in dogs which received protracted low dose-rate exposure associated with 144Ce and 90Sr. Of particular note is the nature of the lung tumors thus far observed

  10. High voltage deposition of daughter 144Pr on platinum electrode from chlorbenzene solution of cerium 8-hydroxyquinolinate

    The deposition of 144Pr, carrier-free, on platinum electrode, formed by beta-decay of 144Ce which was in the form of cerium tetrakis (8-hydroxyquinolinate) chelate in chlorobenzene, was studied in dependence on time and intensity of the electric field. The amount of 144Pr deposited on the cathode after 20 min at the intensity of electric field 8 kV cm-1 was 14% of its total equilibrium amount in the solution. The proportion of 144Pr formed in the solution as ions was found by extrapolating the experimental relationships to be 23%. This value was similar to that of the break-up of molecular forms under the formation of simple 144Pr ions expected on the basis of the decay scheme of 144Ce and the mechanism of the energy transfer inside the atoms and molecular systems. On the basis of the mobility of cations found (9.6x10-5 cm2kV-1s-1) it was assumed that deposited ions were probably monotypes. The amount of 144Pr deposited on the anode was about 1% and that of 144Ce on both the cathode and the anode (caused by adsorption) was 0.5 to 1%. (author)

  11. Brachytherapy treatment simulation of strontium-90 and ruthenium-106 plaques on small size posterior uveal melanoma using MCNPX code

    Abstracts: Concave eye applicators with 90Sr/90Y and 106Ru/106Rh beta-ray sources are usually used in brachytherapy for the treatment of superficial intraocular tumors as uveal melanoma with thickness up to 5 mm. The aim of this work consisted in using the Monte Carlo code MCNPX to calculate the 3D dose distribution on a mathematical model of the human eye, considering 90Sr/90Y and 160Ru/160Rh beta-ray eye applicators, in order to treat a posterior uveal melanoma with a thickness 3.8 mm from the choroid surface. Mathematical models were developed for the two ophthalmic applicators, CGD produced by BEBIG Company and SIA.6 produced by the Amersham Company, with activities 1 mCi and 4.23 mCi respectively. They have a concave form. These applicators' mathematical models were attached to the eye model and the dose distributions were calculated using the MCNPX ⁎F8 tally. The average doses rates were determined in all regions of the eye model. The *F8 tally results showed that the deposited energy due to the applicator with the radionuclide 106Ru/106Rh is higher in all eye regions, including tumor. However the average dose rate in the tumor region is higher for the applicator with 90Sr/90Y, due to its high activity. Due to the dosimetric characteristics of these applicators, the PDD value for 3 mm water is 73% for the 106Ru/106Rh applicator and 60% for 90Sr/90Y applicator. For a better choice of the applicator type and radionuclide it is important to know the thickness of the tumor and its location. - Highlights: ► 106Ru and 90Sr β applicators were modeled using Monte Carlo code MCNPX. ► Dose distributions were calculated for all eye structures, including a tumor region. ► 106Ru generates higher lens doses than those generated by 90Sr

  12. Brachytherapy treatment simulation of strontium-90 and ruthenium-106 plaques on small size posterior uveal melanoma using MCNPX code

    Barbosa, N. A.; da Rosa, L. A. R.; Facure, A.; Braz, D.

    2014-02-01

    Concave eye applicators with 90Sr/90Y and 106Ru/106Rh beta-ray sources are usually used in brachytherapy for the treatment of superficial intraocular tumors as uveal melanoma with thickness up to 5 mm. The aim of this work consisted in using the Monte Carlo code MCNPX to calculate the 3D dose distribution on a mathematical model of the human eye, considering 90Sr/90Y and 160Ru/160Rh beta-ray eye applicators, in order to treat a posterior uveal melanoma with a thickness 3.8 mm from the choroid surface. Mathematical models were developed for the two ophthalmic applicators, CGD produced by BEBIG Company and SIA.6 produced by the Amersham Company, with activities 1 mCi and 4.23 mCi respectively. They have a concave form. These applicators' mathematical models were attached to the eye model and the dose distributions were calculated using the MCNPX *F8 tally. The average doses rates were determined in all regions of the eye model. The *F8 tally results showed that the deposited energy due to the applicator with the radionuclide 106Ru/106Rh is higher in all eye regions, including tumor. However the average dose rate in the tumor region is higher for the applicator with 90Sr/90Y, due to its high activity. Due to the dosimetric characteristics of these applicators, the PDD value for 3 mm water is 73% for the 106Ru/106Rh applicator and 60% for 90Sr/90Y applicator. For a better choice of the applicator type and radionuclide it is important to know the thickness of the tumor and its location.

  13. 2. Quarterly progress report, 1978

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  14. 1. Quaterly progress report, 1979

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  15. 2. Quarterly progress report, 1977

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  16. Monthly progress report

    This monthly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts (air at ground level, high altitude air), rainwater, surface water, underground water, irrigation water, drinking water, food chain (milk, plants, cattle, fish), sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A monthly bibliographic selection is also presented

  17. Hodoscope module with miniature photomultipliers

    The experimental Scintillation Magnetic Spectrometer (SMS) installation, whose main element is an extended hodoscope system, is being built for the accelerator of the High Energy Laboratory of the Joint Institute for Nuclear Research. The authors describe the scintillation hodoscope of the SMS installation and present the applicable amplitude and time characteristics of several types of miniature photomultipliers (FEU-58, FEU-60, FEU-114-1, FEU-147-1, and R-1635 (Hamamatsu, Japan)), which were obtained with a 106Ru radioactive source and standard plastic scintillators of two types, based on oxazoles in polystyrene and in polymethylmethacrylate

  18. Recovery of nitric acid from simulated acidic high level radioactive waste using pore-filled anion exchange membranes

    Acidic waste is generated at different stages of nuclear fuel cycle. The waste contains minor amounts of actinides (241Am, Pu, Np) along with large number of long-lived radionuclides such as 137Cs, 90Sr, 106Ru etc. Before disposal or storage, the overall activity of the waste needs to be reduced. Along with this, the high amount of acid present in the waste needs to be removed. In this study, DD has been used to recover nitric acid from acidic solutions with compositions similar to radioactive waste using pore-filled anion exchange membranes

  19. PMT signal increase using a wavelength shifting paint

    We report a 1.65 times increase of the PMT signal and a simple procedure of application of a new wavelength shifting (WLS) paint for PMTs with non-UV-transparent windows. Samples of four different WLS paints, made from hydrocarbon polymers and organic fluors, were tested on a 5-in. PMT (ET 9390KB) using Cherenkov radiation produced in fused silica disks by 106Ru electrons on a ‘table-top’ setup. The best performing paint was employed on two different types of 5-in. PMTs (ET 9390KB and XP4572B), installed in atmospheric pressure CO2 gas Cherenkov detectors, and tested using GeV electrons

  20. Review of literature on bioassay methods for estimating radionuclides in urine

    Bioassay methods of certain important radionuclides encountered in the nuclear fuel cycle operations, viz., thorium, uranium, sup(239)Pu, sup(241)Am, sup(90)Sr, sup(99)Tc, sup(106)Ru, sup(137)Cs are reviewed, with special emphasis on urinalysis. Since the preconcentration is an important prerequisite for bioassay, various preconcentration methods are also discussed. Brief account of various instruments both nuclear and analytical used in the bioassay programme is included. The sensitivities of the methods cited in the literature vis-a-vis the derived recording levels indicated in ICRP recommendations are compared. Literature surveyed up to 1990 is tabulated. (author). 96 refs., 1 fig ., 3 tabs

  1. 4. Quarterly progress report, 1978

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  2. New results from an imaging CCD used as a position sensitive detector at standard TV rate and room temperature

    This paper shows new and improved results, with respect to previous work, regarding the use of an area imaging CCD (Fairchild CCD 222 running at standard TV rate and at 296 K) as X-ray and charged particle detector. A more dedicated video processor is used and as a consequence single pixel signals, revealing X-rays from a 55Fe source and β-rays from a 106Ru source, can be processed, on the basis of the dark average response and of the rms noise of each pixel. Tests are reported concerning the correlation of the signals with the dark current pattern and with the low light level illumination. (orig.)

  3. Solidification and storage of Savannah River Plant radioactive waste

    A conceptual process for solidification of SRP aqueous waste into high-integrity, low-leachable forms was developed. The process separates about 99.9 percent of the biological hazard from approximately 97 percent of the waste. The major biological hazard remaining in the residual salt is 106Ru, which has a 369-day half-life. Sludge and zeolite can be solidified into concrete or glass. Cost-risk analyses are being made to determine which of these forms is preferred for SRP waste. Also, studies on other parts of the conceptual process are in progress. (auth)

  4. 2. Quarterly progress report, 1981

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radiosotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  5. Monthly progress report

    This monthly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts(air at ground level, high altitude air), rainwater, surface water, underground water, irrigation water, drinking water, food chain (milk, plants, cattle, fish), sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A monthly bibliographic selection is also presented

  6. Studies on screening of adsorbents for up-take of radioruthenium during vitrification of high-level radioactive waste

    106Ru (T1/2 = 369 days) and 103Ru (T1/2 = 39.3 days) are high specific activity fission products present in different types of nuclear waste generated during the reprocessing of spent nuclear fuel. A major part of it converts into RuO4 vapour during vitrification of high-level waste. Different types of materials like zeolite, perchloric acid treated siliceous brick, stainless steel, polythene, polypropylene, silicone were used as an adsorbent where RuO4 reduced to RuO2 and gets deposited on them which subsequently minimizes the spread of contamination. (author)

  7. Monthly progress report

    This monthly report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts (air at ground level, high altitude air), rainwater, surface water, underground water, irrigation water, drinking water, food chain (milk, plants, cattle, fish), sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 104Rh, 226Ra, 54Mn, U and T). A monthly bibliographic selection is also presented

  8. PMT signal increase using a wavelength shifting paint

    Allada, K; Ou, L; Schmookler, B; Shahinyan, A; Wojtsekhowski, B

    2015-01-01

    We report a 1.65 times increase of the PMT signal and a simple procedure of application of a new wavelength shifting (WLS) paint for PMTs with non-UV-transparent windows. Samples of four different WLS paints, made from hydrocarbon polymers and organic fluors, were tested on a 5-inch PMT (ET 9390KB) using Cherenkov radiation produced in fused silica disks by $^{106}$Ru electrons on a `table-top' setup. The best performing paint was employed on two different types of 5-inch PMTs (ET 9390KB and XP4572B), installed in atmospheric pressure CO$_2$ gas Cherenkov detectors, and tested using GeV electrons.

  9. Report on the intercomparison run IAEA-308 radionuclides in seaweed mixture

    The results of an intercomparison exercise on a sample of mixed seaweeds from the Mediterranean Sea, IAEA-308, designed for the determination of artificial and natural radionuclide levels, are reported. The data from 67 laboratories representing 33 countries have been evaluated. The recommended median values, with confidence intervals, for the most frequently measured radionuclides 106Ru, 110mAg, 134Cs, 137Cs, 238Pu, 239+240Pu, 241Am, 40K, 210Pb and 228Th are given. Refs and tabs

  10. Report on the intercomparison run IAEA-307 radionuclides in sea plant

    The results of an intercomparison exercise on a Mediterranean Sea plant sample, coded as IAEA-307, designed for the determination of artificial and natural radionuclide levels, are reported. This sample was collected along the shore from the vicinity of the Principality of Monaco in October 1986. The data from 66 laboratories representing 31 countries have been evaluated. The most frequently measured radionuclides: 106Ru, 110mAg, 134Cs, 137Cs, 238Pu, 239+240Pu, 241Am, 40K and 226Ra. 10 refs, 38 tabs

  11. Programs and procedures for assessing quality of spectral gamma-ray borehole data for the UGTA

    This report describes the procedures and computer programs used to process spectral gamma-ray borehole logging data in the UGTA (UnderGround Test Area) program at the NTS (Nevada Test Site) to assess data quality. These programs and procedures were used to analyze data from five boreholes in the UGTA program. Development of these computer programs and procedures required considerable effort and the primary purpose of this report is to provide continuity with future activities related to spectral gamma-ray borehole logging in the UGTA program. This is especially important because of the long time interval between cessation of logging in April, 1996 and the next round of activity, which has not yet occurred. This report should also be useful if any quality control issues arise regarding past or forthcoming spectral gamma-ray log analyses. In the characterization work underway at the Nevada Test Site Underground Test Area, the logging contractor, Western Atlas, agreed to identify five artificial nuclides based on their gamma-ray signatures. Those nuclides are 60Co, 106Ru, 125Sb, 134Cs, and 137Cs. In the case of 106Ru, which is not a gamma emitter, any detected gamma rays come from the daughter nuclide 106Rh which has a half-life of 30 s. With such a short half-life, 106Rh can be considered to be in equilibrium with 106Ru under most conditions so the result is the same as if the gamma rays were emitted by the 106Ru. The Western Atlas spectral gamma-ray curve plots from a given borehole present detailed qualitative information on the apparent distribution of natural and artificial nuclides with depth in the borehole. The computer programs and procedures described in this report were used to provide a quality analysis of the contractor's processed data and to work with the contractor to validate and/or refine their existing automatic processing. This was done using a procedure that was developed and tested successfully in earlier work at the NTS; the revised and updated

  12. Deposition of long-lived radionuclides after the Chernobyl accident in the forestal massif of Boreon

    After the reactor accident at Chernobyl, samples of soil, moss, lichen and fern were collected in the forest around the Vesubie valley in the South East fo France and analyzed by low energy photon and gamma spectrometry. Activity concentrations as high as 42.8, 9.4 and 3.8 kBq.m-2 were measured for 137Cs, 134Cs and 106Ru, respectively, in soil, in October 1988. 12Sb and 110mAg were also detected. The contamination was found to be the most important between 1400 and 1700 m altitude. (author) 9 refs.; 5 figs.; 2 tabs

  13. Silica aerogel Cerenkov detectors for particle identification

    We present light yield measurements of silica aerogel Cerenkov detectors with photomultiplier readout, showing the light yield dependence of pure and wavelength-shifter-doped silica aerogel on block size using both cosmic muons and electrons from a 106Ru source. We present studies of fluorescent fibers and single photon avalanche diodes, including measurements of attenuation lengths and emission spectra of fibers versus wavelength and tests with a single photon avalanche diode. We show results of the response of a single photon avalanche diode to different light sources. Finally, we discuss a new readout scheme using avalanche photodiodes

  14. 3. Quarterly progress report, 1981

    This report of the SCPRI exposes an interpretation of the principal results concerning the surveillance of radioactivity in the environment: atmospheric dusts, rainwater, surface water, underground water, irrigation water, drinking water, food chain, sea water around nuclear plant sites and other sites. The activities of various radioisotopes are presented in tables (7Be, 95Zr and 95Nb, 103Ru, 131I, 137Cs, 140Ba and 140La, 90Sr, 106Ru and 106Rh, 226Ra, 54Mn, U and T). A bibliographic selection is also presented

  15. Study of the radfioisotopic composition of rain in 2.05 1986 in Bucharest-Magurele area

    The paper presents the activities of radionuclides in the rain that fell in Bucharest-Magurele area on May 2nd, 1986. The artificial radionuclides measured were: Sr-89, Sr-90, Ru-103, Ru-106, Sb-125, I-131, (I+Te)-132, Cs-134, Cs-137, (Ba+La)-140, Ce-141, Ce-144, originating in the nuclear accident at Chernobyl. The activities of I-131 and Cs-137 were 28700 Bq/m2 and 3610 Bq/m2 respectively. (authors)

  16. Deposition and retention of radioactive aerosols on desert vegetation

    Deposition velocities and retention times were obtained for submicron aerosols of 134Cs and 141Ce on a shrub species (Artemisia tridentata) and a grass (Elymus elimoides) in a natural desert environment. Submicron aerosols of these two nuclides were artificially generated and released over a sagebrush community in southeast Idaho during each of three seasons: spring, summer and winter, to determine the effects of weathering and plant development on aerosol deposition and retention. Information on friction velocities, roughness lengths, and particle size was also obtained

  17. Nuclear Decay Data for the International Reactor Dosimetry Library for Fission and Fusion (IRDFF): Updated Evaluations of the Half-Lives and Gamma Ray Intensities

    Chechev, Valery P.; Kuzmenko, Nikolay K.

    2016-02-01

    Updated evaluations of the half-lives and prominent gamma ray intensities have been presented for 20 radionuclides - dosimetry reaction residuals. The new values of these decay characteristics recommended for the IRDFF library were obtained using the approaches and methodology adopted by the working group of the Decay Data Evaluation Project (DDEP) cooperation. The experimental data published up to 2014 were taken into account in updated evaluations. The list of radionuclides includes 3H, 18F, 22Na, 24Na, 46Sc, 51Cr, 54Mn, 59Fe, 57Co, 60Co, 57Ni, 64Cu, 88Y, 132Te, 131I, 140Ba, 140La, 141Ce, 182Ta, 198Au.

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

    As part of a large research effort to study the lifetime health risks of inhaled radionuclides, Beagle dogs inhaled 90SrCl2 or 144CeCl3 or were injected intravenously with 137CsCl. Because these three compounds were soluble in body fluids, the resulting widely differing patterns of radionuclide distribution and dose reflected tissue affinities of the elements involved. Long-term health effects, predominantly cancers, were seen in the organs receiving the highest doses. Investigations are continuing on the extent to which other less irradiated organs may have also been affected

  19. Radionuclide volatilization during plasmachemical reprocessing of radioactive wastes

    Volatilization of 137Cs, 60Co, 90Sr, 144Ce and α-active radionuclides under high temperature utilization of solid and liquid low- and intermediate level radioactive wastes is studied. Low temperature plasma of arc plasmatroned was used as a heat carrier in the laboratory conditions and on experimental installation with shaft furnace and direct flow plasma-chemical reactor. The lowest radionuclides lost (1-2%) was observed from the shaft furnace due to the presence of radionuclides sorbiting layer of wastes

  20. The dispersion of pollutants in the Romanian rivers Olt, Somes and Danube

    The paper describes the results obtained in three tracer experiments carried out into the Romanian rivers Olt and Somes as well as into the Romanian part of the Danube by using the radioactive tracer 82Br. The possibility of a radioactive discharge to occur from the Cernavoda Nuclear Power Plant bring to focus also knowing of the distribution of fission products between water and solid suspended material. Consequently there were also studied and presented the distribution coefficients of the radionuclides 131I, 99Mo, 144Ce, 137Cs, and 95Zr for clay, loess and the particular alluvium collected from the Danube bed. (author)

  1. Migration studies of radionuclides at the WIPP site

    A study was made of the effects on radionuclide migration from the solid TRU waste of inorganic and organic ligands in brine media. Typical organic waste meterials were exposed to synthetic brine at 700 for up to 1 year. Pure brine and brine/organic waste extracts were used to determine actinide and lathanide (153Gd, 144Ce, 152Eu, 243Am) distribution coefficients K/sub d/ between geological media and the brine. Results show that brine containing extract from plywood, etc. reduces considerably the K/sub d/

  2. Appendix to Health and Safety Laboratory environmental quarterly report. [Fallout radionuclides deposited and in surface air at various world sites; /sup 137/Cs and /sup 90/Sr in milk and drinking water in New York City; and stable Pb in surface air

    Hardy, E.P. Jr.

    1977-07-01

    Tabulated data are presented on the deposition of fallout /sup 89/Sr and /sup 90/Sr at various world land sites through 1976; the ..gamma.. spectra and content of /sup 7/Be, /sup 95/Zr, /sup 137/Cs, /sup 144/Ce, /sup 90/Sr, /sup 210/Pb, /sup 238/Pu, /sup 239/Pu, and stable Pb in samples of surface air collected during 1966 at various world sites; and the content of fallout /sup 137/Cs and /sup 90/Sr in samples of drinking water and milk collected in New York City through 1976. (CH)

  3. Reconstruction of dose on the basis of forest litter activity measurements (case studies)

    In a large scale investigation of Polish forest litter contamination performed in recent years we observed the variety of Chernobyl fallout in Poland. Besides large differences in the radiocaesium contamination levels, we found a non-uniform isotopic composition of the fallout; in the north-eastern part of the country we found enhanced (relative to caesium) amounts of non-volatile radioisotopes. We were still able to detect 144Ce, 154Eu and 155Eu as well as plutonium isotopes of Chernobyl origin. 7 refs

  4. Chelating agents in pharmacology, toxicology and therapeutics

    The proceedings contain 71 abstracts of papers. Fourteen abstracts were inputted in INIS. The topics covered include: the effects of chelating agents on the retention of 63Ni, 109Cd, 203Hg, 144Ce, 95Nb and the excretion of 210Po, 63Ni, 48V, 239Pu, 241Am, 54Mn; the applications of tracer techniques for studies of the efficacy of chelation therapy in patients with heart and brain disorders; and the treatment of metal poisoning with chelating agents. (J.P.)

  5. Separation of 90Sr from PUREX HLLW using N,N,N',N'-tetra (2-ethylhexyl)diglycolamide

    This paper describes the separation of 90Sr from PUREX-HLLW employing separation techniques viz. solvent extraction and precipitation. In the first step, PUREX-HLLW was subjected to solvent extraction using TBP (30% in n-dodecane) to remove residual uranium and plutonium. In the subsequent step the raffinate was treated with N,N,N',N'-tetra (2-ethylhexyl) diglycolamide (TEHDGA, 0.20M in 30% isodecyl alcohol and n-dodecane) for the bulk separation of trivalent actinides and lanthanides. The raffinate from this step containing major activity of 90Sr and other fission products such as 137Cs and 106Ru etc. forms ideal feed for 90Sr recovery. Strontium from this non alpha bearing HLLW was extracted using 0.30M TEHDGA in 5% isodecyl alcohol and n-dodecane and stripped with 0.01M HNO3. Recovery of 90Sr was found to be quantitative which was further purified from trace impurities such as 106Ru etc. and concentrated using radiochemical precipitation technique employing Fe scavenging as hydroxide followed by carbonate precipitation after adding natural Fe and Sr as carriers

  6. Screening of silver nanoparticles containing carbonized yeast cells for adsorption of few long-lived active radionuclides

    The present study involves the screening of silver nanoparticles containing carbonized yeast cells isolated from coconut cell sap for efficient adsorption of few long lived radionuclides like 137Cs55, 60Co27, 106Ru44, 239Pu94 and 241Am95. Yeast cells containing silver nanoparticles produced through biological reduction were subjected to carbonization (400 deg C for 1 h) at atmospheric conditions and their properties were analyzed using fourier transform infra-red spectroscopy, X-ray diffraction, scanning electron microscope attached with energy dispersive spectroscopy and transmission electron microscope. The average size of the silver nanoparticles present on the surface of the carbonized silver containing yeast cells (CSY) was 19 ± 9 nm. The carbonized control yeast cells without silver exposure (CCY) did not contain any particles on its surface. The efficiency of CSY and CCY towards the radionuclide adsorption was studied in batch mode at fixed contact time, concentration, and at its native pH. CSY was efficient in removal of 239Pu94 (76.75%) and 106Ru44 (54.73%) whereas CCY showed efficient removal only for 241Am95 (62.89%). Both the adsorbents did not show any retention with respect to 60Co27 and 137Cs55. Based on the experimental data, decontamination factor and distribution coefficient (Kd) were calculated and, from the values, it was observed that these adsorbents have greater potential to adsorb radionuclides. (author)

  7. Monte Carlo-based Bragg-Gray tissue-to-air mass-collision-stopping power ratios for ISO beta sources

    Quantity of interest in external beta radiation protection is the absorbed dose rate to tissue at a depth of 7 mg/cm2 Dt (7 mg/cm2) in a 4-element ICRU (International Commission for Radiation Units and Measurements) unit density tissue phantom. ISO (International Organization for Standardization) 6980-2 provides guidelines to establish this quantity for beta emitters using an extrapolation chamber as a primary standard. ISO 6980-1 proposes two series of beta reference radiation fields, namely, series 1 and series 2. Series 1 covers 90Sr/90Y, 85Kr, 204Tl and 147Pm sources used with beam flattening filter and Series 2 covers 14C and 106Ru/106Rh sources used with beam flattening filter. Dt (7 mg/cm2) is realized based on measured current and set of corrections including Bragg-Gray tissue-to-air mass-stopping power ratio, (S/ρ)t,a. ISO provides (S/ρ)t,a values which are based on approximate methods. The present study is aimed at calculating (S/ρ)t,a for 90Sr/90Y, 85Kr, 106Ru/106Rh and 147Pm sources using the Monte Carlo (MC) methods and compare the same against the ISO values. By definition, (S/ρ)t,a should be independent of cavity length of the chamber which was verified in the work

  8. Monte Carlo-based Spencer-Attix and Bragg-Gray tissue-to-air stopping power ratios for ISO beta sources

    Spencer-Attix (SA) and Bragg-Gray (BG) mass-collision-stopping-power ratios of tissue-to-air are calculated using a modified version of EGSnrc-based SPRRZnrc user-code for the International Organization for Standardization (ISO) beta sources such as 147Pm, 85Kr, 90Sr/90Y and 106Ru/106Rh. The ratios are calculated at 5 and 70 μm depths along the central axis of the unit density ICRU-4-element tissue phantom as a function of air-cavity lengths of the extrapolation chamber l = 0.025-0.25 cm. The study shows that the BG values are independent of l and agree well with the ISO-reported values for the above sources. The overall variation in the SA values is ∼0.3 % for all the investigated sources, when l is varied from 0.025 to 0.25 cm. As energy of the beta increases the SA stopping-power ratio for a given cavity length decreases. For example, SA values of 147Pm are higher by ∼2 % when compared with the corresponding values of 106Ru/106Rh source. SA stopping-power ratios are higher than the BG stopping-power ratios and the degree of variation depends on type of source and the value of l. For example, the difference is up to 0.7 % at l = 0.025 cm for the 90Sr/90Y source. (authors)

  9. Spatial trends on an ungrazed West Cumbrian saltmarsh of surface contamination by selected radionuclides over a 25 year period.

    Caborn, Jane A; Howard, Brenda J; Blowers, Paul; Wright, Simon M

    2016-01-01

    Long term spatial and temporal variations in radionuclide activity have been measured in a contaminated ungrazed saltmarsh near Ravenglass, Cumbria. Over a twenty-five year period there has been a decrease in activity concentration with (106)Ru and (137)Cs showing the highest rate of change followed by Pu alpha and (241)Am. A number of factors contribute to the reduction with time; including radiological half lives, discharge and remobilisation. For (241)Am the lower reduction rate is partially due to ingrowth from (241)Pu and partially as a result of transport of sediment from the offshore Irish Sea mud patch. Considerable spatial variation for the different radionuclides was observed, which with time became less defined. The highest activity concentrations of long-lived radionuclides were in low energy areas, typically where higher rates of sedimentation and vegetation occurred. The trend was reversed for the shorter lived radionuclide, (106)Ru, with higher activity concentrations observed in high energy areas where there was frequent tidal inundation. Surface scrape samples provide a pragmatic, practical method of measuring sediment contamination over large areas and is a sampling approach adopted by most routine environmental monitoring programs, but it does not allow for interpretation of the effect of variation in sedimentation rates. This paper proposes a method for calculating indicative sedimentation rates across the saltmarsh using surface scrape data, which produces results consistent with values experimentally obtained. PMID:26440699

  10. Radioactive contamination of copper produced using nuclear explosives

    Laboratory tests simulating the processing of copper ore after fracturing with nuclear explosives indicate that only very small fractions of the radioactive fission products will be dissolved on leaching with dilute sulfuric acid. Tritium (as tritiated water) will be by far the dominant radionuclide in the circulating leach liquor, assuming use of a fusion device. Only 106Ru appears of significant importance with respect to contamination of the cement copper. It is rejected effectively in electrolytic purification and, therefore, the final copper product should be very low in radiocontamination and not hazardous to the customer. The activity level may be high enough, however, to make the copper unsuitable for some specific uses. If necessary, solvent extraction can be used as an alternative to the cementation process to reduce the radioactivity of the copper products. The tritium in the circulating liquor and the 106Ru in the cement copper are potential hazards at the plant site and must be given consideration in designing and operating the facility. However since the activity levels will be low, the protection necessary to ensure safety of the operating personnel should be neither difficult nor costly to provide. (author)

  11. Distribution of radionuclides among green alga, marine sediments and sea water

    Distributions of radionuclides among green alga (Ulva pertusa), marine sediment and sea water were examined in laboratory experiments with radioisotope tracers to look into the behavior of the radionuclides released into the coastal sea. Marine sands from the five different seashores along the coast of Japan were used. Distributions of 60Co, 95Zr-95Nb and 106Ru-106Rh in these sands were by far the highest of the three components (marine sand, sea water and marine alga). The distributions of the three radionuclides had not so large fluctuations among the five marine sands and were considered to be rather constant. The total amount found in marine sand and green alga was about 90% for the three radionuclides but about 20% for 137Cs on the average in two weeks after the start of the experiments. The activity ratio of marine sediment (radioactivity in 1 g of sediment/radioactivity in 1 ml of sea water) was 4000 for 60co, 30 for 137Cs, 1800 for 95Zr-95Nb and 900 for 106Ru-106Rh. (auth.)

  12. The impact of Chernobyl fallout on Mytilus sp. collected from the French coast

    The spatial distributions of 103Ru, 106Ru, 110mAg, 134Cs and 13/Cs levels in Mytilus sp. samples gathered from the entire French coast subsequent to the explosion of unit 4 at the Soviet nuclear power plant in Chernobyl are largely in line with those based on aerosol and terrestrial measurements. Thus measurements of this bio-indicator found Channel levels to be lower by a factor of 10 than those observed on the eastern section of the Mediterranean coasts. Areas subject to chronic low-level industrial radioactive discharges, such as the Cotentin shoreline and the Rhone estuary, display a slight increase of 106Ru and 137Cs radioactivity levels. In contrast, contamination is especially clear-cut in areas initially free from radionuclides (i.e. surrounding Nice) where biological removal with time has been characterized and modelized, for both ruthenium isotopic forms, and covering 10 and 94 day biological periods. These data, when compared with those found in the literature, indicate that the memorizing time in the event of an accidental release of ruthenium is shorter than for chronic releases. An assessment of public health implications following the ingestion of mussels labelled solely by Chernobyl fallout is of the same order of magnitude as that of mussels gathered in an area exposed to Rhone industry, i.e. 10-5 of the annual dose limit to the whole body for the public at large

  13. The design and the dosimetry of bi-nuclide radioactive ophthalmic applicators

    A novel type of applicator for the treatment of intra-ocular tumors has been developed, based on the two radionuclides 106Ru/106Rh and 125I. The dose distribution of this ophthalmic plaque combines advantageous features of both radionuclides and can be optimally adapted to a tumor thickness in the range 6.5-9 mm, a size which is beyond the dosimetric limitations of the 106Ru/106Rh plaque therapy. Compared with 125I plaques a bi-nuclide plaque allows to maintain the tumor dosage while the dose in the irradiated volume outside of the target volume is significantly reduced. Consequently, radiosensitive structures within the eye can be spared more effectively. Dedicated methods have been developed for the dosimetry of this plaque. These methods are based on our own extensive dosimetric investigations with plastic scintillators. The precondition was the availability, developed in recent years, of a more accurate determination of the absolute dose rate to water of beta- and low energy emitters

  14. Dosimetry of beta-ray ophthalmic applicators: Comparison of different measurement methods

    An international intercomparison of the dosimetry of three beta particle emitting ophthalmic applicators was performed, which involved measurements with radiochromic film, thermoluminescence dosimeters (TLDs), alanine pellets, plastic scintillators, extrapolation ionization chambers, a small fixed-volume ionization chambers, a diode detector and a diamond detector. The sources studied were planar applicators of 90Sr-90Y and 106Ru-106Rh, and a concave applicator of 106Ru-106Rh. Comparisons were made of absolute dosimetry determined at 1 mm from the source surface in water or water-equivalent plastic, and relative dosimetry along and perpendicular to the source axes. The results of the intercomparison indicate that the various methods yield consistent absolute dosimetry results at the level of 10%-14% (one standard deviation) depending on the source. For relative dosimetry along the source axis at depths of 5 mm or less, the agreement was 3%-9% (one standard deviation) depending on the source and the depth. Crucial to the proper interpretation of the measurement results is an accurate knowledge of the detector geometry, i.e., sensitive volume and amount of insensitive covering material. From the results of these measurements, functions which describe the relative dose rate along and perpendicular to the source axes are suggested

  15. Passage of chromium-mordanted and rare earth-labeled fiber: time of dosing kinetics

    Coastal bermudagrass hay was labeled with Cr by the Cr-mordant procedure and with 177Lu applied to the same fiber. Neutral detergent fiber prepared from the same Coastal bermudagrass hay was labeled with Yb, 169Yb, Tb and 160Tb by soaking overnight following by thorough washing and drying. Wood chips were similarly labeled with Sm or La, and Solka Floc was labeled with 147Nd and 141Ce. The carriers, labels and times of administration to cattle were: bermudagrass fiber with both Cr and 177Lu, bermudagrass fiber with 169Yb and Solka Floc labeled with 147Nd at 0 h; bermudagrass fiber with Yb, Solka Floc with 141Ce and wood chips with Sm at 24 h; wood chips with La at 48 h; and bermudagrass fiber labeled with 160Tb at the beginning and labeled with Tb at the end of a meal. Fecal collection followed and passage characteristics were determined with a two-compartment, age-dependent model. Markers labeling the different fiber sources had different (P less than .01) passage rates (Solka Floc greater than Coastal bermudagrass greater than wood chips), but there was no difference within fiber source for rare earth passage. There also was no difference between the passage characteristics of Cr-mordant and 177Lu. However, passage rate of particles administered at the beginning of the meal (160Tb) was 42% higher than for particles at the end of the meal (Tb)

  16. Hair as an indicator of the body burden of metals in relation to age

    Many factors influencing metal deposition in hair are still unknown. Animal experiments were performed to obtain data on the mechanism of transfer of elements into hair and to estimate whether hair retention is influenced by age, sex and chelating agent treatment. Experiments were performed on albino rats (Wistar strain) of different age and sex. Whole body hair (skin included) and organ retention of various elements was determined at different periods of time after intraperitoneal administration of the radioactive isotopes 115mCd, 203Hg, 54Mn, 59Fe, 65Zn, 141Ce, 137Cs, 203Pb and 85Sr. In some experiments DTPA was used for reducing body retention of 155mCd and 141Ce and DMPS for reducing 203Hg retention. Results show that hair and organ retention of elements in rats varies with age, sex and chelation treatment and such changes are specific for each element and can not be generalized. Age as a factor influencing hair retention of metals is likely to be more important for some elements than for others. In kinetic studies we found that due to differences in element distribution and kinetics, the relationship between hair and organ retention at various time intervals varies both with age and the element concerned. Sex influences not only hair but also metal retention and distribution in other organs. (author). 4 refs

  17. Study of shortening of lifetime and of the occurrence of cancers in situ induced by cerium-144 hydroxide administered locally in various organs

    The authors compare the local action of 144Ce administered to rats in three different ways. Inhalation was chosen with a view to comparing the action of the β-emitter 144Ce with that of α-emitters such as plutonium and americium. Intramuscular injection was used to study the risk incurred through wounds contaminated by fission products, the purpose being to devise a model for the experimental study of osteosarcoma therapy. Oro-facial injection was selected in order to determine the carcinogenic effects of local irradiation in the sinuses and maxillaries. Here, too, it seemed useful to have a reproducible model of facial tumours that could be used for physiopathological and therapeutic studies. Cerium administered in hydroxide form and precipitating on the spot upon contact with living tissue gives local irradiation much greater than the dose delivered to other organs by the very slight fraction that diffuses. For these three modes of application the activities deposited in situ were varied, and for two of the three cases (intramuscular and intrafacial injection) the age of the animals at the moment of contamination was varied, too. The experiments brought out two principal effects: the appearance of local tumours, often cancerous, and a shortening of the animals' lifetime, the degree of the effect in both cases being linked to the dose. The experiments described here suggest that lifetime shortening and the presence of cancers in rats are separate phenomena, apparently independent of each other

  18. Gastrointestinal transit in the pig: measurement using radioactive lanthanides and comparison with sheep

    A technique to characterize the transit time of digesta through the gastrointestinal tract of the sheep has been described by Francois and Compere (1971). In the present paper, the authors present an adaptation of the method to the pig. On the first day of the experiment, each animal was given a diet uniformly labelled with 144Ce as an unabsorbable marker. The feces were collected at 1 or 2-hour intervals at progressively extended periods for the remainder of the collection period. The fecal concentration of the marker rose rapidly to a maximum, then decreased following a simple exponential law. Data were also expressed as a cumulative excretion curve of 144Ce. The mean retention time in the pig digestive tract could be calculated by concentration curves using either the m(t) parameter of Debouche (1974) or the t parameter proposed by Levenspiel (1974) to describe the flow of a fluid in an open vessel. The values obtained were identical to those found by Castle and Castle (1957) for the R parameter. These data are compared to those given by the same technique with the sheep

  19. Deadspace breathing as a screening test for early lung damage

    Breathing through added external deadspace (V/sub Dext/) was found to increase the tidal volume of normal dogs in order to achieve alveolar ventilation adequate for gas exchange. Addition of V/sub Dext/ did not alter alveolar-arterial gas gradients or cardiovascular function. Respiratory patterns during V/sub Dext/ breathing were compared with variables measured during treadmill exercise to investigate deadspace breathing as an indicator of early lung dysfunction caused by radiation pneumonitis in dogs. Dogs were evaluated clinically, radiographically and by pulmonary function tests at rest before and after inhaling 144Ce in fused aluminosilicate particles. By 4 mo after inhalation of 32 to 50 μCi/kg 144Ce, there were increases in respiratory frequency and minute volume during V/sub Dext/ breathing and in minute volume and the ventilatory equivalent for O2 while running. No other significant functional, radiographic or clinical changes were noted. The dogs were sacrificed and scattered foci of inflammation were found in their lungs. Deadspace testing detected early, subclinical lung alterations with a sensitivity and at a time identical to treadmill testing and did not require whole-body exercise or training

  20. Natural sorbents as barriers against migration of radionuclides from radioactive waste repositories

    The sorption properties of Bulgarian inorganic sorbents - clinoptilolite, vermiculite, bentonite, glauconite, celadonite and loess, which can be used as buffer, backfill and sealing materials in radwaste repository are studied. Experimental data about sorption and desorption capacities, radiation and thermal stability of sorbents from different Bulgarian deposits are reported and compared. Clinoptilolite from Beli Plast and its sodium variety from Kostino and Moryantsi is recommended as a barrier against radionuclide migration from radwaste repository due to their high sorption capacity of 137Ce, 90Sr and 60Co. The high selectivity of vermiculite for polyvalent ions (144Ce, 59Fe and 90Sr) gives grounds to include the sorption on vermiculite as a second step in the ion exchange technology for low level laundry waste decontamination. Bentonite is studied as a proposed buffer, backfill and sealing material. Its selectivity for cesium is lower compared to those of clinoptilolite. Thus a tailored-made mixture of bentonite and clinoptilolite will act as a barrier against radionuclides in different oxidation state. Glauconite can be successfully used as a barrier against migration of 144Ce, 90Sr, 54Mn and 65Zn. Loess is also included in the study, as the Kozloduy NPP is sited on loess formation and it is a natural potential site for low and intermediate level waste burial. It is concludes that zeolites and clays of Bulgarian deposits can be used effectively against radionuclide migration from radioactive waste repositories. 59 refs., 5 tabs. (author)

  1. Distribution of fission products in graphite sleeves and blocks of the ninth and tenth OGL-1 fuel assemblies

    Distribution of fission products in graphite sleeves and blocks of the ninth and tenth OGL-1 fuel assemblies was measured by gamma spectrometry with lathe sectioning. The assemblies were loaded with HTGR fuel compacts, which had been produced by a scaled-up facility for the High Temperature Engineering Test Reactor (HTTR) being developed by JAERI; and they were irradiated in an in-pile gas loop, OGL-1. Fission products detected in the sleeves were 137Cs, 134Cs, 155Eu, 154Eu, 144Ce, 125Sb and 110mAg. The last nuclide, however, may have been produced by activation of a stable isotope, 109Ag, contained as impurity. Effective retention capability of the sleeve was observed for 155Eu, 154Eu, 144Ce and 125Sb; while, not for 137Cs and 134Cs. Concentration of 137Cs in the graphite blocks was markedly higher at the downstream side than at the upstream side of the coolant. This was ascribed to migration of the nuclide with the coolant flow and its subsequent sorption on the surface of the block. (author)

  2. Educational laboratory experiments on chemistry in a nuclear engineering school

    An educational laboratory experiment on radiochemistry was investigated by students in the general course of the Nuclear Engineering School of Japan Atomic Energy Research Institute. Most of them are not chemical engineers, but electrical and mechanical engineers. Therefore, the educational experiment was designed for them by introducing a ''word experiment'' in the initial stage and by reducing the chemical procedure as far as possible. It began with calculations on a simple solvent extraction process-the ''word experiment''--followed by the chemical separation of 144Pr from 144Ce with tri-n-butyl phosphate in a nitric acid system and then measurement of the radioactive decay and growth of the separated 144Pr and 144Ce, respectively. The chemical procedure was explained by the phenomenon but not by the mechanism of chelation. Most students thought the experiment was an exercise in solvent extraction or radiochemical separation rather than a radioactive equilibrium experiment. However, a pure chemist considered it as a sort of physical experiment, where the chemical procedure was used only for preparation of measuring samples. Another experiment, where 137Cs was measured after isolation with ammonium phosphomolybdate, was also investigated. The experiment eliminated the need for students who were not chemists to know how to use radioactive tracers. These students appreciated the realization that they could understand the radioactivity in the environmental samples in a chemical frame of reference even though they were not chemists

  3. Evaluation of fission product yields from fission spectrum n+239Pu using a meta analysis of benchmark data

    Chadwick, Mark B.

    2009-10-01

    Los Alamos conducted a dual fission-chamber experiment in the 1970s in the Bigten critical assembly to determine fission product data in a fast (fission neutron spectrum) environment, and this defined the Laboratory's fission basis today. We describe how the data from this experiment are consistent with other benchmark fission product yield measurements for 95,97Zr, 140Ba, 143,144Ce, 137Cs from the NIST-led ILRR fission chamber experiments, and from Maeck's mass-spectrometry data. We perform a new evaluation of the fission product yields that is planned for ENDF/B-VII.1. Because the measurement database for some of the FPs is small—especially for 147Nd and 99Mo—we use a meta-analysis that incorporates insights from other accurately-measured benchmark FP data. The %-relative changes compared to ENDF/B-VI are small for some FPs (less than 1% for 95Zr, 140Ba, 144Ce), but are larger for 99Mo (3%) and 147Nd (5%). We suggest an incident neutron energy dependence to the 147Nd fission product yield that accounts for observed differences in the FPY at a few-hundred keV average energy in fast reactors versus measurements made at higher average energies.

  4. Ruthenium-106 brachytherapy for thick uveal melanoma: reappraisal of apex and base dose radiation and dose rate

    Jaberi, Ramin; Sedaghat, Ahad; Azma, Zohreh; Nojomi, Marzieh; Falavarjani, Khalil Ghasemi; Nazari, Hossein

    2016-01-01

    Purpose To evaluate the outcomes of ruthenium-106 (106Ru) brachytherapy in terms of radiation parameters in patients with thick uveal melanomas. Material and methods Medical records of 51 patients with thick (thickness ≥ 7 mm and < 11 mm) uveal melanoma treated with 106Ru brachytherapy during a ten-year period were reviewed. Radiation parameters, tumor regression, best corrected visual acuity (BCVA), and treatment-related complications were assessed. Results Fifty one eyes of 51 consecutive patients including 25 men and 26 women with a mean age of 50.5 ± 15.2 years were enrolled. Patients were followed for 36.1 ± 26.5 months (mean ± SD). Mean radiation dose to tumor apex and to sclera were 71 (± 19.2) Gy and 1269 (± 168.2) Gy. Radiation dose rates to tumor apex and to sclera were 0.37 (± 0.14) Gy/h and 6.44 (± 1.50) Gy/h. Globe preservation was achieved in 82.4%. Preoperative mean tumor thickness of 8.1 (± 0.9) mm decreased to 4.5 (± 1.6) mm, 3.4 (± 1.4) mm, and 3.0 (± 1.46) mm at 12, 24, and 48 months after brachytherapy (p = 0.03). Four eyes that did not show regression after 6 months of brachytherapy were enucleated. Secondary enucleation was performed in 5 eyes because of tumor recurrence or neovascular glaucoma. Tumor recurrence was evident in 6 (11.8%) patients. Mean Log MAR (magnification requirement) visual acuity declined from 0.75 (± 0.63) to 0.94 (± 0.5) (p = 0.04). Best corrected visual acuity of 20/200 or worse was recorded in 37% of the patients at the time of diagnosis and 61.7% of the patients at last exam (p = 0.04). Non-proliferative and proliferative radiation-induced retinopathy was observed in 20 and 7 eyes. Conclusions Thick uveal melanomas are amenable to 106Ru brachytherapy with less than recommended apex radiation dose and dose rates. PMID:26985199

  5. Transfer of radionuclides from sediments to organisms

    The following items were investigated: 1) the transfer of radionuclides (60Co, 95Zr-95Nb, 106Ru-106Rh, 37Cs, and sup(115m)Cd) from sea water to marine sediments, 2) the transfer of the radionuclides from polluted sediments to the organisms, and 3) the transfer of the radionuclides from polluted sea water to the organisms. Earth of the sea bottom, which has a diameter of 0.1 to 0.5 mm phi, was collected as sediment, and Nereis japonica and green alga were used as the organisms. 1) Activity ratio for sediment, which fits for concentration factor the organism, was at its maximum in 60Co, and it decreased in order of 95Zn-95Nb, 106Ru-106Rh, and 137Cs. The distribution of sup(115m)Cd in 500 ml of sea water, 30 g of marine sediment, and 3 g of green alga was 60, 32, and 8%, respectively. Activity ratio of sup(115m)Cd for marine sediment was 9, and concentration factor of sup(115m)Cd for green alga was 21. 2) With respect to radionuclides transfer from sediments to the organism, the level of radionuclides in Nereis japonica reached the equilibrium in about one week. Radioactivity concentration in polluted sediments at the beginning of this experiment and that in Nereis japonica 11 days later were expressed by Acpm/g and Bcpm/g, respectively, and B/A (transfer ratio) was calculated. Transfer ratio of 137Cs, 60Co, 95Zr-95Nb, and 106Ru-106Rh were 0.175, 0.050, 0.009, and 0.06, respectively. The transfer ratio of 137Cs was small when 137Cs transferred from sea water to marine sediments, but the ratio of 137Cs dissolved again into sea water in spite of being absorbed into sediments was larger than that of other nuclides. The transfer ratio of sup(115m)Cd was 0.12. 3) The transfer of nuclides to Nereis japonica was influenced strongly by sea water more than sediments. (Tsunoda, M.)

  6. Determination of burnup balance for nuclear reactor fuel on the basis of γ-spectrometric determination of fission products

    Results are given of experimental investigations in one of the versions of the method for determination of the balance of nuclear fuel burnup process by means of the γ-spectrometry of fission products. In the version being considered a balance of the burnup process was determined on the base of 106Ru, 134Cs.Activity was measured by means of a γ-spectrometer with Ge counter. Investigations were done on the natural uranium metal fuel from the heavy-water moderated reactor of the first Czechoslovakian nuclear power plant A1 in Yaslovske Bohunice. Possibility was checked of determination of the fuel burnup depth as well as of the isotope ratio and content of plutonium. Results were compared with the control data which had been obtained on the base of the mass-spectrometry of U, Pu and Nd. The reasors for deviations were estimated in the cases when they were greater tan error in the control data

  7. Recent studies related to head-end fuel processing at the Hanford PUREX plant

    Swanson, J.L.

    1988-08-01

    This report presents the results of studies addressing several problems in the head-end processing (decladding, metathesis, and core dissolution) of N Reactor fuel elements in the Hanford PUREX plant. These studies were conducted over 2 years: FY 1986 and FY 1987. The studies were divided into three major areas: 1) differences in head-end behavior of fuels having different histories, 2) suppression of /sup 106/Ru volatilization when the ammonia scrubber solution resulting from decladding is decontaminated by distillation prior to being discharged, and 3) suitability of flocculating agents for lowering the amount of transuranic (TRU) element-containing solids that accompany the decladding solution to waste. 16 refs., 43 figs.

  8. Application of a Monte Carlo Penelope code at diverse dosimetric problems in radiotherapy; Aplicacion del codigo Monte Carlo Penelope a diversos problemas dosimetricos en radioterapia

    Sanchez, R.A.; Fernandez V, J.M.; Salvat, F. [Servicio de Oncologia Radioterapica. Hospital Clinico de Barcelona. Villarroel 170 08036 Barcelona (Spain)

    1998-12-31

    In the present communication it is presented the results of the simulation utilizing the Penelope code (Penetration and Energy loss of Positrons and Electrons) in several applications of radiotherapy which can be the radioactive sources simulation: {sup 192} Ir, {sup 125} I, {sup 106} Ru or the electron beams simulation of a linear accelerator Siemens KDS. The simulations presented in this communication have been on computers of type Pentium PC of 100 throughout 300 MHz, and the times of execution were from some hours until several days depending of the complexity of the problem. It is concluded that Penelope is a very useful tool for the Monte Carlo calculations due to its great ability and its relative handling facilities. (Author)

  9. Application of a Monte Carlo Penelope code at diverse dosimetric problems in radiotherapy

    In the present communication it is presented the results of the simulation utilizing the Penelope code (Penetration and Energy loss of Positrons and Electrons) in several applications of radiotherapy which can be the radioactive sources simulation: 192 Ir, 125 I, 106 Ru or the electron beams simulation of a linear accelerator Siemens KDS. The simulations presented in this communication have been on computers of type Pentium PC of 100 throughout 300 MHz, and the times of execution were from some hours until several days depending of the complexity of the problem. It is concluded that Penelope is a very useful tool for the Monte Carlo calculations due to its great ability and its relative handling facilities. (Author)

  10. The hot bench scale plant Ester for the vitrification of high level wastes

    In this paper the hot bench-scale plant ESTER for the vitrification of the high-level radioactive wastes is described, and the main results of the first radioactive campaign are reported. The ESTER plant, which is placed in the ADECO-ESSOR hot cells of the C.C.R.-EURATOM-ISPRA, has been built and is operated by the ENEA, Departement of Fuel Cycle. It began operating with real radioactive wastes about 1 year ago, solidifying a total of 12 Ci of fission products into 2,02 Kg of borosilicate glass, corresponding to 757 ml of glass. During the vitrification many samples of liquid and gaseous streams have been taken and analyzed. A radioactivity balance in the plant has been calculated, as well as a mass balance of nitrates and of the 137Cs and 106Ru volatized in the process

  11. Development of destructive methods of burn-up determination and their application on WWER type nuclear fuels

    Results are described of a cooperation between the Central Institute of Nuclear Research Rossendorf and the Radium Institute 'V.G. Chlopin' Leningrad in the field of destructive burn-up determination. Laboratory methods of burn-up determination using the classical monitors 137Cs, 106Ru, 148Nd and isotopes of heavy metals (U, Pu) as well as the usefulness of 90Sr, stable isotopes of Ru and Mo as monitors are dealt with. The analysis of the fuel components uranium (spectrophotometry, potentiometric titration, mass-spectrometric isotope dilution) and plutonium (spectrophotometry, coulometric titration, mass- and alpha-spectrometric isotope dilution) is fully described. Possibilities of increasing the reproducibility (automatic adjusting of measurement conditions) and the sensibility (ion impuls counting) of mass-spectrometric measurements are proposed and applied to a precise determination of Am and Cm isotopic composition. The methods have been used for burn-up analysis of spent WWER (especially WWER-440) fuel. (author)

  12. Cerenkov counting as a complement to liquid scintillation counting

    A commercially available spectrometer was calibrated for liquid scintillation (LS) and Cerenkov counting efficiency (CCE) using National Institute of Standards and Technology traceable solutions. The CCE increased linearly over a 3 order of magnitude range in 40K β activity, and by 42% per MeV as β-energies increased from 0.300 to 3.54 MeV, achieving a maximum value of 80% for 106Ru/106Rh The CCE can be enhanced by 10-15% when a wavelength shifter is used. A comparison of the data showed that the CCE was typically 20-50% less than the LS counting efficiency for β-particles with maximum energies >1 MeV. Applications that utilize sequential CCE and LS counting to quantitate activity concentrations are discussed for samples containing two β-emitting nuclides of differing energies. (Author)

  13. Ruthenium nitrosyl complexes in nitric acid solutions

    Nine nitrosyl ruthenium complexes have been separated and identified in aqueous solutions of nitric acid. The separation method was low temperature, gradient elution, reverse phase partition chromatography using tri-n-butyl phosphate on a kiesel gel 60 support using 106Ru labelled complexes in the nitric acid phase. The identification of the complexes was deduced from the relationships between the products of aquation and nitration and paper chromatography using both methyl-iso-propyl ketone and nitric acid-acetone elutions. The proportion of each complex at equilibrium in various concentrations of nitric acid have been measured. The rates of nitration in 10 M nitric acid, and of aquation in 0.45 M nitric acid have been determined at 00C. (author)

  14. Radioecological Impact of the French Nuclear Power Plants on the Marine Environment

    Since the end of the 1970s a global method has been developed and improved to characterise the radioecological impact of French nuclear power plants (PWRs) on the marine ecosystems. The environment of every nuclear plant is examined yearly, in addition to special studies carried out before plant operations begin and after each period of ten years. Three nuclear power plants are situated on the Channel coast (Flamanville, Paluel, Penly) and one on the North Sea coast (Gravelines). Near the power plants local radioecological impact is measurable and is essentially due to 58Co, 60Co and 110Agm. The monitoring of artificial gamma-emitter radioactivity in bioindicators (Fucus sp.) reveals the overall decline in releases from the four power stations in question (58Co, 60Co and 110Agm) as well as the more marked decrease in relation to the reprocessing plant at La Hague (106Ru, 60Co, 125Sb, 241Am). (author)

  15. Participation of the radioanalytical laboratories of CDTN/CNEN in the national intercomparison program for radionuclide analysis in water

    This paper reports the performance of the radioanalytical laboratories of Analytical Techniques Service - SERTA/CDTN/CNEN achieved in the National Intercomparison Program - PNI conducted by the Institute of Radiation Protection and Dosimetry - IRD. The program comprehends the distribution of synthetic water samples for some (approximately 25) national laboratories in order to promote analytical credibility and to ensure the reliability of the analytical results based on radiochemical methodologies. In this program water samples are artificially contaminated at environmental level with known amounts of important radionuclides for radiological protection. The parameters and analytes evaluated are, 60Co, 65Zn, 106Ru, 133Ba, 134Cs, 137Cs, 3H, 90Sr, 226Ra, 228Ra, 210Pb, Unat, 232Th and gross alpha and beta measurements. In the last 13 years our performance was considered 'good' and 'acceptable' in over 90% of the rounds accomplished. (author)

  16. Chromatographic decontamination of medium-activity waste concentrates

    The chromatographic decontamination of a MAW concentrate was carried out in a laboratory plant in 1-l-batches in the following way: In order to purify the nitric MAW concentrate from its solid and organic contamination products, it is passed through a filter and an absorber (SM7) for organic species. Subsequently the purified solution runs on-line through all following columns. First the main activity carrier cesium (137Cs, 134Cs) is transferred to ammonium molybdate phosphate (AMP-1) by means of a newly developed fluidized bed process. In the further course, 125Sb is separated on metal oxides (Sb2O5, MnO2) and the three-valued actinides/lanthanides on an extraction-chromatographic CMPO column. Finally the remaining 106Ru and 60Co activities are separated on dimethylglyoximes (DMG) coated on active carbon. (orig./RB)

  17. Radiation Protection in Brachytherapy. Report of the SEFM Task Group on Brachytherapy

    This document presents the report of the Brachytherapy Task Group of the Spanish Society of Medical Physics. It is dedicated to the radiation protection aspects involved in brachytherapy. The aim of this work is to include the more relevant aspects related to radiation protection issues that appear in clinical practice, and for the current equipment in Spain. Basically this report focuses on the typical contents associated with high dose rate brachytherapy with 192Ir and 60Co sources, and permanent seed implants with 125I, 103Pd and 131Cs, which are the most current and widespread modalities. Ophthalmic brachytherapy (COMS with 125I, 106Ru, 90Sr) is also included due to its availability in a significant number of spanish hospitals. The purpose of this report is to assist to the medical physicist community in establishing a radiation protection program for brachytherapy procedures, trying to solve some ambiguities in the application of legal requirements and recommendations in clinical practice. (Author)

  18. Diffusion coefficients of fission products in the UO sub 2 kernel and pyrocarbon layer of BISO-coated fuel particles at extremely high temperatures

    Hayashi, Kimio; Fukuda, Kousaku (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan))

    1990-11-01

    Release of metal fission products from pyrocarbon (PyC) coated UO{sub 2} particles was studied by post-irradiation annealing at temperatures from 1600 to 2300deg C. Release of {sup 106}Ru and {sup 155}Eu was controlled by diffusion in the kernel at temperatures above 1800deg C, and their reduced diffusion coefficients in the kernel were very close to each other. The diffusion coefficient of Cs, D{sub Cs} (m{sup 2}/s), in the PyC layer was determined from the fractional release, as follows: D{sub Cs}=1.2x10{sup -3} exp(-4.12x10{sup 5} (J/mol)/RT), which was larger than that of Ce by an order of magnitude. The diffusion coefficients of fission products in the PyC layer was discussed in terms of their ionic radii and stability of their carbides. (orig.).

  19. Diffusion coefficients of fission products in the UO2 kernel and pyrocarbon layer of BISO-coated fuel particles at extremely high temperatures

    Release of metal fission products from pyrocarbon (PyC) coated UO2 particles was studied by post-irradiation annealing at temperatures from 1600 to 2300deg C. Release of 106Ru and 155Eu was controlled by diffusion in the kernel at temperatures above 1800deg C, and their reduced diffusion coefficients in the kernel were very close to each other. The diffusion coefficient of Cs, DCs (m2/s), in the PyC layer was determined from the fractional release, as follows: DCs=1.2x10-3 exp[-4.12x105 (J/mol)/RT], which was larger than that of Ce by an order of magnitude. The diffusion coefficients of fission products in the PyC layer was discussed in terms of their ionic radii and stability of their carbides. (orig.)

  20. Evaluation of artificial radioactivity of the north Western mediterranean sea and evaluation of the sanitary consequences

    The results of radiological measurements of the north west mediterranean observation network outline the level of artificial radionuclides coming from industrial seewages, 106Ru and from atmospheric fall out, 137Cs and sup(239+240)Pu measured on 3 differents types of bioindicators: Mytilus sp., Posidonia oceanica (L.) Del. and demersal fishes as Solea sp., Anguilla anguilla L., Conger conger L. Mytilus sp. is quite a perfect bioindicator of radionuclides contamination but must be linked with fishes sampling which muscles concentrate Cesium at higher level. The sanitary consequences for the waterside population involved by molluscs and fishes ingestion contamined by these 3 radionuclides lead to a fraction (10-5) of the annual dose limit recommanded by the ICRP 26

  1. Trace elements retained in washed nuclear fuel reprocessing solvents

    Analysis of purified TBP extractant from solvent extraction processes at Savannah River Plant showed several stable elements and several long-lived radioisotopes. Stable elements Al, Na, Br, Ce, Hg, and Sm are found in trace quantities in the solvent. The only stable metallic element consistently found in the solvent was Al, with a concentration which varies from about 30 ppM to about 10 ppM. The halogens Br and Cl appear to be found in the solvent systems as organo halides. Radionuclides found were principally 106Ru, 129I, 3H, 235U, and 239Pu. The 129I concentration was about 1 ppM in the first solvent extraction cycle of each facility. In the other cycles, 129I concentration varied from about 0.1 to 0.5 ppM. Both 129I and 3H appear to be in the organic solvent as a result of exchange with hydrogen

  2. Distribution and migration of radionuclides in soils and their uptake in plants after the Chernobyl reactor accident

    A method of sampling from deep soil layers was developed. With this technique, 500 samples from two sites in Styria, Austria were taken from depth up tp 80 cm and from arable soils as well as from meadows, in the years 1986, 1987 and 1988. The samples were prepared and analyzed for Cs 134, Cs 137, Ru 106, Ru 103, Sb 125, K 40 and Sr 90. The resulting depth distributions are presented in tables and graphs. The transfer functions soil-to-plant (especially wheat) are derived. The conclusion is that cesium remains tightly bound, in meadows, to a surface-near layer for years. This is not the case with Sr 90. 31 refs., 33 tabs., 181 figs

  3. A direct timing method for the two-dimensional precision coordinate detectors based on thin-walled drift tubes

    The results of a study of the longitudinal spatial resolution of 2 m long straw tubes by means of the direct timing method (DTM) are presented. The feasibility of achieving a coordinate resolution (r.m.s.) better than 9 mm over full length of the straw is demonstrated. The spatial resolution insignificantly changes when measured by detecting gammas from a 55Fe gamma-ray source or minimum ionizing particles from a 106Ru source. The use of the same type of FEE for data taking both for measuring the drift time of ionization electrons and propagation of a signal along the anode wire allows one to construct a two-dimensional detector for precision coordinate measurements

  4. Radioactivity concentrations in the North Sea

    The following nuclides can be detected in the North Sea: 90Sr, 106Ru, 137Cs, 134Cs, 241Am and 244Cm. The water in the channel east of Cherbourg still contains low quantities up to 0.5 pCi/l of the fission product 125Sb (t 1/2=2.77 a). The activity of T is not exactly known, for the german Bay it is estimated to 50 pCi/l. In comparison of these artificial radioactivies with the natural radioactivity of the North Sea, which mainly depends on 40K, 87Rb as well as uranium and decay products, it has to be taken into account that the activity of α- and β-active substances from nuclear weapons tests before 1962 and by controlled discharge from nuclear power plants, amounts to a range of 1%. (HP)

  5. Importance of colloids in the transport within the dissolved phase (<450 nm) of artificial radionuclides from the Rhone river towards the Gulf of Lions (Mediterranean Sea)

    The significance of colloidal fractions regarding the transport of artificial radionuclides in natural water systems is underlined by using sequential ultrafiltration both in the Rhone freshwater and the marine area under and outside the influence of the river outflow. Indeed, the Rhodanian aquatic system represents an interesting test site as various artificial radionuclides are released into the Rhone river by several nuclear installations. We focused our study on 137Cs, 106Ru, 60Co, 238Pu and 239+240Pu. Our results show that Fe, Al and Organic carbon (OC) are the main components of colloidal matter. Colloids represent about 15% of dissolved (238Pu and 239+240Pu and have no significance on 137Cs flux

  6. Intercomparison of radionuclides measurements in marine cockle flesh sample IAEA-134

    The results of an intercomparison exercise on a cockle flesh sample from Irish Sea, IAEA-134, designed for the determination of artificial and natural radionuclide levels, are reported. The data from 134 laboratories representing 49 countries have been evaluated. The following are the recommended values, with confidence intervals, for 40K, 60Co, 137Cs, and 239+240Pu (Reference date: 1 January 1992). Information values for 90Sr, 106Ru, 125Sb, 134Cs, 154Eu, 155Eu, 210Pb, 210Po, 226Ra, 228Ra, 228Th, 230Th, 232Th, 234U, 235U, 238U, 238Pu and 241Am are also reported. All the following values are expressed in Bq kg-1 (dry weight). (author)

  7. Intercomparison of radionuclide measurements in marine sediment sample IAEA-135

    The results of an intercomparison exercise on a marine sediment from Irish Sea, IAEA-135, designed for the determination of artificial and natural radionuclides levels, are reported. The data from 151 laboratories representing 51 countries have been evaluated. The following are the recommended values, with confidence intervals, for 40K, 60Co, 134Cs, 137Cs, 154Eu, 155Eu, 226Ra, 228Ra, 232Th,238Pu, 239+240Pu (Reference date: 1 January 1992). Information values for 57Co, 90Sr, 106Ru, 125Sb, 210Pb, 210Po, 228Th, 230Th, 234U, 235U, 238U and 241Am are also reported. All values are expressed in Bq kg-1 dry weight. (author)

  8. An iterative approach for TRIGA fuel burn-up determination using nondestructive gamma-ray spectrometry

    Wang Tienko E-mail: tkw@faculty.nthu.edu.tw; Peir Jinnjer

    2000-01-01

    The purpose of this work is to establish a method for evaluating the burn-up values of the rod-type TRIGA spent fuel by using gamma-ray spectrometry of the short-lived fission products {sup 97}Zr/{sup 97}Nb, {sup 132}I, and {sup 140}La. Fuel irradiation history is not needed in this method. Short-lived fission-product activities were established by re irradiating the spent fuels in a nuclear reactor. Based on the measured activities, {sup 235}U burn-up values can be deduced by iterative calculations. The complication caused by {sup 239}Pu production and fission is also discussed in detail. The burn-up values obtained by this method are in good agreement with those deduced from the conventional method based on long-lived fission products {sup 137}Cs, {sup 134}Cs/{sup 137}Cs ratio and {sup 106}Ru/{sup 137}Cs ratio.

  9. An iterative approach for TRIGA fuel burn-up determination using nondestructive gamma-ray spectrometry

    The purpose of this work is to establish a method for evaluating the burn-up values of the rod-type TRIGA spent fuel by using gamma-ray spectrometry of the short-lived fission products 97Zr/97Nb, 132I, and 140La. Fuel irradiation history is not needed in this method. Short-lived fission-product activities were established by re irradiating the spent fuels in a nuclear reactor. Based on the measured activities, 235U burn-up values can be deduced by iterative calculations. The complication caused by 239Pu production and fission is also discussed in detail. The burn-up values obtained by this method are in good agreement with those deduced from the conventional method based on long-lived fission products 137Cs, 134Cs/137Cs ratio and 106Ru/137Cs ratio

  10. An iterative approach for TRIGA fuel burn-up determination using nondestructive gamma-ray spectrometry.

    Wang, T K; Peir, J J

    2000-01-01

    The purpose of this work is to establish a method for evaluating the burn-up values of the rod-type TRIGA spent fuel by using gamma-ray spectrometry of the short-lived fission products 97Zr/97Nb, 132I, and 140La. Fuel irradiation history is not needed in this method. Short-lived fission-product activities were established by reirradiating the spent fuels in a nuclear reactor. Based on the measured activities, 235U burn-up values can be deduced by iterative calculations. The complication caused by 239Pu production and fission is also discussed in detail. The burn-up values obtained by this method are in good agreement with those deduced from the conventional method based on long-lived fission products 137Cs, 134Cs/137Cs ratio and 106Ru/137Cs ratio. PMID:10670930

  11. A gauge for measuring the dose rate and activity of ophthalmic applicators

    A gauge is developed for determining the dose rate distribution and surface activity of ophthalmic brachytherapy applicators, particularly 106Ru applicators. A plastic Φ2x2 mm scintillator is used as the radiation detector, featuring a high pulse count rate, which results in a law 0.5% random error, due to good counting statistics. Automatic gain control of the photomultiplier tube (PMT) is achieved using a LED as the reference light source. The PMT operates in pulse mode. Long term gain variation due to fatigue of the PMT or ambient temperature variation is thus compensated for. The count rate error due to inaccurate setting of the high voltage supply of the PMT is 0.4%, and the instability error over 7 hours of continuous operation does not exceed 102%, peak-to-peak. (author)

  12. Counting efficiency for radionuclides decaying by beta and gamma-ray emission

    In this paper, counting efficiency vs figure of merit for beta and gamma-ray emitters has been computed. It is assumed that the decay scheme has only a gamma level and the beta-ray emission may be coincident with the gamma-rays or the internal-conversion electrons. The radionuclides tabulated are: 20O, 20F, 28Al, 35P,41Ar, 42K, 47Se, 62Fe, 66Cu, 81Ge, 86Rb, 104Rh, 108Ru, 112Pd, 121Sn(m), 122In, 129I, 141Ce, 142Pr, 151Sm, 170Tm, 171Tm, 194Os, 203Hg, 205Hg, 210Pb, 225Ra, 244Am(m). It has been assumed that the liquid is a toluene based scintillator solution in standard glass vials containing 10 cm3. (Author)

  13. Development of a cosmic veto gamma-spectrometer

    Cosmic radiation contributes significantly towards the background radiation measured by a gamma-spectrometer. A novel cosmic veto gamma-spectrometer has been developed that provides a mean background reduction of 54.5%. The system consists of plastic scintillation plates operated in time-stamp mode to detect coincident muon interactions within an HPGe gamma-spectrometer. The instrument is easily configurable and provides improved sensitivity for radionuclides indicative of nuclear weapons tests and reactor incidents, including 140Ba, 95Zr, 99Mo, 141Ce, 147Nd, 131I, 134Cs and 137Cs. This has been demonstrated for Comprehensive Nuclear-Test-Ban Treaty applications to obtain the required 140Ba MDA of 24 mBq within 2 days counting. Analysis of an air filter sample collected during the Fukushima incident indicates improved sensitivity compared to conventional gamma-spectrometers. (author)

  14. (d,p) reactions on 124Sn, 130Te, 138Ba, 140Ce, 142Nd, and 208Pb below and near the Coulomb barrier

    The reactions 124Sn(d,p)125Sn, 130Te(d,p)131Te, 138Ba(d,p)139Ba, 140Ce(d,p)141Ce, 142Nd(d,p)143Nd, and 208Pb(d,p)209Pb have been investigated by measuring the differential cross sections of the (d,p) reactions and of the elastic scattering of deuterons at various incident energies below and near the Coulomb barrier. Using scattering potentials which describe the elastic scattering of the particles in the entrance and exit channels, reduced normalizations of 40 final states have been determined which are nearly independent of the uncertainties due to the ambiguities of optical potentials. The experimental errors are 8% on the average. In the energy region studied the expected constancy of derived spectroscopic factors is demonstrated

  15. Solvent extraction using tetracycline as complexing agent Pt. 14

    The behaviour of tetracycline as an extracting agent for Sr, I, Ba, Mo, Tc, Zr, Nb, Cs, Ru, Te and U was studied and the influence of the acidity of the aqueous phase upon extraction of the elements mentioned was examined. Experiments were made to determine whether the species extracted into the organic phase is the complex formed between tetracycline and the elements considered and to determine the time of shaking necessary so that the equilibrium between the phases is attained. As a practical application, the possibility of using the tetracycline-benzyl alcohol system for separating the fission products sup(137)Cs, sup(140)La, sup(141)Ce, sup(103)Ru, sup(95)Nb from each other and from uranium is presented. The same study was made for sup(131)I, sup(99m)Tc, sup(99)Mo, sup(132)Te, sup(239)Np and uranium and the steps necassary for the separation of these elements are proposed. (author)

  16. Particle size distribution of aerosols during sand-blasting of steam turbines

    Studies were performed to determine the activity median aerodynamic diameter and the solubility classification of radioactive airborne particulates produced during sand blasting of steam turbines at Chin Shan Nuclear Power Station in Taiwan. Cascade impactors were used to collect air samples in the sand blasting house for analyses of particle size and elemental composition. Radionuclides identified in the samples included 60Co, 137Cs, 131I, 140Ba, 140La and 141Ce. These were found to have an activity median aerodynamic diameter of 3 μm to 4 μm, except for volatile 131I, which had a somewhat smaller diameter of 2.8 μm. The major elements composing the aerosols were Si, Fe, Ca, K, Al, and Cr. (author)

  17. 1975 progress report: Idaho National Engineering Laboratory site radioecology--ecology programs

    Results are reported from measurements of the content of various radionuclides in the tissues of wild animals on or near the Idaho National Engineering Laboratory sampled during 1975. Tissue samples from antelope, waterfowl, rodents, rabbits, and doves were analyzed for 13 radionuclides, including 134Cs, 137Cs, 95Zr, 95Nb, 103Ru, 238Pu, 239Pu, 90Sr, 131I, and 60Co which were responsible for the largest amounts of radioactivity. Measurements were also made of the content of 238Pu, 239Pu, and 241Am in soil samples and the radioactivity in tumbling weeds at the radioactive waste management site. Data are included from studies on the ecology of the pygmy rabbit, Salvilagus idahoensis, amphibians, reptiles, birds of prey, rodents, and coyotes, and vegetation in relation to land use at the site. Seasonal variations in the deposition and retention of 141Ce and 134Cs on sagebrush and bottlebrush grass were compared

  18. Germanium junction detectors. Theoretical and practical factors governing their use in radiation spectrometry

    Semi-conductor detectors have recently greatly increased the possibilities available to nuclear spectroscopists for the study of α, β and γ radiations. Their use in radio-chemistry has encouraged us to study their principle, their mechanism and also the conditions under which they can be used. The first part, which is theoretical, consists of a summary of what should be known concerning the best use of junction detectors, in particular Ge (Li) detectors. The second part, which is experimental, summarizes the laboratory work carried out over a period of one year on Ge (Li) detectors. Stress is laid on the possibilities presented by the use of these detectors as photo-electric spectrometers, and also on the precautions required. Amongst the numerous results presented, the resolution of 2.52 keV obtained for the γ radiation of 145.5 keV for 141Ce may be particularly noted. (authors)

  19. Studies on inner bremsstrahlung from a few β-emitting isotopes

    Past experimental studies on the inner bremsstrahlung (IB) emission from the forbidden β transitions have shown marked deviations from the theoretical calculations of Lewis and Ford, Ford and Martin, Chang and Falkoff, Madansky and Gebhardt. In this paper we have re-analysed the data of IB emissions from four β-emitting isotopes, namely 89Sr, 141Ce, 111Ag and 99Tc, whose transitions are classified as forbidden. The raw experimental data already available in the literature are critically examined in the light of relevant statistics in order to arrive at meaningful conclusions. The unfolding of the IB spectra was done following the step-by-step procedure of Liden and Starfelt. The results obtained were different from those reported in the literature. (author)

  20. Application of the brittle fracture technique (BFT) to homogenise biological samples and some observations regarding the distribution behaviour of the trace elements at different concentration levels in a biological matrix

    NAA was used to analyse K, P, Cl, Na, Fe, Zn, Rb, Mn, Se, Co, and Ag in bovine liver, before and after homogenization, using brittle fracture technique (BFT). The liver specimen analysed in this experiment did not present any extreme variation problem with respect to the trace element distribution profile in the liver matrix. Elaborate sample-handling and the possible influence of the interfering components such as resudial blood, blood vessels and fat on the concentration profile of the above mentioned elements are discussed. In another experiments using 60Co, 134Cs, 141Ce and 198Au radiotracers, the physical distribution of the added tracers following the process of biological matrix disintegration, for homogenization purposes was studied at 1 mg to 10 pg concentration levels. The results indicate that BFT is an efficient, clean and practical tool that meets the homogenization problems because of its suitability to practically all types of biomedical samples. (T.G.)

  1. Nuclear Decay Data for the International Reactor Dosimetry Library for Fission and Fusion (IRDFF: Updated Evaluations of the Half-Lives and Gamma Ray Intensities

    Chechev Valery P.

    2016-01-01

    Full Text Available Updated evaluations of the half-lives and prominent gamma ray intensities have been presented for 20 radionuclides – dosimetry reaction residuals. The new values of these decay characteristics recommended for the IRDFF library were obtained using the approaches and methodology adopted by the working group of the Decay Data Evaluation Project (DDEP cooperation. The experimental data published up to 2014 were taken into account in updated evaluations. The list of radionuclides includes 3H, 18F, 22Na, 24Na, 46Sc, 51Cr, 54Mn, 59Fe, 57Co, 60Co, 57Ni, 64Cu, 88Y, 132Te, 131I, 140Ba, 140La, 141Ce, 182Ta, 198Au.

  2. Seasonal variations in deposition and retention of cerium-141 and cesium-134 in cool desert vegetation

    Deposition velocities and retention half-times were measured for 141Ce and 134Cs aerosols on big sagebrush (Artemisia tridentata) and squirreltail bottlebrush (Elymus elymoides). These aerosols were released over a native community in southeast Idaho during each of three seasons -spring, summer, and winter -to study the effects of plant development and growth on deposition velocity and retention. Air concentrations during the release and vegetation concentration after the release were measured to determine deposition velocity. Friction velocity, roughness length, and particle size were measured to determine retention half-time. There was no significant difference between nuclides for deposition velocity and retention half-time. Species differences were significant (P -1 in spring, summer and winter, respectively. Big sagebrush values were 1.6, 1.6, and 1.0 mm s-1. Retention data indicated a rapid initial loss (half-times of 1-2 d) followed by a slower loss (half-times of several weeks). (Author)

  3. Medical physics aspects of ophthalmic brachytherapy

    Intraocular melanoma is the most common primary malignancy of the eye. Radiation therapy using ophthalmic plaque has proved successful in the management of various ocular lesions. Although a few centres were using 90Sr/90Y plaques for shallow turtlours some years ago, eye plaque therapy was not a common practice in India. A revived interest in the use of eye plaque therapy and very high cost of imported sources has led to the development and production of 125I seed sources by the Radiopharmaceuticals Division, BARC. This report presents a brief description on the clinical, dosimetry and radiation safety aspects of 90Sr/90Y and 106Ru/106Rh beta ray and 125I gamma ray eye plaque applicators. This report has been divided in five Sections. Section I presents general introduction of ophthalmic brachytherapy including the structure of a human eye, types of ophthalmic plaques and characteristics of radioisotopes commonly used in such applications. A brief review of sources, applicators and dosimetry of 90Sr/90Y and 106Ru/106Rh beta and 125I gamma ophthalmic plaques are given in Section II and Section III, respectively. Section IV contains the single seed dosimetry data of BARC OcuProsta 125I seed as well as dosimetry data of typical eye plaques loaded with BARC OcuProsta 125I seed. Quality assurance and radiation safety aspects of these eye applicators are described in Section V. A proforma of the application required to be filled in by the user institution for obtaining regulatory consent to start eye plaque therapy has also been appended to this report. (author)

  4. The Influence of Body Size and Food Preparation Practices on the Uptake and Loss of Radionuclides in Cumbrian Winkles

    It has been suggested that larger winkles may show higher concentrations of radioactivity and that critical group members, when providing MAFF with sub-samples of winkles they have collected, retain the largest organisms for consumption. If both these hypotheses are true, this could imply higher doses than typically estimated. Conversely, it is assumed that winkles are consumed immediately following collection, without gut clearance, which may overestimate the consumption dose. Results obtained in this study indicate the following. (1) Inverse correlations are observed between concentration and body size for 106Ru and 241Am. A positive relationship is observed for 60Co. Although concentrations of 137Cs decrease with increasing body size the negative correlation is not significant, while 110Agm concentration is independent of body size. (2) There is no evidence that critical group consumers retain larger organisms. In any case, consuming larger or smaller winkles, over the size range tested, probably does not affect dose uptake by more than 10%. (3) Concentrations of plutonium and americium decline to 50% of original by soaking winkles for 18 h. Concentrations of caesium are also reduced. (4) Concentrations of 106Ru, 110Agm and 60Co are not reduced by soaking. Overall, current approaches to deriving consumption doses are not likely to suffer from selection bias. Overnight soaking of winkles in saline solution could decrease radiation doses to consumers by a factor of nearly 2; provided that the fractional gut transfer of activity remaining is unaffected. This last assumption, however is questionable and the current approach should provide a 'reasonably conservative' dose estimate appropriate to critical group studies. (author)

  5. 1971 Animal Investigation Program. Annual report

    Data are presented that were obtained from the radioanalysis of tissues collected from cattle, deer, desert bighorn sheep, and other wildlife that reside on or near the Nevada Test Site. Cesium-137 and 106Ru were the only gamma-emitting radionuclides detected in the soft tissues of range cattle. Ruthenium-106 was detected only in the lungs of animals sampled in May. Strontium-90 levels in the cattle femurs ranged from 2 to 37 pCi/g of ash. The latter value was found in the bones of a 14-year-old cow that had lived on the Nevada Test Site her entire life. The bones of the same animal also had the highest level of 239Pu (46 pCi/g of ash) that was reported. Analysis of her 8-month-old fetus revealed the presence of detectable levels of 239Pu which indicates placental transfer of this radionuclide. The average 90Sr levels in the bones from deer and desert bighorn sheep were 3.2 and 4.7 pCi/g of ash, respectively. Elevated levels of 106Ru and 3H were found in the tissues of two mule deer collected near the drainage ponds that collect runoff waters from mines used for nuclear testing activities. Other animals sampled included Golden eagles, feral horses, coyotes, and chukar. The 137Cs levels in an eagle collected during 1964 varied only slightly from one collected during 1971. No gross or microscopic lesions were detected that could be attributable to the effects of ionizing radiation. (auth)

  6. Radioecological impact of the Chernobyl accident on continental aquatic ecosystems

    The pooling of knowledge on water, sediments, aquatic plants and fish allowed an evaluation report to be drawn up on the impact of Chernobyl accident and to extract data on the mechanisms in the transfer of certain radionuclides in rivers and lakes. The radioactivity is related to the level of deposits, essentially, in wet form. Differences in radioactivity levels are noted owing to the distance from Chernobyl, the atmospheric streams and pluviometric conditions. The most commonly detected radionuclides are: 131I, 132Te, 134+137Cs, 103+106Ru, 110m Ag and, to a lesser degree, 89Sr and 90Sr. Very quickly, 137Cs becomes dominant. The peak of radioactivity in rivers occurred very soon after the accident. It was of short duration and the decrease in radioactivity was very quick due to dilution. In lakes, this decay was much slower. In sediment, the radioactivity varied in time owing either to new deposits or to the migration of those deposits downstream in the river basins. The radionuclides present in fallout can be quickly detected using aquatic plant. In certain areas, the concentration of 137Cs increased 200-fold in a few hours. In fish, the presence of 134+137Cs, 103+106Ru, 110m Ag and 90Sr are noted. The only radionuclide of which fixing dynamics can be followed is 137Cs. River fish was only subjected to water and food with a high radioactivity for a very short time and their 137Cs concentration remained constantly low. The effective half-life of 137Cs observed in situ for fish is from 100 to 200 days. For lacustrine fish, we observe differences in radiocontamination, according to the regions (from 48,000 Bq.kg-1 w.w., in Sweden, to 110 in the North of Corsica or the Netherlands), in lakes (in Northern Italy, 137Cs concentrations in fish are higher in small lakes), and species

  7. Radiogenic late effects in the eye after therapeutic application of beta radiation

    Beta irradiation with 90Sr/90Y is used to treat epibulbar tumours (carcinoma, melanoma) and irradiation with 106Ru/106Rh is used to treat intra-ocular tumours (melanoma, retinoblastoma). Two studies have been carried out. Since 1960, 185 patients with epibulbar pigment tumours and 15 patients with conjunctiva carcinomas have been treated with 90Sr/90Y-applicators and observed for several years. The dose applied was 10,000 to 20,000 rads at the focus depending on the type and extent of the tumour. Apart from teleangiectasias of the conjunctiva, there were only a few cases of severe radio-induced complications such as keratopathies and secondary glaucoma, which were regarded as the lesser evil in comparison with the main disease. The radiation cataract after beta irradiation remains peripheral and does not impair vision. So far 39 patients with choroid melanomas and 22 children with retinoblastomas have been observed for more than 5 years after beta irradiation with 106Ru/106Rh. The dose applied at the sclera surface was 40,000 to 100,000 rads for 4 to 8 days. In 39 patients with successfully irradiated choroid melanomas, radio-induced late complications developed such as macula degeneration, opticus atrophy and retinal-vessel ablations, which may impair vision. In the 22 children irradiated, only 7 cases of late complications with impaired functions could be observed. Whereas radiation-induced late damage after beta irradiation of the front section of the eye is of small clinical importance, especially in older patients, intra-ocular tumours with radio-induced late damage in the retinal vessel and capillary system have to be expected after high-dose beta irradiation

  8. Retrospective dosimetry of an accidental intake case of radioruthenium-106 at the Tokai reprocessing plant

    On November 30, 1978, two workers in the acid recovery cell of the nuclear spent fuel reprocessing plant of JAEA-NFCEL were involved in an accident in which they became unconscious due to lack of oxygen. They were rescued immediately by other workers and were given artificial respiration to restore their normal breathing. Subsequent measurements by the whole-body counter showed that they were contaminated internally with 106Ru. Prolonged lung monitoring was carried out for one of them. A significantly high activity of 106Ru was obtained in the lung monitoring on the day of the accident. The physicochemical characteristics of the incorporated radioactive materials were not observed. In order to perform more reasonable internal dose assessment, the interpretation of the bioassay datasets of the worker was made based on the guideline demonstrated in the EU project IDEAS. The effective half-life of the materials in the lungs was determined to be 140 days which leads to the default Type S absorption type in the HRTM and the f1 value was estimated to be less than 0.005 which is one-tenth of the default value. Simultaneous intakes via inhalation and ingestion were also suggested from several pieces of evidence although pure inhalation was assumed for internal dose assessment at the time of the accident. The aerosol size of the materials was not determined due to a lack of information if assuming simultaneous intakes; however, the resulting committed effective dose was about 1 mSv and its variation was small against the aerosol size ranging from 1 μm to 20 μm. (author)

  9. Improved estimate of the cross section for inverse beta decay

    Ankowski, Artur M

    2016-01-01

    The hypothesis of the conserved vector current, relating the vector weak and isovector electromagnetic currents, plays a fundamental role in quantitative description of neutrino interactions. Despite being experimentally confirmed with great precision, it is not fully implemented in existing calculations of the cross section for inverse beta decay, the dominant mechanism of antineutrino scattering at energies below a few tens of MeV. In this article, I estimate the corresponding cross section and its uncertainty, ensuring conservation of the vector current. While converging to previous calculations at energies of several MeV, the obtained result is appreciably lower and predicts more directional positron production near the reaction threshold. These findings suggest that in the current estimate of the flux of geologically produced antineutrinos the 232Th and 238U components may be underestimated by 6.1 and 3.7%, respectively. The proposed search for light sterile neutrinos using a 144Ce--144Pr source is predi...

  10. Radiation-induced mesotheliomas in rats

    Mesotheliomas have been reported in rats that inhaled plutonium, but these tumors have not been extensively studied. To investigate a possible role for inhaled radionuclides in the induction of mesotheliomas, four life-span studies conducted at the Inhalation Toxicology Research Institute are reviewed. A total of 3076 F344 rats were exposed by inhalation to aerosols of 239PuO2, mixed uranium-plutonium oxide, or 144CeO2. Results showed that a low incidence of pleural mesotheliomas was induced by either alpha- or beta-emitting radionuclides deposited and retained in the lung. Chronic alpha irradiation was more effective per unit dose in producing mesotheliomas than chronic beta irradiation of the lung by a factor of 15. 7 refs., 1 tab., 7 figs

  11. Study on measurement of trace radioactivity, (2)

    The method was worked out so as to measure 59Fe, 60Co, 65Zn, 95Zr, and 144Ce successively from the same sample by ion-exchange separation. This method was also applicable to the measurement of 90Sr and 137Cs. It was confirmed that 131I in milk could be measured satisfactorily by the method of US Atomic Energy Commission, when raw milk before processing was preserved in good condition. 3H in natural water can be measured with a gas magnifying counter without isotope concentration when water is transformed into hydrogen gas. It was found that an external heater type reactor is desirable to transform 3H in water into methane gas so far as the repair is concerned. The present reactor needs some improvement, however, to get better yield as the best synthesizing yield for methane gas obtained so far was only 48.8%. (Kobatake, H.)

  12. Training of skin decontamination and its results

    In the nuclear power and radioisotope handling facilities, one of the most important problems is a radioactive contamination on skin. Hand skin contamination occurs very often in the operation area and such surface contamination must be removed as soon as possible to prevent an internal contamination. From 1967 to 1975, training courses for skin decontamination had been held with total 536 of trainee based on the radiation protection manual at the Oarai Research Establishment of JAERI. In the training courses, fresh pig skin samples used instead of human skin were contaminated with 137Cs, 131I, 85Sr, 60Co, 144Ce, 88Y, 239Pu, fission products and activated metal corrosion particles, respectively. These samples were washed practically by each trainee with the skin decontamination method recommended in the manual. Results obtained in the training showed that such training itself is a significant work and this skin decontamination method is an excellent first aid. (auth.)

  13. The risk of liver tumors in dogs and man from radioactive aerosols

    Life-span studies in progress using beagle dogs that inhaled relatively soluble or relatively insoluble forms of radionuclides will provide information from which we may project the risk to humans for liver cancer from inhaled radioactive material. Twenty-two liver tumors have been observed in dogs exposed to beta-emitting radionuclides, mainly 144Ce, and one liver tumor in a dog exposed to 238Pu. Two liver cancers were also observed in control dogs. The risk of liver cancer in dogs that inhaled beta-emitting radionuclides was calculated to be 90 liver cancers per million rads. The risk of liver cancers in dogs in our studies and in studies at the University of Utah, when compared to the incidence of liver tumors in humans exposed to Thorotrast, suggest that the risk of liver cancer from an inhaled beta-emitting radionuclide in people is about 30 liver cancers per million person-rads. 19 refs., 3 tabs

  14. Electrodeposition of actinide traces from aqueous alkaline solutions and tributyl phosphate

    The electrodeposition of uranium and trace quantities of 239Pu, 234Th, 144Ce on a stainless steel disk was investigated from 0.5-2.0M NaOH and the two-phase system, extract of actinides in TBP-aqueous solution of NaOH. The electrodeposition yield of the above elements reaches 98-100% in 40 min of electrolysis with current density 0.4-0.5 A/cm2. The presence of 0.5M Na2CO3, 2.0M NaNO3, 2.0M NaNO2, 0.2M NaF in alkaline solutions does not decrease the electrodeposition yield. The electrodeposited films meet all the requirements of α-spectrometry. The uranium oxidation states (V) and (IV) were determined in the electrodeposited films. (author) 9 refs.; 3 figs.; 1 tab

  15. Methodology for the evaluation of decontaminant drugs at in vitro systems

    An experimental system was developed in order to facilitate hte study of the action of decontaminant drugs in hepatic tissue. Three stages are distinguished: 1) The isolation and the hepatocytes culture in the presence of a chelant agent. 2) The obtainment of the soluble cytoplasmic fraction and its chromatographyc analysis. 3) The comparison of the behaviour of the chelant agent in in vivo and in vitro of the mentioned fraction. 144CeCl was employed as a radionuclide and DTPA CaNa3 as a decontaminant agent. The preliminary results of the mechanism of action of the decontaminant obtained by chromatography shows a different distribution of the radionuclide between compounds of high and low molecular weight, in the hepatocytes incubated in the presence of the chelant concerning the controls. (M.E.L.)

  16. Development of a technology and a pilot plant for treatment of small volumes of liquid radioactive waste

    The development of technology for treatment of liquid radioactive waste is described. Waste arisings are estimated. Liquid wastes of concern are mainly low active wastes according to the Bulgarian legislation. The activity is determined by the presence of 134Cs, 137Cs, 60Co, 90Sr, 144Ce, 65Zc, 54Mn, 110mAg. Different precipitation processes are compared. The mixed iron hydroxide - calcium phosphate precipitation is determined as suitable for decontamination of the liquid radioactive waste. Effective decontamination is achieved when precipitation is followed by ion exchange. Additional increase of the decontamination is possible when sorbents are added during the precipitation step. The sorption and desorption of radionuclides on zeolites are studied. Cement solidification and thermal treatment of zeolites are studied for immobilization of radioactive material from precipitation and ion exchange. Both methods produce stable waste forms suitable for containment of the radionuclides. (author). 17 refs, 3 figs, 12 tabs

  17. Search for Sterile Neutrinos with a Radioactive Source at Daya Bay

    Dwyer, D A; Littlejohn, B R; Vogel, P

    2011-01-01

    The far site detector complex of the Daya Bay reactor experiment is proposed as a location to search for sterile neutrinos with > eV mass. Antineutrinos from a 500 kCi 144Ce-144Pr beta-decay source (DeltaQ=2.996 MeV) would be detected by four identical 20-ton antineutrino targets. The site layout allows flexible source placement; several specific source locations are discussed. In one year, the 3+1 sterile neutrino hypothesis can be tested at essentially the full suggested range of the parameters Delta m^2_{new} and sin^22theta_{new} (90% C.L.). The backgrounds from six nuclear reactors at >1.6 km distance are shown to be manageable. Advantages of performing the experiment at the Daya Bay far site are described.

  18. Radionuclides in plankton from the South Pacific Basin

    We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review has shown that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 104. We participated in Operations Deepfreeze 1981 and 1982, collecting a total of 48 plankton samples from the USCGC Glacier on its Antarctic cruises. Battelle Pacific Northwest Laboratories sampled air, water, rain, and fallout. We were able to measure concentrations in plankton of the naturally-occurring radionuclides 7Be, 40K, and the U and Th series, and we believe that we have detected low levels of 144Ce and 95Nb in seven samples ranging as far south as 680. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and the protozoa content of the samples. 7 references, 5 figures

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

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

    1995-12-01

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

  20. Identification of levels in neutron-rich 145Ce and 147Ce nuclei

    High-spin structures in the neutron-rich nuclei 145Ce and 147Ce produced in the spontaneous fission of 252Cf have been investigated by prompt γ-ray spectroscopy. A collective band structure in 145Ce is identified. Several sidebands along with the new high-spin states in 147Ce are also identified. Particle-plus-rotor model calculations indicate that the yrast bands in 145Ce and 147Ce most probably originate from coupling of the νi13/2 orbital to the ground states of 144Ce and 146Ce. The ground state configurations of 145,147Ce are (νh9/2+νf7/2) and νh9/2, respectively. (c) 1999 The American Physical Society

  1. Fixation of {gamma}-radionuclides by the PVA-PMAA system

    Won, Hui Jun; Ahn, Byung Gil; Jung, Chong Hun; Kim, Gye Nam; Oh, Won Zin [KAERI, Taejon (Korea, Republic of)

    2000-06-01

    A series of laboratory experiments was conducted to investigate the fixation characteristics of poly(vinylalcohol)-poly(methacrylic)(PVA-PMAA) mixed solution on the soluble {gamma}-radionuclides. Using the potentiometric titration technique, it was found out that the PVA and PMAA in a solution form inter macromolecular complex. The mobilized portion of each radionuclide by water from sand surface treated with a fixative was measured by {gamma}-ray spectroscopy. The mobilized portion of minor radionuclides such as {sup 241}Am, {sup 154}Eu, {sup 155}Eu and {sup 144}Ce were higher than those of {sup 134}Cs and {sup 137}Cs. The capability of PVA-PMAA system was better among the candidate solutions for the fixation of total {gamma}-radioactivity. {sup 134,137}Cs which is composed of more than 85 percent of total {gamma}-radioactivity could be fixed effectively by the PVA-PMAA solution. (author)

  2. Fixation of γ-radionuclides by the PVA-PMAA system

    A series of laboratory experiments was conducted to investigate the fixation characteristics of poly(vinylalcohol)-poly(methacrylic)(PVA-PMAA) mixed solution on the soluble γ-radionuclides. Using the potentiometric titration technique, it was found out that the PVA and PMAA in a solution form inter macromolecular complex. The mobilized portion of each radionuclide by water from sand surface treated with a fixative was measured by γ-ray spectroscopy. The mobilized portion of minor radionuclides such as 241Am, 154Eu, 155Eu and 144Ce were higher than those of 134Cs and 137Cs. The capability of PVA-PMAA system was better among the candidate solutions for the fixation of total γ-radioactivity. 134,137Cs which is composed of more than 85 percent of total γ-radioactivity could be fixed effectively by the PVA-PMAA solution. (author)

  3. Measurement by γ spectrometry of specific activities of radioisotopes present in vegetal ashes. Study of variations of the ambient radioactivity level in the Grenoble transverse valley from March 1966 to August 1968

    The first part of this report addresses the dosimetry of γ emitting radio-elements which are present in vegetal samples. The dose measurements were performed by spectrometry and results were processed by using a least square method. The second part reports works performed in the Grenoble transverse valley by using the same techniques. Radioactivity fluctuations of various radio-elements (40K, 54Mn, 95Zr + 95Nb, 103Ru + 106Rh, 137Cs, 137Ba, 140Ba + 140La, 144Ce + 144Pr) in various vegetal species, in water and in sediments have been monitored in seven points of the Isere river banks, upstream and downstream the city of Grenoble, from March 1966 to August 1968. Fluctuations observed for each radio-element are explained by comparison with physiologic, hydrologic and atmospheric climate conditions. The principles of a systematic control of a site for the detection of possible radioactive pollutions are then defined

  4. A study of radionuclide transfer between invertebrates and their marine sedimentary environment

    Exchanges between sediment and marine organisms were studied in some benthic marine invertebrates, especially Arenicola marina L. (an Annelid). Experiments were carried out on the transfer of 60Co, 137Cs and accessorily 59Fe and 144Ce. Water was the chief vector for benthic marine invertebrates. These invertebrates seemed to act mainly in sedimentary areas on the redistribution of adsorbed radionuclides within the sediment. Radioactive contamination of the invertebrates was affected by various physiological or ecological factors. Benthic marine invertebrates were then studied as links in food chains. The transfer of 60Co was studied in three food chains or fractions of food chains. The procedure allowed interesting observations from the health protection point of view and more fundamental investigations on cobalt metabolism (regulation, excretion) in a mollusc, a crustacea and a teleost

  5. Recent Borexino results and prospects for the near future

    D'Angelo, D; Benziger, J; Bick, D; Bonfini, G; Avanzini, M Buizza; Caccianiga, B; Cadonati, L; Calaprice, F; Cavalcante, P; Chavarria, A; Chepurnov, A; Davini, S; Derbin, A; Empl, A; Etenko, A; von Feilitzsch, F; Fomenko, K; Franco, D; Galbiati, C; Gazzana, S; Ghiano, C; Giammarchi, M; Goeger-Neff, M; Goretti, A; Grandi, L; Hagner, C; Hungerford, E; Ianni, Aldo; Ianni, Andrea; Kobychev, V; Korablev, D; Korga, G; Kryn, D; Laubenstein, M; Lehnert, B; Lewke, T; Litvinovich, E; Lombardi, F; Lombardi, P; Ludhova, L; Lukyanchenko, G; Machulin, I; Manecki, S; Maneschg, W; Manuzio, G; Meindl, Q; Meroni, E; Miramonti, L; Misiaszek, M; Mosteiro, P; Muratova, V; Oberauer, L; Obolensky, M; Ortica, F; Otis, K; Pallavicini, M; Papp, L; Perasso, L; Perasso, S; Pocar, A; Ranucci, G; Razeto, A; Re, A; Romani, A; Rossi, N; Saldanha, R; Salvo, C; Schoenert, S; Simgen, H; Skorokhvatov, M; Smirnov, O; Sotnikov, A; Sukhotin, S; Suvorov, Y; Tartaglia, R; Testera, G; Vignaud, D; Vogelaar, R B; Winter, J; Wojcik, M; Wright, A; Wurm, M; Xu, J; Zaimidoroga, O; Zavatarelli, S; Zuber, K; Zuzel, G

    2014-01-01

    The Borexino experiment, located in the Gran Sasso National Laboratory, is an organic liquid scintillator detector conceived for the real time spectroscopy of low energy solar neutrinos. The data taking campaign phase I (2007 - 2010) has allowed the first independent measurements of 7Be, 8B and pep fluxes as well as the first measurement of anti-neutrinos from the earth. After a purification of the scintillator, Borexino is now in phase II since 2011. We review here the recent results achieved during 2013, concerning the seasonal modulation in the 7Be signal, the study of cosmogenic backgrounds and the updated measurement of geo-neutrinos. We also review the upcoming measurements from phase II data (pp, pep, CNO) and the project SOX devoted to the study of sterile neutrinos via the use of a 51Cr neutrino source and a 144Ce-144Pr antineutrino source placed in close proximity of the active material.

  6. Measurement of leached hulls

    Leached hulls are the short lengths of fuel rod cladding and fuel element hardware which constitute a major waste product of a reprocessing plant employing a chop-and-leach head-end process. The small, undissolved fuel residue (0.1 to 1.0% of original fuel content) which is discarded with this waste must be measured for safeguards, material accountability, and process control reasons. This report gives a critical analysis of hull measurement techniques involving the analysis of fission product gamma rays, spontaneous fission neutrons from curium, and delayed neutron activation. Major emphasis is given to the measurement of 2186-keV gamma rays from 144Ce--144Pr. A detailed description of typical leached hull characteristics is presented at the beginning of the report. An extensive review of experience gained from existing hull measurement systems in the United Kingdom, France, Japan, Germany, Italy, and the United States is presented

  7. EML Surface Air Sampling Program, 1990--1993 data

    Measurements of the concentrations of specific atmospheric radionuclides in air filter samples collected for the Environmental Measurements Laboratory's Surface Air Sampling Program (SASP) during 1990--1993, with the exception of April 1993, indicate that anthropogenic radionuclides, in both hemispheres, were at or below the lower limits of detection for the sampling and analytical techniques that were used to collect and measure them. The occasional detection of 137Cs in some air filter samples may have resulted from resuspension of previously deposited debris. Following the April 6, 1993 accident and release of radionuclides into the atmosphere at a reprocessing plant in the Tomsk-7 military nuclear complex located 16 km north of the Siberian city of Tomsk, Russia, weekly air filter samples from Barrow, Alaska; Thule, Greenland and Moosonee, Canada were selected for special analyses. The naturally occurring radioisotopes that the authors measure, 7Be and 210Pb, continue to be detected in most air filter samples. Variations in the annual mean concentrations of 7Be at many of the sites appear to result primarily from changes in the atmospheric production rate of this cosmogenic radionuclide. Short-term variations in the concentrations of 7Be and 210Pb continued to be observed at many sites at which weekly air filter samples were analyzed. The monthly gross gamma-ray activity and the monthly mean surface air concentrations of 7Be, 95Zr, 137Cs, 144Ce, and 210Pb measured at sampling sites in SASP during 1990--1993 are presented. The weekly mean surface air concentrations of 7Be, 95Zr, 137Cs, 144Ce, and 210Pb for samples collected during 1990--1993 are given for 17 sites

  8. Toxicity of inhaled beta-emitting radionuclides: an experimental approach

    An experimental approach to evaluation of the toxicity of inhaled beta-emitting radionuclides in laboratory animals is described. These radionuclides are being studied in both relatively soluble (90SrCl2, 144CeCl3, 91YCl3 or 137CsCl) and relatively insoluble aerosol forms (90Y, 91Y, 144Ce or 90Sr in fused aluminosilicate particles). Initial lung or whole-body radionuclide burdens were selected to result in early deaths due to severe lesions at the highest exposure levels, and more subtle changes, such as neoplasia, at the lower levels. The organs affected vary depending on the solubility and chemical characteristics of the isotope. For radionuclides inhaled in relatively soluble forms, long-term effects have been seen in the liver, skeleton, respiratory tract and other tissues. In contrast, long-term effects seen in the dogs exposed to relatively insoluble forms have been mainly associated with the lung and contiguous tissues. In all experiments, emphasis is placed on an evaluation of the influence of radiation dose rate and total dose on the resulting dose-response relationship. Over the mid-range of exposure levels, it will be possible to compare the radiation dose and biological response relationships for the several radioactive aerosols with their different radiation dose patterns. These studies with young adult dogs are complemented with comparable studies in other species (mice, rats and Syrian hamsters) and with animals of different ages (immature, aged). This basic approach, with emphasis on factors that alter the resulting radiation dose pattern, offers the maximum likelihood of meeting the continuing, and not always predictable, needs for information on the toxicity of inhaled beta-emitting radionuclides that may be encountered in nuclear industry operations

  9. Toxicity of inhaled beta-emitting radionuclides: an experimental approach

    An experimental approach to evaluation of the toxicity of inhaled beta-emitting radionuclides in experimental animals is described. Graded levels of these radionuclides are being studied in both relatively soluble (90SrCl2, 144CeCl3, 91YCl3, 137CsCl) and relatively insoluble forms (90Y, 91Y, 144Ce and 90Sr in fused clay particles). Initial lung or whole-body activity burdens were selected to result in early deaths due to severe lesions at the highest levels, deaths at later times with moderate to marked pathologic changes and more subtle changes such as neoplasia at the lower levels. The organs affected vary depending on the solubility and chemical characteristics of the isotope. For radionuclides inhaled in relatively soluble forms, long-term effects have been seen in the liver, skeleton, and other tissues in addition to some pulmonary effects. In contrast, long-term effects seen in the dogs exposed to relatively insoluble forms have been mainly associated with the lung and contiguous tissues. In the latter experiments, emphasis is placed on an evaluation of the influence of radiation dose rate and total dose on the resulting dose-response relationship. Over the mid-range of the relationship between radiation dose and biological response, it will be possible to compare the relationships for the several radioactive aerosols with their different radiation dose patterns. These studies with young adult dogs are complemented with comparable studies in other species (mice, Syrian hamsters) and with animals of different ages (immature, aged). This basic approach, with emphasis on factors that alter the resulting radiation dose pattern, offers the maximum likelihood of meeting the continuing, and not always predictable, needs for information on the toxicity of inhaled beta-emitting radionuclides that may be encountered in nuclear industry operations. (U.S.)

  10. Studies of the coagulation flotation of bentonite and its application to the removal of Co2+ ions and fission products, Ce and Eu

    The regions of dispersion, coagulation precipitation, coagulation flotation, and redispersion were determined for aqueous bentonite-cationic surfactant and bentonite-cationic surfactant-polyacrylamide(PAA) systems. The region of coagulation flotation was markedly extended by the addition of PAA to both the lower and higher concentration regions of the cationic surfactant, hexadecyldimethylbenzylammonium chloride(HDBAC), and to the lower concentration region of bentonite. The phenomenon of coagulation flotation was investigated in detail and was applied to the removal of Co2+ ions and nuclear fission products, 144Ce and 155Eu, from an aqueous solution. The composition of the reagents for the maximum efficiency of bentonite flotation corresponded to that of the maximum efficiency of Co2+-ion flotation. The effect of the pH on the flotation efficiency was studied in particular. The maximum flotation efficiency of 96% was obtained at pH 11 for Co2+ ions, 86% at pH 9.7 for 144Ce, and 93% at pH 10.5 for 155Eu. These radioactive elements were almost completely adsorbed on the surface of bentonite particles and were floated with them in the pH region of the maximum flotation efficiency. It was confirmed that Co2+ ions could be floated also from an extremely low concentration (10-9 mol/l) of Co2+ ions with nearly the same efficiency of flotation and with the additives in the same condition. Co2+ ions could also be effectively removed by using the step-by-step flotation, showing as high a flotation efficiency as 99.8%. (auth.)

  11. Radiocaesium forms in soil - problems of experimental determination

    A method for determining Cs form in soil is proposed based on the comparison of the experimental data on desorption of Cs radionuclide from the soil contaminated as a result of the Chernobyl accident and from the soil samples on which Cs was absorbed in laboratory (Cs was introduced in ionic form in solution). The data obtained on desorption of Cs from different soils show that Cs radionuclide is present in the soil contaminated as a result of the Chernobyl accident predominantly in an ionic form (sorbed on the different soil fractions). It has also been found that the ratio of 144Ce/137Cs radionuclides is much higher in solution than in the soil. At the same time the data on sorption of Cs and Ce radionuclides on different soils from solution 0.1M HCI + 0.1M KCI + 0.1M FeCI3 show that the sorption ability of Cs is higher than the sorption ability of Ce for all the soil types investigated. Hence, it can be assumed that the mechanism of the radionuclides extraction is desorption rather than dissolution of the matrix particles, since in the letter case extraction value of the radionuclides would not be different. The fact that the ratio of 144Ce/137Cs radionuclides in solution remains higher than in soil independent on the distance from the Chernobyl NPP indicates that the form of the radionuclides does not change with the distance from the reactor. In order to determine what type of molecules Cs radionuclide can be bound to in soil the experiments on sorption of Cs on sandy soil in the presence of humic acid in solution has been carried out. The data obtained show that the presence of humic acids has none or little effect on the sorption of Cs. This indicates that interaction of Cs radionuclides with humic acid is week and these molecules can not be responsible for binding Cs in soil. (author)

  12. Sediment-seawater distribution coefficient for radionuclides and estimation of radionuclide desorption ratio from soil in seawater

    Soil can migrate to the sea through river systems by weathering; radionuclides sorbed on the soil could migrate together to the sea. In the terrestrial environment, soil is in contact with freshwater; however, after it reaches the sea, large amounts of high-salinity seawater can contact with the soil. Consequently, some radionuclides as well as stable elements would be released from the soil. To estimate the potential extractability of radionuclides from soil, the solid/liquid distribution coefficient, Kd, was used in this study. Since there were no reported Kd values for sediments in Japanese estuarine areas, the published global fallout 60Co, 90Sr, 137Cs and 144Ce activity concentration data in estuarine areas in Japan were collated first. Data suitable for obtaining Kd for sediment-seawater values were identified. The geometric means of the Kd values for 60Co, 90Sr, 137Cs and 144Ce were 1200, 23, 200 and 2000, respectively. Using the Kd differences between the terrestrial and estuarine environments, the extractability of these radionuclides from soil to seawater was estimated. Stable element concentration data for Japanese soil and estuarine sediments were also used for comparisons. It was found that the extraction of Co and Ce from soil would be negligible; however, Sr and Cs would be partially removed from the soil to the seawater. For Cs, a preliminary study on 137Cs extractability from soil in seawater was carried out. The data supported a possible Cs extraction from Cs contaminated soil in estuarine systems, which might affect the biota living in the systems. (author)

  13. EML Surface Air Sampling Program, 1990--1993 data

    Larsen, R.J.; Sanderson, C.G.; Kada, J.

    1995-11-01

    Measurements of the concentrations of specific atmospheric radionuclides in air filter samples collected for the Environmental Measurements Laboratory`s Surface Air Sampling Program (SASP) during 1990--1993, with the exception of April 1993, indicate that anthropogenic radionuclides, in both hemispheres, were at or below the lower limits of detection for the sampling and analytical techniques that were used to collect and measure them. The occasional detection of {sup 137}Cs in some air filter samples may have resulted from resuspension of previously deposited debris. Following the April 6, 1993 accident and release of radionuclides into the atmosphere at a reprocessing plant in the Tomsk-7 military nuclear complex located 16 km north of the Siberian city of Tomsk, Russia, weekly air filter samples from Barrow, Alaska; Thule, Greenland and Moosonee, Canada were selected for special analyses. The naturally occurring radioisotopes that the authors measure, {sup 7}Be and {sup 210}Pb, continue to be detected in most air filter samples. Variations in the annual mean concentrations of {sup 7}Be at many of the sites appear to result primarily from changes in the atmospheric production rate of this cosmogenic radionuclide. Short-term variations in the concentrations of {sup 7}Be and {sup 210}Pb continued to be observed at many sites at which weekly air filter samples were analyzed. The monthly gross gamma-ray activity and the monthly mean surface air concentrations of {sup 7}Be, {sup 95}Zr, {sup 137}Cs, {sup 144}Ce, and {sup 210}Pb measured at sampling sites in SASP during 1990--1993 are presented. The weekly mean surface air concentrations of {sup 7}Be, {sup 95}Zr, {sup 137}Cs, {sup 144}Ce, and {sup 210}Pb for samples collected during 1990--1993 are given for 17 sites.

  14. Studies on influence of biological factors on concentration of radionuclides

    Biological factors influencing the concentration of radionuclides were studied from the points of uptake through digestive tract, food as pathways, and metabolic activities. The uptake of radionuclides by marine fishes through digestive tract was determined by whole body counter. 137Cs, 65Zn, 131I, 54Mn, 60Co, 85Sr, and 144Ce were used as tracers and was given with solid feed. The feed given was excreated 24 to 48 hours later in small of middle sized fishes, and 20 to 48 hours later in large sized fishes. The uptake rate of 137Cs and 65Zn was high absorption of 20 to 80 per cent, that of 131I, 60Co and 54Mn was not remarkable, and that of 85Sr and 144Ce was low absorption. The biological concentration of 137Cs through pathways of food. In fishes taking up radionuclides through contaminated food, concentration factor increased in accordance with contamination level. In addition, radionuclides with small uptake but delayed excretion and those with high concentration rate could be the factors to decide the concentration factors of marine organisms. In order to study the relationship between metabolic activities and concentration, the uptake of one-year old fishes and adult fishes, and fishes fed and those non-fed were compared. One-year fishes took up large amount of 85Sr during short period, however, concentration by metabolism in adult fishes was slow. Comparing feeding group and non-feeding group, the former showed 85Sr concentration factor of 1.5 to 2 times that of the later, and the later showed 137Cs concentration factor of 2 to 4 times that of the former. However, both uptake and excretion were rapid suggesting that taking food activated the metabolism of substances. (Kanao, N.)

  15. Preliminary studies on adsorption of Ruthenium on carbon nanotubes

    Commercial availability of carbon nanotubes (CNTs) in different forms has enhanced the research on its ability to treat effluents. Due to porous and hollow structures, large surface area, low density, high mechanical, thermal and chemical stabilities, they are being used as a potential adsorbent for removing a wide spectrum of both organic compounds and inorganic ions. Examples include: organic compounds such as dioxin, resorcinol and other phenolic derivatives, pesticides and metallic ions such as lead, copper etc. Recently they have also been applied for recovery of radionuclides such as thorium, europium, americium and plutonium from aqueous solutions. They have also been functionalised with different groups such as diglycolamide for effective adsorption of uranium. In continuation of the study, attempt has been made on the adsorption of Ruthenium on pristine carbon nanotubes. Ruthenium (Ru), a rare transition metal of platinum group elements, is typically present in common terrestrial rocks at ng g-1 level. It is also produced as a fission product in nuclear reactors. It has seven naturally occurring isotopes and thirty four radioactive isotopes. Of these radioactive isotopes, the most stable radioisotopes viz, 97Ru (t1/2=3 days), 103Ru (t1/2=40 days) and 106Ru (t1/2=386 days) are important from the environmental point of view. 106Ru, a soft beta emitter (Eβ max = 39 keV) is used for treatment of eye cancer. The highly volatile nature of Ruthenium as RuO4 (B.Pt.313 K) is an important aspect to be considered in spent nuclear fuel reprocessing facilities. Traces of these radionuclides may remain in waste solutions generated in reprocessing laboratories. Among the methods available for separation of Ruthenium, adsorption plays an important role since it eliminates the need for huge sludge handling process. A well designed sorption process with high efficiency results in a high-quality effluent after treatment which can be recycled or safely disposed. Studies on

  16. Volatility of ruthenium-106, technetium-99, and iodine-129, and the evolution of nitrogen oxide compounds during the calcination of high-level, radioactive nitric acid waste

    The nitrate anion is the predominant constituent in all high-level nuclear wastes. Formic acid reacts with the nitrate anion to yield noncondensable, inert gases (N2 or N2O), which can be scrubbed free of 106Ru, 129I, and 99Tc radioactivities prior to elimination from the plant by passing through HEPA filters. Treatment of a high-level authentic radioactive waste with two moles of formic acid per mole of nitrate anion leads to a low RuO4 volatility of about 0.1%, which can be reduced to an even lower level of 0.007% on adding a 15% excess of formic acid. Without pretreatment of the nitrate waste with formic acid, a high RuO4 volatility of approx. 35% is observed on calcining a 4.0 N HNO3 solution in quartz equipment at 3500C. The RuO4 volatility falls to approx. 1.0% on decreasing the initial HNO3 concentration to 1.0 N or lower. It is postulated that thermal denitration of a highly nitrated ruthenium complex leads to the formation of volatile RuO4, while decarboxylation of a ruthenium-formate complex leads to the formation of nonvolatile RuO2. Wet scrubbing with water is used to remove RuO4 from the off-gas stream. In all glass equipment, small amounts of particulate RuO2 are formed in the gas phase by decomposition of RuO4. The 99Tc volatility was found to vary from 0.2 to 1.4% on calcining HNO3 and HCOOH (formic acid) solutions over the temperature range of 250 to 6000C. These unexpectedly low volatilities of 99Tc are correlated to the high thermal stability limits of various metal pertechnetates and technetates. Iodine volatilities were high, varying from a low of 30% at 3500C to a high of 97% at 6500C. It is concluded that with a proper selection of pretreatment and operating conditions the 106Ru and 99Tc activities can be retained in the calcined solid with recycle of the wet scrubbing solution

  17. Exposure of the population of countries within the European Union to radioactivity in the mediterranean sea: Project MARINA-MED

    The discharges examined in the Project MARINA-MED were from nuclear installations in France, Italy and Spain, over the period 1980-1991; those from the Marcoule fuel reprocessing plant were found to contribute most of the collective dose arising from radioactivity in the Mediterranean Sea. Over 90% of beta-gamma discharges were of tritium and the remainder comprised some 80% 106Ru + 106Rh, 7% 90Sr + 90Y, 6% 137Cs, and 1% each of 134Cs, 58Co and 54Mn. The alpha emitters were dominated by 241Am, 239+240Pu and natural uranium, each representing 30% of the total. The contribution from Chernobyl had largely disappeared by 1990, except in the northern Aegean Sea, where continuing input came from the Black Sea. The corresponding exposure of the critical group in the Mediterranean Sea area from 137Cs (for an annual consumption of 73 kg fish and 35 kg shellfish) was estimated to be 7.5 μSv in 1990; the exposure of the critical group in the Black Sea area would have been about 40 μSv. These values are much lower than that estimated for 210Po, which corresponds to about 0.5 mSv. Data were obtained on catches and consumption rates of fish, crustaceans and molluscs for the relevant countries within the European Union, including import and export. Using data from the Food and Agriculture Organization of the United Nations, it was possible to extend the data to other countries bordering the Mediterranean Sea. Peak annual collective doses were estimated at less than 0.2 man·Sv for the period considered. For discharges over the entire period (1980-1991) the total collective dose commitment, truncated at 500 years, was estimated to be about 2 man·Sv. The most significant radionuclides, especially in the first few years, were found to be 106Ru (0.76 man·Sv) and 241Am (0.25 man·Sv). (author). 7 refs, 3 tabs

  18. Chromatographic purification of neutron capture molybdenum-99 from cross-contaminant radionuclides

    Technetium-99m is called the work horse, for many reasons, in nuclear medicine diagnostic purposes. It is produced as the β-decay of 99Mo radionuclide. Molybdenum-99 gel type generators are considered as a suitable alternative of the conventional chromatographic alumina columns loaded with fission molybdenum-99. 99Mo neutron-capture is cross-contaminated with radionuclides originated from activation of chemical impurities in the Mo target such 60C0, 65Zn, 95Zr, 175Hf, 181Hf, 86Rb, 134Cs, 141Ce, 152Eu, 140La,51Cr, 124Sb,46Sc, 54Mn, 59Fe and / or fast neutrons interactions with the stable isotopes of molybdenum such as 92mNb, 95Nb and 95Zr. To prevent contamination of the eluted 99mTc, successive purification methods were made. After complete dissolution of the irradiated target wrapped with thin Al foil in 5 M NaOH solution, hydrogen peroxide was added to start precipitation of Fe(OH)3. The formed Fe (III) minerals allow complete elimination of some radio contaminants from the molybdate solute such as 152Eu, 140La,141Ce, 45Mn and 92mNb in addition to partial elimination of 46Sc, 60Co and 59Fe radionuclides. The remaining supernatant was acidified by concentrated nitric acid to ph 9.5 for precipitation of Al(OH)3 with complete elimination of radio contaminants such as 95Zr 175Hf, 181Hf, 65Zn, 124Sb, 51Cr, 46Sc, 60Co and 59Fe. 134Cs and 86Rb radionuclides were not affected by precipitation of Fe(OH)3 or Al(OH)3. Chromatographic column of potassium nickel hexacyanoferrate (II) (KNHCF) has high affinity towards elimination of 134Cs and 86Rb radionuclides. Highly pure molybdate-99Mo solution was processed for preparation of zirconium molybdate gel generator with 99mTc eluate of high radionuclidic, radiochemical and chemical purity suitable for use in medical purposes.

  19. Geochemical studies of sorption and transport of radionuclides in rock media

    Four studies, which supported the goals of the WISAP Program at Battelle PNL, were undertaken by the Lawrence Livermore Laboratory during FY 1979. These were: (1) Batch K/sub d/ experiments, (2) Dynamic sorption experiments on rock cores, (3) Feasibility study for an in situ tracer test at the Climax Stock, NTS, and (4) Geochemical equilibrium code development. Only the equilibrium code development was not funded by the WISAP during FY 1979. The emphasis for the batch K/sub d/ studies was on various (15) sandstones in brine using 75Se, 85Sr, 125Sb, 137Cs, 141Ce, and 237Pu tracers. These sandstone samples were well-characterized for their physical and mineralogical nature. Complex K/sub d/ behavior was observed for the radionuclides studied but 85Sr showed K/sub d/ values near zero for all samples. Both 141Ce and 239Pu K/sub d/ values ranged from 20 to upper limits of greater than or equal to 17,000. Dynamic sorption studies were done on NTS tuff and St. Peter sandstone core using 3H, 85Sr, and /sup 95m/Tc. These radionuclides were injected as a short pulse into the rock-equilibrated water that was flowing through the core. Tracer-free water was then continually flowed through the core until elution curves for the mobile radionuclides were established. Tritium and /sup 95m/Tc both traveled through the cores at the same rate, indicating no sorption for the mobile fraction of /sup 95m/Tc (95TcO4-). Strontium-85 did not exit the tuff cores but did exit the sandstone core although the elution curves showed definite retardation relative to the movement of 3H and /sup 95m/Tc. Post-elution sectioning of the cores indicated that a fraction of the /sup 95m/Tc remained in the cores and was evenly distributed through the tuff cores. Strontium-85 showed a generally decreasing distribution from the inlet side to the outlet side of the tuff cores

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

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

  1. Recent changes in liquid radioactive waste discharges to the Irish Sea from Sellafield. Pt.1. Inputs and uptake by coastal biota

    A revised authorization to discharge liquid radioactive waste from Sellafield was granted in January 1994. The revision took account of the need to review authorizations regularly, new radiological protection criteria, and new plant developments at Sellafield. These developments included the Thermal Oxide Reprocessing Plant (THORP) and the Enhanced Actinide Removal Plant (EARP). The revised authorization included reduced discharge limits for radionuclides of greatest radiological significance, such as 106Ru, 137Cs and the transuranics. To allow operation of the new plants, increases in discharge limits were allowed for some nuclides of low radiological significance, such as 3H, 14C, 99Tc and 129I. Changes in the discharges of radionuclides with the operation of the new developments are described, together with selected results from a comprehensive programme of aquatic environmental monitoring. The trends in results of monitoring over the period 1990-95 are related to the changes in discharge patterns since the new developments commenced operation, taking account of earlier discharges from Sellafield. (author)

  2. Study of the ruthenium fission-product behavior in the containment, in the case of a nuclear reactor severe accident

    Ruthenium tetroxide is an extremely volatile and highly radio-toxic species. During a severe accident with air ingress in the reactor vessel, ruthenium oxides may reach the reactor containment building in significant quantities. Therefore, a better understanding of the RuO4(g) behaviour in the containment atmosphere is of primary importance for the assessment of radiological consequences, in the case of potential releases of this species into the environment. A RuO4(g) decomposition kinetic law was determined. Steam seems to play a catalytic role, as well as the presence of ruthenium dioxide deposits. The temperature is also a key parameter. The nature of the substrate, stainless steel or paint, did not exhibit any chemical affinities with RuO4(g). This absence of reactivity was confirmed by XPS analyses, which indicate the presence of the same species in the Ru deposits surface layer whatever the substrates considered. It has been concluded that RuO4(g) decomposition corresponds to a bulk gas phase decomposition. The ruthenium re-volatilization phenomenon under irradiation from Ru deposits was also highlighted. An oxidation kinetic law was determined. The increase of the temperature and the steam concentration promote significantly the oxidation reaction. The establishment of Ru behavioural laws allowed making a modelling of the Ru source term. The results of the reactor calculations indicate that the values obtained for 106Ru source term are closed to the reference value considered currently by the IRSN, for 900 MWe PWR safety analysis. (author)

  3. Extraction of certain radionuclides from aqueous schungite solutions

    The sorption of 90Sr, 106Ru, 137Cs, and 238Pu from aqueous solutions over a wide pH range was studied. Swelled schungite chips (Nigozero, Kondopozhsk region) (1) and schungite (Onezhsk lake) (2) were tested as sorbents. The minerals were used both untreated and after oxidation (HNO3, 1:1, contact time 1 day). The oxidation, judging from the literature, facilitates the formation of carboxylic and phenolic functional groups on the surface of the carbon-containing sorbents. The presence of such groups is responsible for the high selectivity of the sorbents for multicharged cations. Futhermore, the hydrophobicity of the schungites enormously decreases after the oxidation. The studied sorbents had an average particle size of 0.08-0.1 mm. The schungite was contacted with the solution under static conditions with periodic stirring in order to establish equilibrium. The concentration of the radionuclides was 2-4 MBq/liter. The solution volumes were 10 ml. The sorbent content was 0.01 g. The required pH was set by adding HCl or NaOH

  4. Correction factors for the ISO rod phantom, a cylinder phantom, and the ICRU sphere for reference beta radiation fields of the BSS 2

    The International Organization for Standardization (ISO) requires in its standard ISO 6980 that beta reference radiation fields for radiation protection be calibrated in terms of absorbed dose to tissue at a depth of 0.07 mm in a slab phantom (30 cm x 30 cm x 15 cm). However, many beta dosemeters are ring dosemeters and are, therefore, irradiated on a rod phantom (1.9 cm in diameter and 30 cm long), or they are eye dosemeters possibly irradiated on a cylinder phantom (20 cm in diameter and 20 cm high), or area dosemeters irradiated free in air with the conventional quantity value (true value) being defined in a sphere (30 cm in diameter, made of ICRU tissue (International Commission on Radiation Units and Measurements)). Therefore, the correction factors for the conventional quantity value in the rod, the cylinder, and the sphere instead of the slab (all made of ICRU tissue) were calculated for the radiation fields of 147Pm, 85Kr, 90Sr/90Y, and, 106Ru/106Rh sources of the beta secondary standard BSS 2 developed at PTB. All correction factors were calculated for 0° up to 75° (in steps of 15°) radiation incidence. The results are ready for implementation in ISO 6980-3 and have recently been (partly) implemented in the software of the BSS 2

  5. Radioactivity in food crops

    Drury, J.S.; Baldauf, M.F.; Daniel, E.W.; Fore, C.S.; Uziel, M.S.

    1983-05-01

    Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for /sup 137/Cs, /sup 40/K, /sup 90/Sr, /sup 226/Ra, /sup 228/Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for /sup 241/Am, /sup 7/Be, /sup 60/Co, /sup 55/Fe, /sup 3/H, /sup 131/I, /sup 54/Mn, /sup 95/Nb, /sup 210/Pb, /sup 210/Po, /sup 106/Ru, /sup 125/Sb, /sup 228/Th, /sup 232/Th, and /sup 95/Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g/sup -1/ (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins.

  6. The transfer of radionuclides from saltmarsh vegetation to sheep tissues and milk

    Radionuclides released into the Irish Sea by the Sellafield reprocessing plant are deposited onto tide-washed pastures along the western coast of the United Kingdom. Many of these pastures are grazed by sheep or cattle. This paper describes a controlled feeding study, in which saltmarsh vegetation harvested from close to the Sellafield plant, was fed to lambs and adult female sheep for a period of 8 weeks. Activity concentrations of 60Co, 95Nb, 106Ru, 134Cs, 137Cs, 238Pu, 239,240Pu and 241Am were determined in edible tissues and transfer parameters estimated. The activity concentrations of some of the radionuclides will not have been in equilibrium with those in the diet. Nevertheless, the study was reasonably realistic in terms of agricultural management as the period of the study was similar to that for which lambs graze on the saltmarshes. A field study to determine the activity concentrations of 137Cs and 239,240Pu in the milk of ewes grazing a saltmarsh close to Sellafield is also described

  7. Radiation Protection in Brachytherapy. Report of the SEFM Task Group on Brachytherapy; Proteccion radiologica en Braquiterapia. Informe del grupo de trabajo de Braquiterapia de la SEFM

    Perez-Calatayud, J.; Corredoira Silva, E.; Crispin Contreras, V.; Eudaldo Puell, T.; Frutos Baraja, J. de; Pino Sorroche, F.; Pujades Claumarchirant, M. C.; Richart Sancho, J.

    2015-07-01

    This document presents the report of the Brachytherapy Task Group of the Spanish Society of Medical Physics. It is dedicated to the radiation protection aspects involved in brachytherapy. The aim of this work is to include the more relevant aspects related to radiation protection issues that appear in clinical practice, and for the current equipment in Spain. Basically this report focuses on the typical contents associated with high dose rate brachytherapy with {sup 1}92Ir and {sup 6}0Co sources, and permanent seed implants with {sup 1}25I, {sup 1}03Pd and {sup 1}31Cs, which are the most current and widespread modalities. Ophthalmic brachytherapy (COMS with {sup 1}25I, {sup 1}06Ru, {sup 9}0Sr) is also included due to its availability in a significant number of spanish hospitals. The purpose of this report is to assist to the medical physicist community in establishing a radiation protection program for brachytherapy procedures, trying to solve some ambiguities in the application of legal requirements and recommendations in clinical practice. (Author)

  8. Field and model investigations of external gamma dose rates along the Cumbrian coast, NW England.

    McDonald, P; Bryan, S E; Hunt, G J; Baldwin, M; Parker, T G

    2005-03-01

    A survey of the contribution to external dose from gamma rays originating from intertidal sediments in the vicinity of the British Nuclear Group Sellafield site showed that the major anthropogenic contributions were due to (137)Cs and (60)Co. At some sites, traces of other anthropogenic radionuclides were detected, namely (106)Ru, (125)Sb, and (154)Eu. The proportions of fine grained material (Drigg Barn Scar and Whitehaven Coal Sands sites, which had their own unique characteristics. The highest (60)Co activity concentrations in this study were detected at Drigg Barn Scar. These relatively high activity concentrations of (60)Co were due to the presence of (60)Co in mussels and barnacles, hence upsetting the fine sediment relationships used in previous dose calculations. Whitehaven Coal Sands was unusual in that it contained higher levels of radionuclides than would be expected in sandy sediment. The mineralogy of these sediments was the controlling factor on (137)Cs binding, rather than the proportion of fine grained material. By adjusting the effective fine grained sediment proportions for calculations involving (60)Co and (137)Cs at Drigg Barn Scar and Whitehaven Coal Sands respectively, the CUMBRIA77/DOSE77 model predictions could be improved upon significantly for these sites. This work highlights the influence of particle size and sediment composition on external dose rate calculations, as well as the potential for external dose contributions from biota. PMID:15798279

  9. Field and model investigations of external gamma dose rates along the Cumbrian coast, NW England

    A survey of the contribution to external dose from gamma rays originating from intertidal sediments in the vicinity of the British Nuclear Group Sellafield site showed that the major anthropogenic contributions were due to 137Cs and 60Co. At some sites, traces of other anthropogenic radionuclides were detected, namely 106Ru, 125Sb, and 154Eu. The proportions of fine grained material (60Co activity concentrations in this study were detected at Drigg Barn Scar. These relatively high activity concentrations of 60Co were due to the presence of 60Co in mussels and barnacles, hence upsetting the fine sediment relationships used in previous dose calculations. Whitehaven Coal Sands was unusual in that it contained higher levels of radionuclides than would be expected in sandy sediment. The mineralogy of these sediments was the controlling factor on 137Cs binding, rather than the proportion of fine grained material. By adjusting the effective fine grained sediment proportions for calculations involving 60Co and 137Cs at Drigg Barn Scar and Whitehaven Coal Sands respectively, the CUMBRIA77/DOSE77 model predictions could be improved upon significantly for these sites. This work highlights the influence of particle size and sediment composition on external dose rate calculations, as well as the potential for external dose contributions from biota

  10. Assessment of the potential for radionuclide migration from a nuclear-explosion cavity

    The source term for radionuclides in the region of the Cambric nuclear explosion has been determined. Drillback cores were obtained and analyzed, and water was pumped from several vertical zones and analyzed. Most of the radioactivity produced in the test was found to be retained in the fused debris with only low concentrations in the water which had been in contact with the debris for nearly ten years. Most of the radioactivity and the highest specific activities of all radionuclides were found to be in the region of the original explosion cavity. No activity was found 50 m below the cavity. Water from the region of highest radioactivity at the bottom of the cavity contained only tritium and 90Sr at levels higher than the recommended concentration guides for drinking water in uncontrolled areas. During nearly six years of pumping from a satellite well located 91 m from the Cambric cavity, only tritium 85Kr have been positively identified in water removed from this well, although there is some evidence for the possible migration of minute amounts of 106Ru. These results are consistent with laboratory studies which indicate that, in general, radionuclide sorption is sufficiently high to preclude the migration of such nuclides from the original cavity to the satellite well in the near future

  11. Radioactivity in food crops

    Published levels of radioactivity in food crops from 21 countries and 4 island chains of Oceania are listed. The tabulation includes more than 3000 examples of 100 different crops. Data are arranged alphabetically by food crop and geographical origin. The sampling date, nuclide measured, mean radioactivity, range of radioactivities, sample basis, number of samples analyzed, and bibliographic citation are given for each entry, when available. Analyses were reported most frequently for 137Cs, 40K, 90Sr, 226Ra, 228Ra, plutonium, uranium, total alpha, and total beta, but a few authors also reported data for 241Am, 7Be, 60Co, 55Fe, 3H, 131I, 54Mn, 95Nb, 210Pb, 210Po, 106Ru, 125Sb, 228Th, 232Th, and 95Zr. Based on the reported data it appears that radioactivity from alpha emitters in food crops is usually low, on the order of 0.1 Bq.g-1 (wet weight) or less. Reported values of beta radiation in a given crop generally appear to be several orders of magnitude greater than those of alpha emitters. The most striking aspect of the data is the great range of radioactivity reported for a given nuclide in similar food crops with different geographical origins

  12. Contribution to investigations on trace elements transport in the Channel: spatial distribution of industrial tracers in mytilus edulis and fucus serratus

    The distribution of artificial tracers - gamma emitters - has been studied in biological indicator species, mussels and fucus, along the french and english Channel shores in order to gain a better knowledge of trace elements transports in the Channel coastal areas. The main conclusions are supplied by 106Ru-Rh and 60Co. Extension of species labelling is larger eastwards than westwards, and the differences recorded between french and english shores show weak exchanges between south and north Channel; in the norman-breton gulf and in the Seine river bay, the distribution of radioactive tracers demonstrates complex current processes. The results are compared to the hydrodynamical studies carried out through models and follow-up of radioactive tracers in sea-water. Particular processes have been observed, corresponding to areas where the decay gradient from the source term is not respected (western Cotentin shore, western Seine Bay, Caux aerea). They are discussed in relation with fresh - sea water mixing, current and physico-chemical problems

  13. The present state of research on the vitrification of concentrated solutions of fission products (1962)

    The present report gives the actual point of studies on vitrification of concentrated solutions of fission products. An active cell, giving glasses in crucibles, permitted to study various glass compositions. The leaching rate from the glass raises 1 to 2 10-7 g of glass/cm2/day. Activity loss by volatility during vitrification remains weak and often below 0.1 per cent of total activity. Off gas cleaning is made easier by presence of filter which is compound of granules including iron oxide. After saturation the content of this filter can be melt. Moreover different processes are in experimentation for a more important production. Daily 72 liters of solution containing tracer activity are treated in a continuous calcination and vitrification plant. The loss in 106Ru is still important and a modification of installation has been necessary. A pot vitrification plant is in study. In order to reduce cost of processing the possibility to pour glass after melting is actuality in study. A production set of very active glass is also in project. (authors)

  14. Study of charge collection and noise in non-irradiated and irradiated silicon detectors

    Leroy, C; Dezillie, B; Glaser, M; Lemeilleur, F; Trigger, I

    1996-01-01

    The large collection and noise were studied in non-irradiated and irradiated silicon detectors as a function of temperature (T), shaping time (0) and fluence , up to about 1,2 x 10(14) protons per cm2 for minimum-ionizing electrons yielded by a 106 Ru source. The noise of irradiated detectors is found to be dominted for short shaping times (¾50ns) by a series noise compo- nent, while for longer shaping times („80ns) a parallel noise component (correlated with the reverse current) prevails. For non-irradiated detectors, where the reverse current is three orders of magnetude smaller compared with irradiated detectors, the series noises dominates over the whole range of shaping times investigated (20-150ns). A signal degradation is observed for irradiated detectors. However, the signal ca be distinguished from noise, even after a fluence of about 1.2 x10(14) protons per cm2, at a temperature of 6øC and with a shaping time tipical of rge LHC inter-bunch crossing time (20-30ns). The measurements of the signal a...

  15. Study of charge collection and noise in non-irradiated and irradiated silicon detectors

    Leroy, C. [Montreal Univ., PQ (Canada); Bates, S. [CERN, ECP, CH-1211 Geneva (Switzerland); Dezillie, B. [CERN, ECP, CH-1211 Geneva (Switzerland); Glaser, M. [CERN, ECP, CH-1211 Geneva (Switzerland); Lemeilleur, F. [CERN, ECP, CH-1211 Geneva (Switzerland); Trigger, I. [Montreal Univ., PQ (Canada)

    1997-04-01

    Charge collection and noise were studied in non-irradiated and irradiated silicon detectors as a function of temperature (T), shaping time ({theta}) and fluence ({Phi}), up to about 1.2 x 10{sup 14} protons cm{sup -2}, for minimum ionizing electrons yielded by a {sup 106}Ru source. The noise of irradiated detectors is found dominated for short shaping times ({theta}{<=}50 ns) by a series noise component while for longer shaping time ({theta}{>=}80 ns) a parallel noise component (correlated with the reverse current) prevails. For non-irradiated detectors, where the reverse current is three orders of magnitude smaller compared with irradiated detectors, the series noise dominates over the whole range of shaping times investigated (20-150 ns). A signal degradation is observed for irradiated detectors. However, the signal can be distinguished from noise, even after a fluence of about 1.2 x 10{sup 14} protons cm{sup -2}, at a temperature of 6 C and with a shaping time typical of LHC inter-bunch crossing time (20-30 ns). The measurement of the signal as a function of voltage shows that irradiated detectors depleted at 50% of the full depletion voltage can still provide a measurable signal-to-noise ratio. (orig.).

  16. Environment surveillance

    The Cogema group involved in the nuclear fuel cycle from the uranium extraction to the reprocessing of spent fuels and the recycling of re-usable energy materials, performs periodical controls of radioactivity levels in the environment close to its facilities. At Cogema-La Hague, 80000 analyses were performed on 25000 samples taken at 820 different sites in the vicinity of the facility in 1997. These controls concern different elements of the terrestrial and maritime environments (surface and ground waters, rain water, plants, beach sand, marine sediments, marine fauna and flora). After a brief presentation of natural and artificial radioactivity, this brochure presents the results of the measurements performed by Cogema-La Hague (alpha- and beta-activity, tritium, 7Be, 40K, 241Am, 137Cs, 125Sb, 129I, 90Sr, 106Ru, 60Co, 110mAg) in air, surface waters, grass, milk, coastal waters, algae, molluscs and fishes. A special chapter is devoted to the presentation of tritium (origin, metabolism, toxicity, concentration in effluents). (J.S.)

  17. Electrochemical treatment of liquid wastes

    Hobbs, D.T. [Savannah River Technology Center, Aiken, SC (United States)

    1997-10-01

    Under this task, electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This technology targets the (1) destruction of nitrates, nitrites and organic compounds; (2) removal of radionuclides; and (3) removal of RCRA metals. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale reactor, and (5) analysis and evaluation of test data. The development program team is comprised of individuals from national laboratories, academic institutions, and private industry. Possible benefits of this technology include: (1) improved radionuclide separation as a result of the removal of organic complexants, (2) reduction in the concentrations of hazardous and radioactive species in the waste (e.g., removal of nitrate, mercury, chromium, cadmium, {sup 99}Tc, and {sup 106}Ru), (3) reduction in the size of the off-gas handling equipment for the vitrification of low-level waste (LLW) by reducing the source of NO{sub x} emissions, (4) recovery of chemicals of value (e.g. sodium hydroxide), and (5) reduction in the volume of waste requiring disposal.

  18. Electrochemical treatment of liquid wastes

    Under this task, electrochemical treatment processes are being evaluated and developed for the destruction of organic compounds and nitrates/nitrites and the removal of other hazardous species from liquid wastes stored throughout the DOE complex. This technology targets the (1) destruction of nitrates, nitrites and organic compounds; (2) removal of radionuclides; and (3) removal of RCRA metals. The development program consists of five major tasks: (1) evaluation of electrochemical reactors for the destruction and removal of hazardous waste components, (2) development and validation of engineering process models, (3) radioactive laboratory-scale tests, (4) demonstration of the technology in an engineering-scale reactor, and (5) analysis and evaluation of test data. The development program team is comprised of individuals from national laboratories, academic institutions, and private industry. Possible benefits of this technology include: (1) improved radionuclide separation as a result of the removal of organic complexants, (2) reduction in the concentrations of hazardous and radioactive species in the waste (e.g., removal of nitrate, mercury, chromium, cadmium, 99Tc, and 106Ru), (3) reduction in the size of the off-gas handling equipment for the vitrification of low-level waste (LLW) by reducing the source of NOx emissions, (4) recovery of chemicals of value (e.g. sodium hydroxide), and (5) reduction in the volume of waste requiring disposal

  19. A study of gamma-emitting radionuclides present into the sediments and algae of the ''Baie de l'Orne'' (Central Normandy Coast) collecting during the years 1980 - 1982

    The present status of some environmental effects of existing sources of gamma-emitting radionuclides, along the Central part of the Normandy Coast (Calvados shores and river Orne mouth) was determined. A systematic study was made on the behaviour of the marine sediments and brown alga 'Laminaria digitata' with regard to their properties as indicators of radioactive contamination. Marine sediments were collected into the river Orne at fixed locations and into the sea in and around the estuary from 1977 to 1982. Algae samples were picked up along the coast from 1980 to 1982, mostly on the western part of the Orne estuary. Dosimetry techniques employed have produced accurate and reliable results, despite the very low levels of activity involved. Gamma-emitting radionuclides present in the environment (chiefly 106Ru, 137Cs, 95Zr) were identified and measured. Their behaviour into the marine sediments and into Laminaria Digitata were determined. This study provides evidence on the presence of numerous gamma-emitting radionuclides into the marine environment of the Central part of the Normandy coast, but, altogether with very low levels of radioactivity

  20. Beta Radiation Exposure of Personnel in Radiosynovectomy and at the Production of Eye Application

    Full text: Beta radionuclides are increasingly used in nuclear medicine therapy. In a study of exposure at working places with supposed enhanced radiation risk the followings are monitored: 1. Production of eye applicators (106Ru/106Rh) for therapy of intraocular tumours. During the processes radionuclides are used in sealed and unsealed form. 2. Radiosynovectomy (RSO). This therapy is often used in treatment of inflammatory joint disease. The radionuclides 169Er, 186Re and 90Y are applied in form of radioactive solutions. A complex of problems has to be solved here: Handling of high activities (several GBq per day), very small distances between source and skin, high risk of skin contamination, unsatisfactory dose measurement techniques. In our investigations high sensitive thin thermoluminescence dosimeters (LiF:Mg,Cu,P) were used to determine the skin dose of the hands especially fingertips during preparation and application of the radioactive substances at several institutions. During production of eye applicators we found hand doses essentially below the annual limit. But direct radiation at RSO caused more than 100 mSv at the fingertips per working day in some cases. Even higher doses (more than 50% of the annual limit for skin during a working day) were caused by contamination of the hands. By use of manipulators, wearing of appropriate protection gloves and by improvement of directions for work, the radiation exposure could be reduced dramatically. Consequences for individual beta dosimetry and with respect to license of use of beta radionuclides are discussed. (author)

  1. Assessment of Cesium, Iodine, Strontium and Ruthenium isotopes behaviour in urban areas, after contamination from accidental release

    The exposures of urban populations to the radiation derived from the deposition, after accidental atmospheric releases, of 137 Cs, 134 Cs, 129 I, 131 I, 133 I, 89 Sr, 103 Ru and 106 Ru were assessed, using the integrated system for the evaluation of environmental radiological impact in emergency situations, developed by the Instituto de Radioprotecao e Dosimetria (IRD)/Comissao Nacional de Energia Nuclear (CNEN). These radionuclide are fission products likely to be emitted in the occurrence of severe nuclear reactor accidents. Their environmental behaviour in urban areas, due to their deposition in soil, in urban surfaces and in vegetable-garden food products, such as leafy and non-leafy vegetables, were analyzed, and dose assessments at the short, medium and long terms were performed, with an without the application of protective measures for reduction of doses. Simulations of unitary initial deposition for each radionuclide and of two different potential accidents involving water reactors (PWR), with different source terms and distinct deposition for each radionuclide, were performed. Results were analyzed on the basis of relative relevance of radionuclides and pathways for the exposure of members of the public, as a function of age and time after the release. It was also performed an assessment of the effectiveness of protective measures as a function of the moment of their implementation. (author)

  2. Estimated radiological doses to the maximumly exposed individual and downstream populations from releases of tritium, strontium-90, ruthenium-106, and cesium-137 from White Oak Dam

    Concentrations of tritium, 90Sr, 106Ru, and 137Cs in the Clinch River for 1978 were estimated by using the known 1978 releases of these nuclides from the White Oak Dam and diluting them by the integrated annual flow rate of the Clinch River. Estimates of 50-year dose commitment to a maximumly exposed individual were calculated for both aquatic and terestrial pathways of exposure. The maximumly exposed individual was assumed to reside at the mouth of White Oak Creek where it enters the Clinch River and obtain all foodstuffs and drinking water at that location. The estimated total-body dose from all pathways to the maximumly exposed individual as a result of 1978 releases was less than 1% of the dose expected from natural background. Using appropriate concentrations of to subject radionuclides diluted downstream, the doses to populations residing at Harriman, Kingston, Rockwood, Spring City, Soddy-Daisy, and Chattanooga were calculated for aquatic exposure pathways. The total-body dose estimated for aquatic pathways for the six cities was about 0.0002 times the expected dose from natural background. For the pathways considered in this report, the nuclide which contributed the largest fraction of dose was 90Sr. The largest dose delivered by 90Sr was to the bone of the subject individual or community

  3. Development of a method for analyzing traces of ruthenium in plant materials and determination of the transfer factors soil/plant for ruthenium compounds from reprocessing plants

    In an artificial humous and sandy soil spiked with 106Ru as RuO2 and RuCl3, pasture grass was grown under artificial illumination in our laboratory. The amounts of ruthenium taken up by the plants were determined by γ-spectrometry. For open-air investigations with pasture grass, wheat and potatoes inactive ruthenium(III) chloride and ruthenium nitrosylchloride were used. Ruthenium was determined by electrothermal atomic absorption spectrometry (ETAAS) after destroying the organic material and concentrating the solution. The concentration and chemical form of the ruthenium exert an unimportant influence on the transfer factor. For the pasture-grass, the stems of wheat and the weed of potatoes it amounts to 0.00005 to 0.0015, for the ear of wheat to about 0.00005. In peeled potatoes there was no ruthenium detectable, therefore the limit of detection leads to a transfer factor ≤ 0.00001. So it is evident that ruthenium is little available for the roots of the plants. In the event of an accident in a nuclear plant the uptake of radioactive ruthenium by roots has only negligible radioecological consequences. This applies even if 50 years of ruthenium enrichment in the soil are assumed. (orig./RB)

  4. Chemical isotopic analysis of fission products in PWR-MOX spent fuels and computational evaluation using JENDL, ENDF/B, JEF, and JEFF

    A chemical isotopic analysis of high-burn-up MOX spent fuels with a burn-up of 45 MWd/kgHM was carried out to accumulate nuclide composition data. Furthermore, computational analysis was performed using the integrated burn-up calculation code system SWAT. The differences between the amounts of fission products obtained by the chemical isotopic analysis and SWAT calculation using JENDL-3.2, JENDL-3.3, ENDF/B-VI.5, ENDF/B-VI.8, JEF-2.2, and JEFE-3.0 were evaluated as the ratios of the calculated values to the experimental ones (C/E ratios). The fission products such as 88Sr, 90Sr, 106Ru, 133Cs, 134Cs, and 135Cs, which are gamma and decay heat sources, neutron absorption nuclides, or burn-up indicators in spent fuels, were further investigated to improve their C/E ratios using the simplified burn-up chains of fission products using JENDL-3.3; consequently, the correction values for the fission yields or capture cross sections of the fission products were estimated using sensitivity coefficients. The C/E ratios for 154Eu, 155Eu, 154Gd, 155Gd, and 156Gd markedly differed among libraries. The reason for this difference was also discussed using the sensitivity coefficient and capture cross section of each fission product, which is in their main sensitive production paths. (author)

  5. Specific activity and activity ratios of radionuclides in soil collected about 20 km from the Fukushima Daiichi Nuclear Power Plant: Radionuclide release to the south and southwest

    Tagami, Keiko, E-mail: k_tagami@nirs.go.jp; Uchida, Shigeo; Uchihori, Yukio; Ishii, Nobuyoshi; Kitamura, Hisashi; Shirakawa, Yoshiyuki

    2011-10-15

    Soil samples at different depths (0-2, 5-7 and 10-12 cm) were collected from J Village, about 20 km south of Fukushima Daiichi Nuclear Power Plant (FNPP) to determine their radionuclide specific activities and activity ratios. The concentrations and activity ratios of {sup 131}I, {sup 134,} {sup 136,} {sup 137}Cs and {sup 129m}Te were obtained, but only trace amounts of {sup 95}Nb, {sup 110m}Ag and {sup 140}La were detected which were too low to provide accurate concentrations. Radionuclides such as {sup 95}Zr, {sup 103,} {sup 106}Ru and {sup 140}Ba that were found in Chernobyl fallout, were not found in these soil samples. This suggests that noble gasses and volatile radionuclides predominated in the releases from FNPP to the terrestrial environment. The average activity ratios of {sup 131}I/{sup 137}Cs, {sup 134}Cs/{sup 137}Cs, {sup 136}Cs/{sup 137}Cs and {sup 129m}Te/{sup 137}Cs were 55, 0.90, 0.22 and 4.0 (corrected to March 11, 2011) in the 0-2 cm soil samples of April 20 and 28, 2011.

  6. Specific activity and activity ratios of radionuclides in soil collected about 20 km from the Fukushima Daiichi Nuclear Power Plant: Radionuclide release to the south and southwest

    Soil samples at different depths (0-2, 5-7 and 10-12 cm) were collected from J Village, about 20 km south of Fukushima Daiichi Nuclear Power Plant (FNPP) to determine their radionuclide specific activities and activity ratios. The concentrations and activity ratios of 131I, 134,136,137Cs and 129mTe were obtained, but only trace amounts of 95Nb, 110mAg and 140La were detected which were too low to provide accurate concentrations. Radionuclides such as 95Zr, 103,106Ru and 140Ba that were found in Chernobyl fallout, were not found in these soil samples. This suggests that noble gasses and volatile radionuclides predominated in the releases from FNPP to the terrestrial environment. The average activity ratios of 131I/137Cs, 134Cs/137Cs, 136Cs/137Cs and 129mTe/137Cs were 55, 0.90, 0.22 and 4.0 (corrected to March 11, 2011) in the 0-2 cm soil samples of April 20 and 28, 2011.

  7. Results of radioactivity measurements in French coastal waters during 1985

    Various sampling networks for the environmental monitoring of levels from radioactive waste releases from french nuclear plants have been set up by the Departement de Protection Sanitaire (DPS) since 1983. In 1985, various marine and freshwater biological indicators were collected regularly on the Channel, Atlantic and Mediterranean shores and at the level of the lower Rhone river. As in the previous years, the results showed the prevailing effects of the releases from the LA HAGUE reprocessing plant on the Channel and of the Rhone waters on the Mediterranean sea. Measurements at the level of the lower Rhone showed a clear labelling of the Rhone river waters by 106Ru. The monitoring of ruthenium levels in various biological indicators from the Mediterranean shore supplied a good representation of the marine areas affected by the Rhone river. At the stations with the highest levels, the sanitary consequence of man-made radionuclides remained low, representing a fraction in the range of 10-5 of the dose limit recommended by the International Commission on Radiological Protection

  8. Migration of technetium-99 in the Nevada Test Site aquifer

    The Hydrology Radionuclide Migration Experiment is measuring the migration of radionuclides from the site of an underground nuclear explosion at the Nevada Test Site. The Cambric event, detonated in 1965, was chosen as the initial experimental site. By 1974, water had returned to its pre-shot level allowing soluble radionuclides to be leached into the water. A re-entry well (RNM-1) was dug into the original cavity to take core and water samples. A satellite well (RNM-2S) was placed 91 meters from the Cambric cavity. Pumping water from this well has induced an artificial gradient which has allowed soluble radionuclides to migrate. Tritium (HTO) has been observed in the RNM-2S water; its elution has been well characterized. Other radionuclides have been monitored in this water: 36Cl, 85Kr, 129I, and 106Ru. The authors have recently measured 99Tc at the 10--20 femtogram/liter level. Technetium appears to be migrating slower than 36Cl and possibly a little faster than tritium

  9. Radioactive substance in the Japanese environment

    The sources of environmental radiation exposure, the features of radioactive substances, the effect of radioactive nuclides to mankind by their intake and so on are explained. The distribution and variation of radioactive substances around Chernobyl Nuclear Power Station and in USSR due to the accident are shown. The worldwide contamination centering around Europe is also shown. In Japan, the rise of radioactivity level due to the accident was small. The radioactive substances which seemed to be originated from the accident were detected from May 3, 1986, and as the nuclides, I-131, Cs-137, Cs-134, Sr-90, Ru-106, Ru-103, Te-132, Ba-140, La-140, Ce-144 and so on were found. Sr-90 somewhat rose in May, but in June, it returned to the state in April, and the level of Cs-137 was somewhat high until July, but returned to the state in April around September. The concentration of radioactive nuclides in foods in Japan was low. The concentration in milk became the maximum in the middle of May, though the maximum fallout occurred on May 3 - 5. As the natural radioactive nuclides in Japan, 110,000 pCi of K-40 and 70,000 kCi of C-14 are contained in a whole body. (Kako, I.)

  10. Thermal stability of the C106 dye in robust electrolytes

    Lund, Torben; Phuong, Nguyen Tuyet; Pechy, Peter; Zakeeruddin, Shaik M.; Grätzel, Michael

    Thermal stability of the C106 dye in robust electrolytes. We have investigated the thermal stability and degradation chemistry of the ruthenium dye C106 (Figure 1) at 80 ◦C in the “robust” electrolyte “B” comprised of 1.0 M DMII, 0.03 M I2, 0.5 M NBB, and 0.1 M GuNCS in 3-methoxypropionitrile (3......-MPN) introduced by Gao et al. in 2008. [1]. Figure 1 Thermal degradation of C106 bound to TiO2 at 80 ºC in dark as a function of heating time. ● C106 = RuLL´(NCS)2 ■ RuLL´(NCS)(NBB)+ ▲ RuLL´(NCS)(3-MPN)+ The C106 dye was attached to the surface of TiO2 nano-particles and stable colloidal solutions of...... the particles were prepared in electrolyte mixture B. The solutions were thermally treated at 80 ◦C for 0-2000 hours followed by dye extraction and analysis by HPLC coupled to UV/Vis and electro spray mass spectrometry [2]. Figure 1 shows the concentration profiles of C106 samples prepared under...

  11. The Cambric migration experiment: A summary report

    The Cambric migration experiment was undertaken in 1974 to provide data concerning the migration of radionuclides away from the site of a nuclear test where there is an induced hydraulic gradient. First, the distribution of radioactive isotopes around the site of the Cambric explosion was investigated by analysis of samples recovered from a hole drilled through the nuclear debris. Then water was pumped from a well, located 91 m away, to induce flow from the nuclear explosion site. Analyses of water samples showed that the migration velocity of tritium, 16Cl, 85Kr, 99Tc, 106Ru, and 129I was nearly the same as that of the moving water, from the explosion site to the pumped well. Less than 0.5% of the total 90Sr and 0.0003% of the total 137Cs accompanied the tritium to the pumped well, although both isotopes appear to have migrated away from the source zone to some extent. The concentration of 239Pu at the pumped well was below the detection limit of 106 atoms/m ell in water collected at the time of peak tritium concentration. Peak tritium concentration in the pumped water occurred when 5,000,000 m3 had been pumped

  12. Radioactive decontamination methods and their effectiveness as a function of terrain

    A large area of rugged terrain on the Nevada Test Site was contaminated following a spill of radioactively contaminated drilling mud. The contamination was shown to consist of 103Ru and 106[Ru-Rh] with total estimated activity at release time of 38 and 6 Ci, respectively. Several decontamination methods were used and their effectiveness assessed by determining the fraction of radioactivity remaining (FR) following each. In flat areas, the front end loader was by far the most efficient method, removing large quantities of dirt in relatively short periods of time. FRs of 10-22 were achieved. In canyon areas, flushing with water was most effective on rocky surfaces with FRs of 10-3, while shoveling and bagging in evaporated mud collection ponds worked well and resulted in FRs of 10-2. The FR in rocky cracks was about 10-1 following flushing with water. In Locations where radioactive mud/water had not penetrated the ground surface to more than 1-2in., such as fine grain, flat compact dirt, vacuuming was very effective achieving FRs of 10-3. However, unless the contaminated area was very small (e.g. dropping from front end loading operations), vacuuming was too slow to be of practical value. Under the supervision of experienced radiation monitors, the radioactive mud spill area was safely cleaned up using, for the most part, standard earth moving equipment and personnel untrained in decontamination procedures. (author)

  13. Performance evaluation of of caesium, iodine, strontium and ruthenium isotopes in urban areas after contamination by accidental release

    The exposures of urban populations to the radiation derived from the deposition, after accidental atmospheric releases, of I37Cs, 134Cs, 129I, 131I, 133I, 89Sr, l03Ru and 106Ru were assessed, using the integrated system for the evaluation of environmental radiological impact in emergency situations (SIEM), developed by the Instituto de Radioprotecao e Dosimetria (IRD) / Comissao Nacional de Energia Nuclear (CNEN). These radionuclides are fission products likely to be emitted in the occurrence of severe nuclear reactor accidents. Their environmental behaviour in urban areas, due to their deposition in soil, in urban surfaces and in vegetable-garden food products, such as leafy and non-leafy vegetables, were analyzed, and dose assessments at the short, medium and long terms were performed, with and without the application of protective measures for reduction of doses. Simulations of unitary initial deposition for each radionuclide and of two different potential accidents involving pressurized water reactors (PWR), with different source terms and distinct deposition for each radionuclide, were performed. Results were analyzed on the basis of the relative relevance of radionuclides and pathways for the exposure of members of the public, as a function of age and time after the release. It was also performed an assessment of the effectiveness of protective measures as a function of the moment of their implementation. (author)

  14. The application of an environmental radiological impact integrated evaluation system in emergency situations for the radiological exposure evaluation of urban areas population

    An integrated computational system for environmental radiological impact assessment in emergency situations has been developed at IRD/CNEN. This system has been used, in this paper, to assess the exposure to members of the public, in a urban area, after the release to the environment of radionuclides that may be relevant after a severe nuclear accident with a PWR reactor. Doses were calculated, for the short and long terms, for the radionuclides 137 Cs, 134 Cs, 129 I, 131 I, 133 I, 89 Sr, 90 Sr, 103 Ru and 106 Ru. The study also simulates the application of some protective measures aiming the estimate of dose reduction, taking into account the moment of their implementation. The starting point for the simulation is the activity deposited on the ground and on urban surfaces and includes the ingestion of home grown products, such as green vegetables, legumes and chicken. This paper is part of a program to derive tools for planning of emergency attendance, taking into account the present knowledge about the fate of radionuclides delivered to the environment, based on estimates of exposure, for the protection of population in tropical climate environments. (author)

  15. Study on the method for determination of the nuclear fuel elements burnout by the quantitative analysis of 148Nd

    The scope of present work to study the precision and accuracy of a method for separation and determination of the.stable isotope 148Nd. The extraction chromatography and ion exchange techniques were used for the separation of fission products and uranium. Kieselguhr and di(2-ethyl-hexyl)phosphoric acid were used as inert support and stationary phase, respectively, in the steps of the separation procedure where the extraction chromatography technique was applied, and anionic resin mixed with Pb02 was used for the ion exchange operation. The behaviour of each element in the separation procedure was verified by means of radioactive tracers, namely, 147Nd, 141Ce and 137Cs. Use was made of the thermal neutron activation analysis in order to determine the 148Nd percentage recovered after the separation procedure was run. On the other hand, the radioactive isotope 147Nd was used to find chemical yield achieved for the separation procedure. Student's t test applied to verify the accuracy of the method used whose acceptability was verified by using the criterion recommended by McFarren and also taking into account the suggestion proposed by Eckschlager. The precision of the method was verified by means of the standard deviation of the several determinations. (author)

  16. Effects of vasoactive intestinal peptide on vascular conductance are unaffected by anesthesia

    In rats anesthetized with ketamine and pentobarbital (KET/PB), vasoactive intestinal peptide (VIP) increases vascular conductance (VC) in the salivary gland, pancreas, and thyroid gland, whereas no changes in VC are observed in a number of other organs. Because anesthesia may alter the responsiveness of physiological systems, we compared the effects of VIP on organ VC in conscious or anesthetized rats. Chronically catheterized rats were studied in the conscious state or 30 min after induction of anesthesia with KET/PB, isoflurane, or Inactin. Blood flows were measured by the reference sample version of the radioactive microsphere (MS) technique using two MS injections (141Ce-MS/85Sr-MS). Mean arterial blood pressure was monitored and used in the calculation of VC. Organ VCs were similar under basal conditions in conscious and anesthetized rats. VIP infusion caused systemic hypotension and increased VCs in the salivary gland, pancreas, and thyroid gland, and these responses were largely unaffected by anesthesia. These results indicate that the anesthetics used do not alter basal VC or the responsiveness of the vasculature to exogenous VIP

  17. Application of inorganic exchangers in fission product separation

    Synthetic ion exchangers ammonium phosphomolybdate/phosphotungstate (APW), polyantimonic acid (PA) and manganese dioxide have been investigated for separation of cesium, strontium and cerium respectively with a view to their use in fission product separation. Their breakthrough capacities and elution characteristics were determined using 137Cs, sup(85,89)Sr and 141Ce as tracers. Results indicate that : (1) Cs adsorbed on APW is easily eluted with 3M NH4NO3 at a temperature of 500C with an overall yield of 90% in about 10 column volumes, (2) strontium adsorbed on PA is completely eluted by 1M AgNo3 + 8M HNO3 at room temperature and (3) manganese sulphate (1 mg/ml) + 3M HNO3 elutes cerium adsorbed on manganese dioxide. Column characteristics (exchange capacity and flow rate) are not affected upto 6 cycles of sorption-elution. Based on these findings, a scheme of separation of fission products from waste solution is proposed. Pu uptake on PA is found to be governed by U/Pu ratio in the solution. The ratio > 104 inhibits the uptake. Pu on PA is eluted in 10 column volumes by 0.01M ascorbic acid +2M nitric acid. The exchange PA can be used over 20 cycles of sorption-elution. (M.G.B.)

  18. Solvent extraction study on the separation of molybdenum-99 and uranium in sulfuric acid solution by tri-n-octylamine in kerosene

    The basic extraction study on the separation of fission product molybdenum-99 and uranium in sulfuric acid solution by tri-n-octylamine (TOA) in kerosene has been investigated. The equilibration time and the effect of temperature, concentration of extractant, uranium and sulfuric acid concentration on this extraction system were examined. The optimum conditions for the coextraction of molybdenum-99 and uranium have been obtained with the overall recovery of 90% for 99Mo and greater than 99% for uranium. Based on the complex stability difference between UO2(VI) and MoO2 (VI) with TOA, uranium in the organic phase can be back-extracted by proper chloride concentration. On the other hand, molybdenum-99 can be stripped from the organic phase by sodium carbonate or ammonium hydroxide solution. Decontamination factors of some major fission products such as 95Zr, 95Nb, 103Ru, 132Te, 141Ce and 131I in the separation process were also examined in this report. 11 references, 8 figures, 2 tables

  19. Interim environmental monitoring report for the Nevada test site, first quarter 1981

    During the first calendar quarter of 1981, no radioactivity from the nuclear tests conducted at the Nevada Test Site was measured offsite by the US Environmental Protection Agency's Environmental Monitoring Systems Laboratory. Low concentrations of 95Zr, 95Nb, 103Ru, and 141Ce attributed to the People's Republic of China nuclear test of October 15, 1980, were detected in air samples throughout the Air Surveillance Network. The maximum concentrations of these radionuclides were less than 0.1 percent of the Concentration Guides. The dosimeters of fixed station at Complex I (Coal Valley) indicated an exposure of 1.6 mR, and the dosimeters of two offsite residents, one living at Glendale, Nev., and the other near Complex I, (Coal Valley) appeared to have net exposures of 3.1 mR and 3.2 mR, respectively; however, further evaluation revealed that the net exposures were not due to an exposure from NTS operations, but may be a statistical anomaly related to an unusually low variation in the environmental background exposure rate. Further investigation is in progress

  20. Inorganic oxides as alternative in the separation of non fissioned residual uranium

    The Al2O3, SiO2 and SnO2 as well as vegetable carbon have been studied for its possible use as sorbent in the concentration and separation of non fissioned residual uranium of some fission products such as: 141 Ce, 134 Cs, 125 Sb, 103 Ru, 95 Zr, 95 Nb of alkaline aqueous systems. The separation efficiency has been evaluated using natural uranium and radionuclides in static and dynamic processes, through liquid scintillation and gamma spectrometry. Therefore Al2O3, SiO2, SnO2 and carbon were pre-treated thermic and chemically and characterized through the technique of Nitrogen absorption analysis, X-ray diffraction and IR spectroscopy. By means of the p H determination and the aqueous system potential the present hydrolysis products were determined. The inorganic oxides show structural and surface changes due to the treatment. The adsorption process is realized by different mechanism depending of the sorbent. The results show that the retention capacity is a dependence of the oxides pre-treatment and of the hydrolysis products in the aqueous system, as well as of the experimental conditions. Not in this way for carbon in which the results show the treatment and the experimental conditions significantly have not influence in its adsorption capacity. (Author)

  1. VIP and its homologous increase vascular conductance in certain endocrine and exocrine glands

    The effects of vasoactive intestinal peptide (VIP) and related structural homologues on tissue vascular conductances were investigated in anesthetized male rats. VIP, peptide histidine isoleucine (PHI), secretin, growth hormone-releasing factor (GHRF), gastric inhibitory peptide (GIP), or saline was infused intravenously over 4 min. Tissue blood flows were measured during this time by use of 141Ce-labeled microspheres. Circulating thyrotropin (TSH), triiodothyronine (T3), and thyroxine (T4) levels were determined before and at 20 min and 2 h after treatment. Marked increases in thyroid, pancreatic, and salivary gland vascular Cs occurred during peptide infusion with the order of potency correlating with the degree of structural homology to VIP. PHI and secretin produced maximal increases in vascular Cs, which were the same as those obtained with VIP. Circulating TSH, T3, and T4 levels were not different from values in saline-infused rats after peptide treatments that caused striking increases in thyroid vascular C. These observations indicate that the vascular beds of certain endocrine and exocrine glands are responsive to the vasodilatory action of VIP and related homologues with the order of potency corresponding to the degree of structural homology to VIP. These results are also consistent with the proposal that structural homologues of VIP act at the same vascular receptor as VIP. Alternative, the involvement of different vascular receptors, acting through the same mechanism at a level beyond the receptor site, cannot be excluded

  2. Intestinal circulation during inhalation anesthesia

    This study was designed to evaluate the influence of inhalational agents on the intestinal circulation in an isolated loop preparation. Sixty dogs were studied, using three intestinal segments from each dog. Selected intestinal segments were pumped with aortic blood at a constant pressure of 100 mmHg. A mixture of 86Rb and 9-microns spheres labeled with 141Ce was injected into the arterial cannula supplying the intestinal loop, while mesenteric venous blood was collected for activity counting. A very strong and significant correlation was found between rubidium clearance and microsphere entrapment (r = 0.97, P less than 0.0001). Nitrous oxide anesthesia was accompanied by a higher vascular resistance (VR), lower flow (F), rubidium clearance (Cl-Rb), and microspheres entrapment (Cl-Sph) than pentobarbital anesthesia, indicating that the vascular bed in the intestinal segment was constricted and flow (total and nutritive) decreased. Halothane, enflurane, and isoflurane anesthesia were accompanied by a much lower arteriovenous oxygen content difference (AVDO2) and oxygen uptake than pentobarbital or nitrous oxide. Compared with pentobarbital, enflurane anesthesia was not accompanied by marked differences in VR, F, Cl-Rb, and Cl-Sph; halothane at 2 MAC decreased VR and increased F and Cl-Rb while isoflurane increased VR and decreased F. alpha-Adrenoceptor blockade with phentolamine (1 mg . kg-1) abolished isoflurane-induced vasoconstriction, suggesting that the increase in VR was mediated via circulating catecholamines

  3. Assessments of circulatory changes in the scalded skin of rats using radioactively labelled microspheres

    In this study, changes in dermal circulation occurring in scalded rats were to be obtained with the aid of 141Ce-labelled microspheres. Prior to the tests, scalds were artificially produced to meet the standards prescribed for lesions of grades I, IIb and III. The comparative group was made up of rats, the dorsal skin of which had been treated with DMSO. In all animals, parallel measurements were carried out to assess the circulation of the intact abdominal skin. The highest values were obtained in DMSO-treated animals, with those determined for rats of the grade IIb group being only marginally lower. In animals showing first-degree lesions the blood supply of the dorsal skin was poor at 5 min following traumatisation, even though values were seen to rise again after 10 min. Extremely low circulatory values were measured in rats showing third-degree scalds. The findings revealed here matched the data obtained by other methods on changes in dermal circulation caused by scalds. (orig./MG)

  4. Feasibility of the instrumental neutron activation analysis of entire archaeological pottery. Part 1: Precision of the results and radiological safety of the process

    The feasibility of the instrumental neutron activation analysis of entire pieces of archaeological pottery, using low thermal neutron fluxes, is examined. The study takes into account the chemical elements relevant for archaeological investigations, as well as the degree of accuracy required for such kind of research. It is shown that after irradiation of a typical pottery sample of about 1 kg during 45 minutes, at a thermal flux of about 109 n.cm-2.s-1, analytical signals are obtained, by gamma spectrometry, with counting statistics better than 1%, for 76As, 131Ba, 141Ce, 60Co, 134Cs, 181Hf, 140La, 24Na, 122Sb, 46Sc, 153Sm and 233Pa, whereas 51Cr, 152Eu, 42K, 86Rb, 175Yb and 65Zn can be detected with counting statistics within 1% and 2%. On the other hand, the statistics of measurement are relatively poor (orders of 3% - 10%) for 177Lu, 147Nd, 239Np, 160Tb and 181Ta. The feasibility of accomplishment reliable quantitative determinations, taking into account the complexity of the analysis of entire pieces of archaeological pottery is discussed, which involves factors such as high masses, as well as asymmetric and variable shapes. (orig.)

  5. Determination of uranium fission products interference factors in neutron activation analysis

    Neutron activation analysis is a method used in the determination of several elements in different kinds of matrices. However, when the sample contains high U levels the problem of 235U fission interference occurs. A way to solve this problem is to perform the correction using the interference factor due to U fission for the radionuclides used on elemental analysis. In this study was determined the interference factor due to U fission for the radioisotopes 141Ce, 143Ce, 140La, 99Mo, 147Nd, 153Sm and 95Zr in the research nuclear reactor IEA-R1 on IPEN-CNEN/SP. These interference factors were determined experimentally, by irradiation of synthetic standards for 8 hours in a selected position in the reactor, and theoretically, determining the epithermal to neutron fluxes ratio in the same position where synthetic standards were irradiated and using reported nuclear parameters on the literature. The obtained interference factors were compared with values reported by other works. To evaluate the reliability of these factors they were applied in the analysis of studied elements in the certified reference materials NIST 8704 Buffalo River Sediment, IRMM BCR- 667 Estuarine Sediment e IAEA-SL-1 Lake Sediment. (author)

  6. Determination of uranium fission products interference factors in neutron activation analysis; Determinacao de fatores de interferencia de produtos de fissao de uranio na analise por ativacao neutronica

    Ribeiro Junior, Ibere Souza

    2014-09-01

    Neutron activation analysis is a method used in the determination of several elements in different kinds of matrices. However, when the sample contains high U levels the problem of {sup 235}U fission interference occurs. A way to solve this problem is to perform the correction using the interference factor due to U fission for the radionuclides used on elemental analysis. In this study was determined the interference factor due to U fission for the radioisotopes {sup 141}Ce, {sup 143}Ce, {sup 140}La, {sup 99}Mo, {sup 147}Nd, {sup 153}Sm and {sup 95}Zr in the research nuclear reactor IEA-R1 on IPEN-CNEN/SP. These interference factors were determined experimentally, by irradiation of synthetic standards for 8 hours in a selected position in the reactor, and theoretically, determining the epithermal to neutron fluxes ratio in the same position where synthetic standards were irradiated and using reported nuclear parameters on the literature. The obtained interference factors were compared with values reported by other works. To evaluate the reliability of these factors they were applied in the analysis of studied elements in the certified reference materials NIST 8704 Buffalo River Sediment, IRMM BCR- 667 Estuarine Sediment e IAEA-SL-1 Lake Sediment. (author)

  7. Inorganic oxides as alternative in the separation of non fissioned residual uranium; Oxidos inorganicos como alternativa en la separacion del uranio residual no fisionado

    Baca G, A

    1997-07-01

    The Al{sub 2}O{sub 3}, SiO{sub 2} and SnO{sub 2} as well as vegetable carbon have been studied for its possible use as sorbent in the concentration and separation of non fissioned residual uranium of some fission products such as: {sup 141} Ce, {sup 134} Cs, {sup 125} Sb, {sup 103} Ru, {sup 95} Zr, {sup 95} Nb of alkaline aqueous systems. The separation efficiency has been evaluated using natural uranium and radionuclides in static and dynamic processes, through liquid scintillation and gamma spectrometry. Therefore Al{sub 2}O{sub 3}, SiO{sub 2}, SnO{sub 2} and carbon were pre-treated thermic and chemically and characterized through the technique of Nitrogen absorption analysis, X-ray diffraction and IR spectroscopy. By means of the p H determination and the aqueous system potential the present hydrolysis products were determined. The inorganic oxides show structural and surface changes due to the treatment. The adsorption process is realized by different mechanism depending of the sorbent. The results show that the retention capacity is a dependence of the oxides pre-treatment and of the hydrolysis products in the aqueous system, as well as of the experimental conditions. Not in this way for carbon in which the results show the treatment and the experimental conditions significantly have not influence in its adsorption capacity. (Author)

  8. Influence of gamma irradiation on conductivity of YBa2Cu3O7

    Manjunatha, H. C.

    2015-08-01

    We report a study on influence of gamma irradiation on conductivity of YBa2Cu3O7. We have measured the mass attenuation coefficient, effective atomic number, electron density and electrical conductivity for various gamma sources of energy ranging from 0.084 MeV to 1.330 MeV (170Tm, 57Co, 141Ce, 203Hg, 51Cr, 113Sn, 22Na, 137Cs, 60Co, 22Na and 60Co). The measured values agree with the theoretical values. The values of these parameters have been found to change with energy and interaction of gamma. We find evidence for a variation of the electrical conductivity of YBa2Cu3O7 with the irradiated photon energy and this variation is shown in figures up to 105 MeV. The variations of effective atomic number and electron density with energy are shown graphically for all photon interactions. Conductivity found to vary with the energy of the irradiated gamma radiation and interaction process of gamma. This kind of studies is important in the field of superconductivity.

  9. Transfer of radionuclides from maternal food to the fetus and nursing infants of minipigs

    Transfer of 110mAg, 58Co, 59Fe, 141Ce, 103Ru, 88Y, 85Sr, 51Mn, 134Cs, 152Eu, 95mTc, 75Se, 65Zn and 133Gd was investigated in utero and during lactation in minipigs given the radioactive material added to food from day 50 of pregnancy until the end of lactation. The paper presents selected results on Ag, Co, Fe, Sr, Mn, Cs, Ru and Y and Tc. Transfer was highest for Cs and, in haemopoietic tissues, for Fe. Lower transfer was found for Ag, Fe, Mn with some preference for certain tissues (Ag in brain and liver, Mn in pancreas). Sr accumulated almost exclusively in bone and Tc in thyroid with higher concentrations in fetal and infant tissues than in maternal tissues. Lanthanides, Ru and Y were all close to detection limits or below in most maternal or fetal or infant tissues and could be found in bone and, less consistently, in kidney and liver. (author)

  10. A seasonal comparison of deposition velocities and retention half-times for Cs-134 and Ce-141 on cool desert vegetation

    Due to a scarcity of reliable deposition velocity estimates for radionuclides (particularly those in the submicron range) pooled estimates have been used to predict population doses resulting from atmospheric releases of radioactive particulates. The use of these estimates has led to large uncertainties in whole body dose estimates. Deposition velocities and retention half-times were therefore determined for submicron aerosols of 141Ce (biologically inactive) and 134Cs (biologically active) on sagebrush dominated desert vegetation in SE Idaho. Approximately 250 mCi (9.3 GBq) of each radionuclide were released over stands of Artemisia tridentata (big sagebrush) and bottlebrush grass (Sitanion hystrix) during three stages of plant development - spring vegetative growth, seed development, and plant dormancy. Air filters and vegetation samples were collected immediately following each release for use in deposition velocity calculations. Vegetation sampling was continued for a period of three months to obtain retention data. Deposition velocity values were 0.20 cm/s for sagebrush and 0.025 cm/s for grass. The loss of activity on the vegetation seemed to best fit a two component exponential loss function. Short component half-times were 1 to 2 days for both species. Long component half-times were two to three weeks for the shrub species and one to two weeks for the grass species. No significant difference was observed between nuclides. (author)

  11. Selective extraction of trivalent actinides from lanthanides using dicyclohexyldithiophosphinic acid and tributylphosphate

    In a previous study we showed that the three dithiophosphinic acids: dicyclohexyldithio-phosphinic acid (HDCHDTP), diphenyldithiophosphinic acid (HDPhDTP), and bis(2,4,4-trimethylpentyl)-dithiophosphinic acid (Cyanex trademark 301) in combination with the synergist tributylphosphate (TBP) could selectively extract trivalent actinides (represented by 241Am) from lanthanides (represented by 152Eu). This study was based on the premise that actinides form more stable complexes with ligands containing soft donor atoms than lanthanides due to a slightly greater covalent bonding component for the actinide ions. However, due to the difference in the radii of Am(III) (1.07 Angstrom) and Eu(III) (0.95 Angstrom), it was necessary to extend the study to include a wider variety of lanthanides to show that the ion radius size was not an important factor in these extractions. In this study the most promising of the three dithiophosphinic acids, HDCHDTP, was used along with the synergist TBP to selectively extract 241Am-from 152Eu, 141Ce, and 88Y (acting as a pseudolanthanide). Large separation factors (up to 540 to 980 depending on the Ln) between the extraction of the actinides over the lanthanides were still observed proving that ionic radius was not the important factor in these extractions

  12. Probing new physics with underground accelerators and radioactive sources

    New light, weakly coupled particles can be efficiently produced at existing and future high-intensity accelerators and radioactive sources in deep underground laboratories. Once produced, these particles can scatter or decay in large neutrino detectors (e.g. Super-K and Borexino) housed in the same facilities. We discuss the production of weakly coupled scalars ϕ via nuclear de-excitation of an excited element into the ground state in two viable concrete reactions: the decay of the 0+ excited state of 16O populated via a (p,α) reaction on fluorine and from radioactive 144Ce decay where the scalar is produced in the de-excitation of 144Nd⁎, which occurs along the decay chain. Subsequent scattering on electrons, e(ϕ,γ)e, yields a mono-energetic signal that is observable in neutrino detectors. We show that this proposed experimental setup can cover new territory for masses 250 keV≤mϕ≤2me and couplings to protons and electrons, 10−11≤gegp≤10−7. This parameter space is motivated by explanations of the “proton charge radius puzzle”, thus this strategy adds a viable new physics component to the neutrino and nuclear astrophysics programs at underground facilities

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

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

  14. Some analytical aspects of the technologies using molten fluorides

    Analytical activities accompanying the development or a molten fluoride reactor can be divided into 3 groups: (i) Balance analyses of fissile and fertile isotopes and their isotope composition; (ii) Analytical control of the reactor process; and (iii) Special analyses and measurements for physical reactor parameters determination. The first group is formed by the precise determination of U, Pu, Th content and isotope composition. Both destructive and non-destructive methods are recommended. The suitable methods are the following: chemical methods (e.g. titrimetric methods), x-ray fluorescence and IDA with alpha- or mass-spectrometric ending. The mass-spectrometry, ICP-MS and gamma-spectrometry are preferred for the isotope analysis. The analyses important for operating reactor form the second group. There is the determination of important activation and fission products as: 233Pa, 137Cs, 90Sr, 144Ce, rare earth elements, transuranium elements, tritium etc. The methods commonly used are based on gamma-spectrometry, alpha-spectrometry, ICP-MS and LSC. In the last group the analyses used for the determination of reactor parameters or the chemical form of some elements in the melt of fluorides can be included. As an example the mass-spectrometric determination of the capture-to-fission ratio or the use of FTIR spectrometry for the determination of the chemical form of fluoride melt. The paper describes the results of measurements obtained for the systems similar to fluoride melts. The possibility of the methods application is discussed. (author)

  15. Long-lived radionuclides in low-level waste

    In July 1982, the Low-Level Waste Licensing Branch of the NRC, anticipating the impact of the proposed Part 61 to 10 CFR, funded a two-year project by SAI to study the radionuclide contents of LWR generated in low-level waste. The objectives of the study are: (1) to analyze, using verified techniques, 150 archived samples for specified beta- and x-ray-emitting nuclides that had not previously been analyzed; (2) to analyze twenty new samples obtained from operating plants for all relevant nuclides and compare them to previous data to ascertain trends; (3) to develop empirical scaling factors through the use of which concentrations of hard-to-analyze nuclides can be estimated from analyses of the gamma-ray emitting nuclides. The new samples are analyzed and the results are summarized and interpreted. Over fifty archived samples have also been analyzed. We discuss scaling factor development. Factors are presented that relate 63Ni and 59Ni to 60Co for PWRs and to 58Co for BWRs, 90Sr to 137Cs for BWRs and 241Pu, 239Pu, 241Am, and 244Cm to 144Ce for all LWRs. 8 figures, 3 tables

  16. Amchitka Radiobiological Program. Final report, July 1970-December 1979

    The Amchitka Radiobiological Program, to collect biological and environmental samples for radiological analyses, began in 1970 and continued through 1979. The principal objective was to determine the extent of radionuclide contamination from worldwide atmospheric fallout and from the detonation of three underground nuclear tests on Amchitka. Leakage of radionuclides from the underground test sites would be suspected if the amount of contamination was significantly greater than could be attributed to worldwide fallout or if an unexpected assemblage of radionuclides was detected. No radionuclides from the underground sites were detected, except for tritium from the Long Shot test (1965) which produced increased tritium concentrations in surface water and freshwater plants near the test site. This final report compiles all previous data into one report and considers the temporal trends in these data. Two naturally occurring radionuclides, 40K and 7Be, were the most abundantly occurring radionuclides in most samples; in lichen samples either 137Cs or 144Ce had the highest activity. All samples were below applicable Radiation Protection Guides and by 1979 most samples were near or below the statistical detection limits. Increased concentrations of short-lived fallout radionuclides following the Chinese atmospheric tests were found in freshwater and seawater samples and in most indicator organisms

  17. Amchitka Radiobiological Program. Final report, July 1970-December 1979

    Sibley, T.H.; Tornberg, L.D.

    1982-11-01

    The Amchitka Radiobiological Program, to collect biological and environmental samples for radiological analyses, began in 1970 and continued through 1979. The principal objective was to determine the extent of radionuclide contamination from worldwide atmospheric fallout and from the detonation of three underground nuclear tests on Amchitka. Leakage of radionuclides from the underground test sites would be suspected if the amount of contamination was significantly greater than could be attributed to worldwide fallout or if an unexpected assemblage of radionuclides was detected. No radionuclides from the underground sites were detected, except for tritium from the Long Shot test (1965) which produced increased tritium concentrations in surface water and freshwater plants near the test site. This final report compiles all previous data into one report and considers the temporal trends in these data. Two naturally occurring radionuclides, /sup 40/K and /sup 7/Be, were the most abundantly occurring radionuclides in most samples; in lichen samples either /sup 137/Cs or /sup 144/Ce had the highest activity. All samples were below applicable Radiation Protection Guides and by 1979 most samples were near or below the statistical detection limits. Increased concentrations of short-lived fallout radionuclides following the Chinese atmospheric tests were found in freshwater and seawater samples and in most indicator organisms.

  18. Determination of plutonium americium and curium in soil samples by solvent extraction with trioctylphosphine oxide

    A method of Pu, Am and Cm determination in soil samples, which was developed for analyzing samples from territories subjected to radioactive contamination as a result of the Chernobyl accident is described. After preliminary treatment the samples were leached by solution of 7 mol/l HNO23+0.3 mol/l KBrO3 during heating. Pu was isolated by extraction with 0.05 mol TOPO from 7 mol/l HNO3. 144Ce and partially remaining in water phase isotopes of Zr, U and Th were isolated in an extraction-chromatographic column with TOPO and PbO2. Then Am and Cm were extracted by 0.2 mol/l TOPO from solution 1 mol/l HLact+0.07 mol/l DTPA+1 mol/l Al(NO3)3. Alpha-activity of both extracted products was determined in liquid scintillation counter. Chemical yield of plutonium counted to 85±10%, that of americium and curium -75±10%. 17 refs

  19. Study of the behaviour of transuranics and possible chemical homologues in Lake Michigan water and biota

    Concentration factors for Pu, Am and U in Lake Michigan biota are compared to those of a number of stable trace elements that have short residence times in Lake Michigan water. The relative order of uptake for these nuclides in Lake Michigan biota is Am>Pu much>U. Evidence is summarized which suggests that the predominant oxidation state of 239, 240Pu in Lake Michigan water is 4+. Concentrations of 239, 240Pu in net plankton, filterable particulate matter, sediment trap, and benthic floc samples indicate that sorption by biogenic detritus, and settling of this material, can account for the reduced concentration of 239, 240Pu observed in surface waters during summer stratification, but that deposition into the sediments is primarily non-biological. Concentrations of 7Be, 144Ce and 137Cs in sediment trap samples show the effect of spring convective mixing and demonstrate the resuspension of mineral-rich surficial sediments during the summer months. The effect on the concentration of dissolved plutonium in the water column, of varying degrees of resuspension of sedimentary floc, is described using a simple mass-action model. A radiochemical method for the determination of americium and uranium in Lake Michigan environmental samples is also presented. (author)

  20. Calibration of Ge(Li) semiconductor detector by method using agar volume source

    The Ge(Li) semiconductor detector was calibrated for measurements of environmental samples. The radioisotopes used for standard sources are 22Na, 51Cr, 56Co, 57Co, 133Ba, 137Cs, 144Ce and 241Am. These are mixed with hot agar aqueous solution and fixed uniformly in a cylindrical plastic case in cooling. The agar volume source is advantageous in handling over the fluid aqueous source. The prepared cylindrical standard sources are in diameters 6 and 8 cm and thicknesses 1, 5, 10, 20, 30 and 40 mm (only for 8 cm diameter). The radioactivities of prepared standard sources are between 0.03 μCi and 0.2 μCi. It takes only a week to make the calibration except data processing. The obtained full energy peak efficiency curves include 5 - 10% error due to preparation of agar source, reference radioactivity data of purchased standard solutions, reference data of branching ratio of gamma-ray and sum effect. The efficiency curves, however, are sufficient for quantitative analysis of environmental samples. (author)

  1. Varieties of fuel particles in fallout of the Chernobyl NPP exclusion zone

    Soil in the Chernobyl NPP 30-km zone is known to be contaminated by fine particles of dispersed irradiated fuel. Experimental data obtained by the authors shortly after the accident indicated a significant excess of 95Zr in the particles compared with its calculated amount. This suggested that particles of the U fuel also contain construction material from the core, activated Zr. The authors have isolated particles of radioactive material from the heavy soil fraction in order experimentally to confirm this. Their dimensions varied from 85 to 750 μm; their mass, from 10 to 700 μg. Such characteristics as the microstructure, elemental composition, and the concentration of 144Ce and other radionuclides obtained from electron microscope measurements, microprobe analysis, and γ- and α-spectrometry were used to classify the particles. It was found that two types of highly active particles are characteristic of the Chernobyl NPP exclusion zone (up to 4-5 km) and the western track of the fallout for a distance of 20 km from the destroyed fourth block. The first type are genuine particles of irradiated fuel. The second type are aggregates consisting of U and Zr oxides. The second type predominates in fallout of the exclusion zone and in the western track

  2. Animal metabolism

    Studies on placental transport included the following: clearance of tritiated water as a baseline measurement for transport of materials across perfused placentas; transport of organic and inorganic mercury across the perfused placenta of the guinea pig in late gestation; and transport of cadmium across the perfused placenta of the guinea pig in late gestation. Studies on cadmium absorption and metabolism included the following: intestinal absorption and retention of cadmium in neonatal rats; uptake and distribution of an oral dose of cadmium in postweanling male and female, iron-deficient and normal rats; postnatal viability and growth in rat pups after oral cadmium administration during gestation; and the effect of calcium and phosphorus on the absorption and toxicity of cadmium. Studies on gastrointestinal absorption and mineral metabolism included: uptake and distribution of orally administered plutonium complex compounds in male mice; gastrointestinal absorption of 144Ce in the newborn mouse, rat, and pig; and gastrointestinal absorption of 95Nb by rats of different ages. Studies on iodine metabolism included the following: influence of thyroid status and thiocyanate on iodine metabolism in the bovine; effects of simulated fallout radiation on iodine metabolism in dairy cattle; and effects of feeding iodine binding agents on iodine metabolism in the calf

  3. Communication of nuclear data progress No. 21 (1999)

    The 21th issue of Communication of Nuclear Data Progress (CNDP) is presented, in which the achievements of last half year in nuclear data field in China are carried.It includes the measurement of differential cross sections for 6Li(n,t)4He reaction at 3.67 and 4.42 MeV, 14 MeV neutron activation cross section for 93Nb (n,2n)92Nb reaction, double differential cross sections for 39K(n,α36Cl reaction at 4.41, 5.46, 6.52 MeV; theoretical calculations of n + 235U, 151,153,154,155Eu, 135-138Ba69,71Ga, 83-86Kr at En = 0.001-20 MeV; evaluations of neutron reaction cross sections for 140,141,142,144Ce, 63,65,NatCu, 115In, 105,108Pd and 103Rh, complete data for 63Cu, and photonuclear reaction for 90,91,92,94,96Zr, nuclear data sheets for A = 195 and thermal-neutron captures data evaluation for A = 1-19; construction of covariance matrix for absolute fission yield data measurement; thermal and fast reactor benchmark testing of ENDF/B-6.4. Also the activities on nuclear data in China are summarized

  4. Hazards to the eye lens and gonads from hard beta rays

    Considerable attention has been paid to the protection against x and γ radiation but comparatively less stress has been given to the possible hazard due to external radiation from high-energy beta rays. In order to evaluate the magnitude of this hazard, central-axis depth doses at different source-to-skin distances for 90Sr-90Y and 32P sources were measured. Isodose curves in a testicular phantom for a 90Sr-90Y source were measured. The data of Haybittle for 144Ce for 10 cm SSD has been included. From the measured data, the eye-lens epithelium dose may be as high as 51%, 21.5%, and 82%, respectively, for the three sources instead of 15% as has been conventionally assumed. The isodose curves obtained in the testicular phantom indicate that an appreciable amount of testicular tissue can be subjected to radiation exposures. The radiation hazards due to high-energy beta rays are not negligible and considerable care should be exercised while using these sources

  5. Assay of long-lived radionuclides in low-level wastes from power reactors

    The 10 CFR Part 61 waste classification system includes several nuclides which are difficult to assay without expensive radiochemical methods. In order for waste generators to classify wastes practically, NRC Staff has recommended the use of correlation factors to scale the difficult-to-measure nuclides with nuclides which can be measured more easily (i.e., gamma emitters such as 60Co or 137Cs). In this study, Science Applications International Corporation (SAIC) performed complete radiochemical assays for all the 10 CFR Part 61 waste classification nuclides on over 100 samples. These data, along with almost 800 other samples in the SAIC data base, were used to assess the validity of correlation factors suggested for use in nuclear power plant wastes. Specific generic correlation factors are recommended with other approaches to correlate nuclides for which generic scaling factors are not defensible. The primary nuclide correlations studied were 14C, 55Fe, 59Ni, 63Ni, and 94Nb, with 60Co; 90Sr, 99Tc, 129I, 135Cs, and /sup 239, 240/Pu with 137Cs; 238Pu, /sup 239, 240/Pu, 241Pu, 241Am, 242Cm, and /sup 243, 244/Cm with 144Ce; and 238Pu, 241Pu, 241Am, 242Cm and /sup 243, 244/Cm with /sup 239, 240/Pu

  6. Fraction of energy absorbed from β-emitting particles in the rat lung

    Forty-four male Fischer-344 rats were exposed, nose only, to a relatively insoluble aerosol of 144Ce-labeled fused aluminosilicate particles. Fractional β energy absorption was measured 7 to 9 days after exposure for 28 rats (ages 12 to 25 weeks and body weights of 183 to 337 g); lung burdens were 13 to 82 nCi. An additional group of 16 rats was exposed when 12 weeks old and maintained for 6 months prior to analysis; body weights and lung burdens 6 months after exposure ranged from 276 to 368 g and 16 to 46 nCi, respectively. Lungs were carefully removed, inflated, and frozen by immersion in liquid nitrogen. The energy spectrum from each lung was measured in a 4π β spectrometer, keeping the lung frozen throughout this procedure. Over the range of lung sizes in this study (0.88 to 1.66 g) the mean fractional energy absorption and standard deviation were 0.23 +- 0.078, respectively. Results agreed well with theory, indicating that calculated values for fractional energy absorption in the lung can be used for a range of lung sizes and β energies. Calculated values for fractional energy absorption as a function of β energy are included for several lung sizes between 0.5 and 10 g

  7. TMI-2 Reactor Building source term measurements: surfaces and basement water and sediment

    Presented in this report are the results of radiochemical and elemental analyses performed on samples collected from the Three Mile Island Unit 2 Reactor Building from August 1979 to December 1983. The quantities of fission products and core materials that were measured on the external surfaces in the Reactor Building or in the water and sediment in its basement are summarized. Recent analysis results for access panels removed from the air cooling assembly and for liquid and particulate samples collected from the Reactor Building sump and reactor coolant drain tank are included in the report. Measurements show that 59% of the 3H, 2.7% of the 90Sr, 15% of the 129I, 20% of the 131I, and 42% of the 137Cs originally in the core at the time of the accident could be accounted for outside the core in the Reactor Building. With the exceptions of 90Sr and 144Ce, the vast majority of each radionuclide released was found dispersed in the water and sediment in the basement

  8. The long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation: results from leach experiments

    The Belgian Nuclear Research Centre SCK-CEN has carried out a number of studies to evaluate the long-term behaviour of cemented research reactor waste under the geological disposal conditions of the Boom Clay Formation. Static leach experiments in synthetic clay water were performed on active samples of cemented research reactor waste. The leach experiments were carried out under anaerobic conditions at two testing temperatures (23 and 85oC). Leach rates of seven radionuclides (60Co, 90Sr, 134Cs, 137Cs, 144Ce, 154Eu and 241Am) were measured. Most investigated radionuclides are well retained within the cement matrix over a 280 days testing period. Results on the source term of radionuclides were complemented with data on the leaching behaviour of cement matrix constituents as Ca, Si, Al, Na, K, Mg and SO4 as well as with data from performance assessment calculations and in situ tests. Despite limitations inherent to short-term experiments, combined results from these investigations indicate only limited interactions of disposed research reactor waste with the near field of a geological repository in clay. (author)

  9. Metaphase chromosome aberrations as markers of radiation exposure and dose

    Chromosome aberration frequency provides the most reliable biological marker of dose for detecting acute accidental radiation exposure. Significant radiation-induced changes in the frequency of chromosome aberrations can be detected at very low doses. Our paper provides information on using molecular chromosome probes ''paints'' to score chromosome damage and illustrates how technical advances make it possible to understand mechanisms involved during formation of chromosome aberrations. In animal studies chromosome aberrations provide a method to relate cellular damage to cellular dose. Using an In vivo/In vitro approach aberrations provided a biological marker of dose from radon progeny exposure which was used to convert WLM to dose in rat tracheal epithelial cells. Injection of Chinese hamsters with 144Ce which produced a low dose rate exposure of bone marrow to either low-LET radiation increased the sensitivity of the cells to subsequent external exposure to 60Co. These studies demonstrated the usefulness of chromosome damage as a biological marker of dose and cellular responsiveness

  10. Studies on treatment of radioactive animal carcass, (2)

    A method of dehydration for the waste treatment of radioactive animal carcass by microwave heating was developed. A heating apparatus was devised by annexing the microwave output controlling circuit to a 600 W commercial microwave oven, and the aqueous vapour from the animal carcass was collected by duplex cold traps. Body weight of the carcass was reduced to 20-30% by dehydration, and a three-year storage test proved that the dehydrated carcass was very hard to decompose. Time needed for dehydration was about 10 min for a 25 g mouse, and about 1 hr for 668 g dog. Violent rupture of the carcass, and/or fuming due to overheating that had often been observed during dehydration were proved to be avoidable by controlling the microwave output during the process. The ratio of radioactivity (60Co, 137Cs, 85Sr, 144Ce) that escaped from the carcass during dehydration was found to be less than 3 x 10-4 by a series of experiment. Some related radiation safety problems were discussed. (author)

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

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

  12. Assessment of a Compton-event suppression γ-spectrometer for the detection of fission products at trace levels

    The improvement in detection limits for low and high activity samples measured with the Compton-suppression γ-spectrometer installed at the Institute for Transuranium Elements (ITU) for environmental monitoring of radioactivity, as well as nuclear safeguards, is discussed. The advantage of using two parallel acquisition lines for simultaneous measurement with and without Compton-event suppression is outlined with respect to cascade and non-cascade γ-emitters. The background reduction by Compton-event suppression made it possible to detect small peaks, which otherwise would not have been found in a conventional spectrum. In Compton-event suppression mode, the detection limit for 137Cs was improved by a factor of about 3, for 241Am we found a factor of 1.2 both in high and low active samples. The measurements of environmental reference samples showed good agreement with certified values in both acquisition modes. The application of this instrument for the determination of fission products in smear samples is described. In particular, for nuclides like 54Mn, 125Sb and 144Ce, an improvement in the detection limits by a factor of 1.6-2.4 was obtained

  13. Marine plankton as an indicator of low-level radionuclide contamination in the Southern Ocean

    Marsh, K.V.; Buddemeier, R.W.

    1984-07-01

    We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review shows that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 10/sup 4/. In the years 1956-1958, considerable work was done on the accumulation and distribution of a variety of fission and activation products produced by the nuclear tests in the Marshall Islands. Since then, studies have largely been confined to a few selected radionuclides, and by far most of this work has been done in the northern hemisphere. We participated in Operation Deepfreeze 1981, collecting 32 plankton samples from the U.S. Coast Guard Cutter Glacier on its Antarctic cruise, while Battelle Pacific Northwest Laboratories concurrently sampled air, water, rain and fallout. We were able to measure concentrations of the naturally occurring radionuclides /sup 7/Be, /sup 40/K and the U and th series, and we believe that we have detected low levels of /sup 144/Ce and /sup 95/Nb in seven samples ranging as far south as 68/sup 0/. There is a definite association between the radionuclide content of plankton and air filters, suggesting that aerosol resuspension of marine radioactivity may be occurring. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and foraminifera content of the samples. 38 references, 7 figures, 3 tables.

  14. Benefits and risks of bronchopulmonary lavage: a review

    Studies were conducted in beagle dogs and baboons over a period of 20 years to determine the efficiency of treatment by lung lavage after inhalation of insoluble radioactive particles. The radionuclides tested were 144Ce in fused clay, 238Pu, 239Pu, 241Am, Pu-TBP, Pu02, UO2, and (Pu,U)02. After inhalation of any of these radionuclides, a single lavage of the two lungs removed almost a quarter of the intitial lung burden (ILB) in the two species. When lavage was repeated five times, it removed up to half of the ILB. However, the individual variation was large. For the same radionuclide, lavage efficiency was independent of the ILB. Particle removal was better and continued longer for particles with a long retention half-time. The use of lavage can be combined with that of chelating agents like DTPA. The removal of radioactive particles lenghtened survival time and reduced the severity of pathology. The lavage in itself is safe, and does not induce permanent or progressive pathology. The biomedical risk of the lavage mainly depends on the risks inherent in anaesthesia and the health status of the patient. (author)

  15. Classification of hot particles from the Chernobyl accident and nuclear weapons detonations by non-destructive methods

    Both after the Chernobyl accident and nuclear weapon detonations, agglomerates of radioactive material, so-called hot particles, were released or formed which show a behaviour in the environment quite different from the activity released in gaseous or aerosol form. The differences in their characteristic properties, in the radionuclide composition and the uranium and actinide contents are described in detail for these particles. While nuclear bomb hot particles (both from fission and fusion bombs) incorporate well detectable trace amounts of 60Co and 152Eu, these radionuclides are absent in Chernobyl hot particles. In contrast, Chernobyl hot particles contain 125Sb and 144Ce which are absent in atomic bomb HPs. Obvious differences are also observable between fusion and fission bombs' hot particles (significant differences in 152Eu/155Eu, 154Eu/155Eu and 238Pu/239Pu ratios) which facilitate the identification of HPs of unknown provensence. The ratio of 239Pu/240Pu in Chernobyl hot particles could be determined by a non-destructive method at 1:1.5. A non-destructive method to determine the content of non-radioactive elements by Kα-emission measurements was developed by which inactive Zr, Nb, Fe and Ni could be verified in the particles

  16. Results of gamma-scanning measurements on Windscale AGR stringer Mk4/S46 and implications for civil AGRs

    Axial rating distributions in a WAGR fuel stringer were determined retrospectively using the measured gamma count rates from five fission products after cooling times of 70 to 100 days. The results from all five isotopes were in general agreement with predictions using the Windscale code CAMPARI, but revealed mutually consistent discrepancies with prediction near the top axial reflector. The measurements were conducted to test the gamma-scanning apparatus and methods of analysis in preparation for the post irradiation examination of CAGR fuel. It was concluded from the results that accuracies of +- 2% to +- 3% (1 sigma) should be attainable in the determination of relative ratings using the measured gamma count rates from the isotopes 140Ba, 103Ru, 95Zr, 144Ce and 137Cs. The accuracies will, however, depend on the type of fuel being examined and the fission product used. In particular, care must be taken when using 137Cs since it may migrate from its point of formation, and cooling times of less than 110 days must be achieved to measure relative concentrations of the short-lived isotope 140Ba with sufficient accuracy. (author)

  17. Practical aspects of sea and fresh-water algae utilization

    Regularities of sea and fresh-water microalgae cultivation, revealed during the operation of industrial plants, are presented in detail. The study of the Platymonas viridis cultivation mechanisms has shown the possibility of active intervention into the cycle of intense reproduction of the biomass. Among physical factors of the medium, which influence the reproduction of the industrial strain of Platymonas viridis, the effect of the red light, ultraviolet radiation, ultrahigh frequency fields and gamma radiation upon the cell division of these microalgae has been investigated. It has been shown that the effect of gamma radiation on the cell division of Platymonas viridis, other bacteria and protozoans is inhibiting. In the experiments using the radionuclides strontium-90 and cerium-144 as indicators of metabolism the dependence of the radionuclide accumulation factor on the quantity of stable lead as well as the effect of the temperature on the accumulation process have been studied. The coefficients of 90Sr and 144Ce accumulation by Nitellopsis obtusa cell compartments depending on stable lead and temperature are presented. 200 refs.; 21 figs.; 54 tabs

  18. Transfer factors of trace elements and radionuclides in the marine environment of India

    The document presents the data base on Bioaccumulation Factor, Bp and Distribution Coefficient, Kd values generated in the eastern and western coastal marine waters of India with a view to develop site-specific or species-specific values. Comparison with the IAEA default values from Safety Series No. 57 and Technical Report Series No. 247 values is made. Generally, the Bp values for trace elements do not vary by more than a factor of 3 except for some specific cases like Fe in molluscs, crustaceans and fish, Ni in molluscs and Zn in sea weeds and molluscs. The same is true for the Bp values of fission nuclides viz.,137Cs and 90Sr in molluscs, crustaceans and sea weeds except for the Bp of 137Cs in fish which is significantly lower in the Indian context. The fission nuclide 144Ce shows distinctly higher accumulation factors in all organisms. The Bp values of natural radionuclides such as 210Pb ,210Po, Ra and U are close to the IAEA default values except for the high value of U in fish. Similarly, Bp values of Pu in fish and crustaceans are significantly higher than that of the IAEA default values. The report presents Bp values for Cu and Cd in different marine organisms and Kd values in marine sediments. Kd values for suspended particles are also presented. Bp values for plankton and porifera are also given. (author)

  19. Linear free energy correlations for fission product release from the Fukushima-Daiichi nuclear accident.

    Abrecht, David G; Schwantes, Jon M

    2015-03-01

    This paper extends the preliminary linear free energy correlations for radionuclide release performed by Schwantes et al., following the Fukushima-Daiichi Nuclear Power Plant accident. Through evaluations of the molar fractionations of radionuclides deposited in the soil relative to modeled radionuclide inventories, we confirm the initial source of the radionuclides to the environment to be from active reactors rather than the spent fuel pool. Linear correlations of the form In χ = −α ((ΔGrxn°(TC))/(RTC)) + β were obtained between the deposited concentrations, and the reduction potentials of the fission product oxide species using multiple reduction schemes to calculate ΔG°rxn (TC). These models allowed an estimate of the upper bound for the reactor temperatures of TC between 2015 and 2060 K, providing insight into the limiting factors to vaporization and release of fission products during the reactor accident. Estimates of the release of medium-lived fission products 90Sr, 121mSn, 147Pm, 144Ce, 152Eu, 154Eu, 155Eu, and 151Sm through atmospheric venting during the first month following the accident were obtained, indicating that large quantities of 90Sr and radioactive lanthanides were likely to remain in the damaged reactor cores. PMID:25675358

  20. A probable radiation-induced epidermal carcinoma in a sheep

    The sheep discussed in this report was one of 12 wether lambs given daily doses of 144Ce-144Pr to investigate the effect of radionuclides on the alimentary tract. The sheep received 20 mCi daily over a 16 day period when treatment was discontinued due to the development of sever diarrhea and later anorexia. Changes in the sheep reported (alopecia, ulceration, disappearance of adnexa, and fibrous replacement of the dermal collagen) indicate a radiation dose in excess of that used in previous experiments. About 4.5 yr after dosing, a firm enlargement was noticed in the right ventrolateral coccygeal region. As the enlargement increased in size, ulceration and bacterial infection occurred. The sheep was killed 59 months after initial treatment and a necropsy performed. The findings were consistent with the diagnosis of locally invasive squamouscell carcinoma. The authors feel that the relative rarity of epidermal carcinomas in sheep, exposure of the coccygeal area to large doses of irradiation, and the carcinogenic effect of radiation indicates a probable cause-and-effect relationship of radiation and tumour development. (U.K.)

  1. Radionuclide migration experiments in a natural fracture in a quarried block of granite

    A radionuclide migration experiment was performed over a distance of 1 m in a natural fracture in a quarried block of granite. The fracture in the block was characterized hydraulically by measuring the pressure drop in borehole-to-borehole pump tests. The effective fracture volume in the block was ∼100 mL. A silicone coating was applied to the exterior, and the block was immersed in a tank of water to which hydrazine was added to provide a chemically reducing barrier. Migration experiments were performed at a flow rate of 2.2 mL h-1 using 85Sr, 131I,137Cs, 144Ce, 152Eu, 237Np and 238Pu. A total of 9.5 L of groundwater was pumped through the fracture, corresponding to ∼95 fracture volumes. Only 85Sr, 131I, 137Cs, 237Np and 238Pu were observed in the eluent. Scanning of the fracture surface at the end of the migration experiment showed limited mobility of α-emitting radionuclides and of the rare-earth elements, consistent with static sorption data obtained on representative fracture surface material. The mobility of 137Cs was higher than that of the rare-earth elements, but it was lower than that of 85Sr. When samples of fracture-coating material were separated into fractions with different specific gravity, there was a clear indication of radionuclide association with mineral groups. (author)

  2. Radionuclide migration experiments in a natural fracture in a quarried block of granite

    Vandergraaf, Tjalle T.; Drew, Douglas J.; Masuda, Sumio

    1996-02-01

    A radionuclide migration experiment was performed over a distance of 1 m in a natural fracture in a quarried block of granite. The fracture in the block was characterized hydraulically by measuring the pressure drop in borehole-to-borehole pump tests. The effective fracture volume in the block was ˜ 100 mL. A silicone coating was applied to the exterior, and the block was immersed in a tank of water to which hydrazine was added to provide a chemically reducing barrier. Migration experiments were performed at a flow rate of 2.2 mL h -1 using 85Sr, 131I, 137Cs, 144Ce, 152Eu, 237Np and 238Pu. A total of 9.5 L of groundwater was pumped through the fracture, corresponding to ˜95 fracture volumes. Only 85Sr, 131I, 137Cs, 237Np and 238Pu were observed in the eluent. Scanning of the fracture surface at the end of the migration experiment showed limited mobility of α-emitting radionuclides and of the rare-earth elements, consistent with static sorption data obtained on representative fracture surface material. The mobility of 137Cs was higher than that of the rare-earth elements, but it was lower than that of 85Sr. When samples of fracture-coating material were separated into fractions with different specific gravity, there was a clear indication of radionuclide association with mineral groups.

  3. Marine plankton as an indicator of low-level radionuclide contamination in the Southern Ocean

    We have initiated an investigation of the utility of marine plankton as bioconcentrating samplers of low-level marine radioactivity in the southern hemisphere. A literature review shows that both freshwater and marine plankton have trace element and radionuclide concentration factors (relative to water) of up to 104. In the years 1956-1958, considerable work was done on the accumulation and distribution of a variety of fission and activation products produced by the nuclear tests in the Marshall Islands. Since then, studies have largely been confined to a few selected radionuclides, and by far most of this work has been done in the northern hemisphere. We participated in Operation Deepfreeze 1981, collecting 32 plankton samples from the U.S. Coast Guard Cutter Glacier on its Antarctic cruise, while Battelle Pacific Northwest Laboratories concurrently sampled air, water, rain and fallout. We were able to measure concentrations of the naturally occurring radionuclides 7Be, 40K and the U and th series, and we believe that we have detected low levels of 144Ce and 95Nb in seven samples ranging as far south as 680. There is a definite association between the radionuclide content of plankton and air filters, suggesting that aerosol resuspension of marine radioactivity may be occurring. Biological identification of the plankton suggests a possible correlation between radionuclide concentration and foraminifera content of the samples. 38 references, 7 figures, 3 tables

  4. Fission-Product Development Laboratory cell-decommissioning project plan

    The Fission Product Development Laboratory (FPDL) at Oak Ridge National Laboratory (ORNL) was a full-scale processing facility for separating megacurie quantities of 90Sr, 137Cs, and 144Ce for a variety of source applications, operating at full capacity from 1958 to 1975. Since facility shutdown, the inactive portions of the FPDL have been maintained in a protective storage mode as part of the ORNL Surplus Facilities Management Program (SFMP). Due to the significant radio-nuclide inventory remaining in the facility, the high surveillance and maintenance costs necessary to assure radionuclide containment, and the potential for reuse of the facility by other programs, the decommissioning of the inactive portions of the FPDL has been given a high priority by the SFMP. In response to this program direction, plans are being made for initiation of these activities in late FY 1983. This project plan has been prepared to satisfy the program documentation requirements for SFMP project planning. The plan outlines the scope of the proposed effort, describes the proposed methods of project accomplishment, and provides estimates of the project resource needs and schedule

  5. The passage of lanthanides (Cd-144, Nd-147, Sm-153, Eu-155 and Tb-160) into fetus and newborn after intravenous contamination of rats and estimation of absorbed dose in whole body and gastrointestinal tract

    The purpose of the study was the determination of the passage of certain lanthanum elements (147Nd, 153Sm, 155Eu and 160Tb) from maternal blood through the placenta to the fetus in the second and third weeks of pregnancy and also estimation of absorbed dose in gastrointestinal tract in newborn rats contaminated with 147Nd, 153Sm, 155Eu and 160Tb. The study demonstrated that the lanthanum elements passed across the placental barrier. Placental retention was several times higher in late pregnancy (in the case of 160Tb it was even 16 - fold greater). In the last period of pregnancy this passage increased with increasing mass number of the elements (Nd160Tb (17%) and decreased with the drop of molecular weight of radionuclides. For all lanthanides tested, the dose of γ-radiation absorbed by newborns could be neglected since it comprised only 0.5% of β-radiation. The absorbed dose of β-radiation during the first week of life of new newborns fed by mother injected with 37 kBq of radionuclides ranged from 204 mGy for 160Tb to 0.23 mGy for 144Ce. (author). 15 refs., 5 figs., 4 tabs

  6. TMI-2 Reactor Building source term measurements: surfaces and basement water and sediment

    McIsaac, C V; Keefer, D G

    1984-10-01

    Presented in this report are the results of radiochemical and elemental analyses performed on samples collected from the Three Mile Island Unit 2 Reactor Building from August 1979 to December 1983. The quantities of fission products and core materials that were measured on the external surfaces in the Reactor Building or in the water and sediment in its basement are summarized. Recent analysis results for access panels removed from the air cooling assembly and for liquid and particulate samples collected from the Reactor Building sump and reactor coolant drain tank are included in the report. Measurements show that 59% of the /sup 3/H, 2.7% of the /sup 90/Sr, 15% of the /sup 129/I, 20% of the /sup 131/I, and 42% of the /sup 137/Cs originally in the core at the time of the accident could be accounted for outside the core in the Reactor Building. With the exceptions of /sup 90/Sr and /sup 144/Ce, the vast majority of each radionuclide released was found dispersed in the water and sediment in the basement.

  7. Probing New Physics with Underground Accelerators and Radioactive Sources

    Izaguirre, Eder; Pospelov, Maxim

    2014-01-01

    New light, weakly coupled particles can be efficiently produced at existing and future high-intensity accelerators and radioactive sources in deep underground laboratories. Once produced, these particles can scatter or decay in large neutrino detectors (e.g Super-K and Borexino) housed in the same facilities. We discuss the production of weakly coupled scalars $\\phi$ via nuclear de-excitation of an excited element into the ground state in two viable concrete reactions: the decay of the $0^+$ excited state of $^{16}$O populated via a $(p,\\alpha)$ reaction on fluorine and from radioactive $^{144}$Ce decay where the scalar is produced in the de-excitation of $^{144}$Nd$^*$, which occurs along the decay chain. Subsequent scattering on electrons, $e(\\phi,\\gamma)e$, yields a mono-energetic signal that is observable in neutrino detectors. We show that this proposed experimental set-up can cover new territory for masses $250\\, {\\rm keV}\\leq m_\\phi \\leq 2 m_e$ and couplings to protons and electrons, $10^{-11} < g_e...

  8. Advanced orient cycle, for strategic separation, transmutation and utilization of nuclides in the nuclear fuel cycle

    directly recover pure Cm as well as pure Am with minimum number of reprocessing separation steps is reported in another paper. The recent experiments indicated that strong adsorption of 106Ru and 125Sb was observed under the diluted HCl medium, thereby completely 106Ru-free feed dissolver solution was obtained. The CEE separation step will follow this IX step for further purification and fabrication of RMFP material for their utilization. Based on those technologies, the Trinitarian Research and Development project (Advanced ORIENT Cycle) on partitioning, transmutation and utilization of actinides and fission products will be developed to realize ultimate reducing long-term radio toxicity in the radioactive wastes. Actinides, LLFP (135Cs, etc), MLFP (90Sr, 137Cs) and RMFP shall be separated to the level of isotope as well as element. The CEE process will be added for utilization of RMFP. The RMFP, one of the products of Ad. ORIENT Cycle, would be expected to be a 'FP-catalyst' to circulate between nuclear and hydrogen / fuel cell energy systems, and thereby contributing to save the natural precious metal resources

  9. Department of Radiation Shielding and Dosimetry: Overview

    Full text: The research activities of the Department in 1998, similarly to the previous year were focused on the following problems: Dosimetry for medical purposes; Microdosimetry at the nanometer level; Numerical modelling of interaction of radiation with matter; DOSIMETRY: Based on experience gained in previous years in absolute and relative measurements of absorbed dose for 106Ru applicators, the detectors and methods for dosimetry of β radiation applied in intravascular brachytherapy have been undertaken. A new, small size scintillation probe with NE102A scintillator 1 mm dia. by 1 mm coupled to a 30 cm long flexible light guide and to a 9524S photomultiplier has been assembled and tested. The GAF Chromic foils, MDSS, have been found to be very promising detectors for intravascular and ocular brachytherapy. A miniature ionisation chamber for Kerma in air measurements in radiation field of a ''photon needle'' (small size X-ray tube operated at 30 KV) has been assembled and tested. MICRODOSIMETRY: The absolute efficiency of two types of electron multipliers, i.e. discrete dynode electron multiplier DM205IG and channel electron multiplier X719BL for Ar+ ions in energy range 1 keV to 10 keV has been determined in an experiment performed in cooperation with the Weizmann Institute of Science. These electron multipliers are used in the set up ''JET COUNTER'' as detectors for ion cluster studies. A method for measuring the spectra of ion clusters created along a charged particles track has been proposed. The ion clusters spectra produced by alpha particles 241Am source passed a distance of 3.6 to 10 nm (in units of density scale) in nitrogen have been measured. Also, preliminary measurements of ion clusters created by low energy electrons 50 and 100 eV have been carried out. Activities in this field were supported by IV CEC Framework Programme as well as by the Polish State Commission for Scientific Research. NUMERICAL MODELLING: Monte Carlo simulation is direct and

  10. Speciation and transport of radionuclides in ground water

    Studies of the chemical speciation of a number of radionuclides migrating in a slightly contaminated ground water plume are identifying the most mobile species and providing an opportunity to test and/or validate geochemical models of radionuclide transport in ground waters. Results to date have shown that most of the migrating radionuclides are present in anionic or nonionic forms. These include anionic forms of 55Fe, 60Co, /sup 99m/Tc, 106Ru, 131I, and nonionic forms of 63Ni and 125Sb. Strontium-70 and a small fraction of the mobile 60Co are the only cationic radionuclides which have been detected moving in the ground water plume beyond 30 meters from the source. A comparison of the observed chemical forms with the predicted species calculated from modeling thermodynamic data and ground water chemical parameters has indicated a good agreement for most of the radioelements in the system, including Tc, Np, Cs, Sr, Ce, Ru, Sb, Zn, and Mn. The discrepancies between observed and calculated solutions species were noted for Fe, Co, Ni and I. Traces of Fe, Co, and Ni were observed to migrate in anionic or nonionic forms which the calculations failed to predict. These anionic/nonionic species may be organic complexes having enhanced mobility in ground waters. The radioiodine, for example, was shown to behave totally as an anion but further investigation revealed that 49-57% of this anionic iodine was organically bound. The ground water and aqueous extracts of trench sediments contain a wide variety of organic compounds, some of which could serve as complexing agents for the radionuclides. These results indicate the need for further research at a variety of field sites in defining precisely the chemical forms of the mobile radionuclide species, and in better understanding the role of dissolved organic materials in ground water transport of radionuclides

  11. Results of the Separations Area ground-water monitoring network for 1981

    This report summarizes and interprets the results of the Separations Area ground-water monitoring program for calendar year 1981. The Separations Area ground-water monitoring program satisfies US Department of Energy requirements that all onsite discharges be monitored. There are 105 water quality monitoring wells in the 1981 Separations Area monitoring network. Samples from the water quality monitoring wells were collected at monthly or semiannual intervals. These samples were analyzed selectively for total alpha, total beta, 60Co, 106Ru, 137Cs, 90Sr, tritium, uranium, and nitrate. Review of 1981 results indicated few changes from 1980. The 3000-pCi/mL tritium guideline was exceeded in three wells that monitor two active sites: Well 299-E24-2 monitors the 216-A-10 Crib, and Wells 299-E25-18 and 299-E25-20 monitor 219-A-37 Crib. Sample concentrations reflect plume migrations of active sites. With the exception of tritium, all contamination greater than 10% of Table II guidelines in the ground water under the Separations Area was caused by past disposal to inactive sites. The only samples with contamination that exceeded Table II guidelines were collected from Wells 299-W22-1, 299-E28-23, and 299-E33-27, which monitor the inactive 216-S-1 and -2 Crib, 216-B-5 Reverse Well, and 216-BX Tank Farm. However, the zone of contamination appears stable and highly localized for these sites. Analysis of contamination plumes within the Separations Area indicates that contamination levels in ground water migrating out of the Separations Area at this time are less than the DOE Table II guidelines

  12. Kinetics of ruthenium in humans

    The fission products 103Ru and 106Ru may represent a radiological hazard for the population in case of their release in the environment and transfer to the food chain; considerable amounts of these radionuclides were indeed found in the fall-out of the Chernobyl accident and also after nuclear weapon tests. As for many other radionuclides, the biokinetic model for ruthenium currently recommended by ICRP is mainly based on animal data. In order to obtain valuable information directly in humans, a technique based on stable isotopes administration and analytical methods such as activation analysis with charged particles and inductively coupled mass spectrometry has been purposely developed. A total of six investigations were conducted on two healthy volunteers by administration of given amounts of isotopically enriched ruthenium. Blood samples were withdrawn at fixed intervals in the first 6 hours after administration, and the total renal excretion in the first two days collected. Tracer concentration in the biological samples were determined using the analytical methods introduced above. The results show that the kinetics in plasma and the urinary pattern present several deviation from the behaviour described by the current ICRP model. The intestinal absorption proceeds at a faster rate, however the fraction absorbed dose not differ greatly from the value of 0.05 recommended. The excretion in the urine is on the contrary greatly reduced, which could suggest that Ru radionuclides may be retained more efficiently in the body. These differences could have significant impact on the calculation of dose coefficient after incorporation of Ru radionuclides. (author)

  13. Preparation, characterisation and evaluation of nano MnO2 for uptake of alpha contaminants from radioactive liquid waste

    Radioactive liquid waste is generated during reprocessing of spent nuclear fuel, which is classified as, low level liquid waste (LLW), intermediate level waste (ILW) and high level waste (HLW) based on radioactivity concentration. The strategy for management of LLW and ILW lies in the development and deployment of innovative processes having volume reduction as one of the important parameter. For achieving volume reduction, methodologies based on separation science such as ion exchange, adsorption, extraction etc. are used. Effluents generated during such treatment of LLW will have small concentration of radionuclides like 137Cs, 90Sr, 106Ru, 238U, 239Pu, 241Am etc. These waste streams require treatment to further reduce their activity content following near zero discharge approach. Nano-materials based on the mineral oxides of Si, Al, Ti, Mn, etc., are used as sorbents for heavy metal ions present in waste waters. Oxidative nature of MnO2 has been shown to regulate the concentration of some of the toxic metal ions, viz., Cr, Pb, in estuarine waters. Keeping these properties of MnO2 in mind, in the present study, nanocrystalline manganese oxide was prepared by hydrolysis of potassium permanganate by ethanol. A FT-IR spectrum of the powder was recorded to ensure that there is no organic impurity in the sample due to the alcoholic hydrolysis process. The oxide obtained was characterized for phase analysis and crystallite size estimation using X-ray diffraction technique. The average crystallite size calculated from the Scherrer's formula was found to be ∼ 4 to 8 nm, which is further confirmed from the TEM micrographs. The nano MnO2was evaluated for the sorption characteristics of Pu

  14. The potentialities of the complexation ultrafiltration technique for the decontamination of fission product contaminated aqueous effluents

    Many nuclear researchers and industrial operators lay emphasis on improving the back end of the fuel cycle. A major problem concerns the liquid wastes generated by the reprocessing plant at La Hague, discharged into the sea after treatment in the Effluent Treatment Station (STE) 3), and which have become crucial matter. The activity of these wastes is well below the current legal limits, and is constantly decreasing these last years. To bring it close to zero, and ambitious goal, entails innovative new reprocessing techniques. We accordingly investigated the possibilities of complexation-ultrafiltration, a technique that uses water-soluble macromolecules to complex the target elements to be separated. We first achieved the strontium (II) separation with poly-acrylic and poly-sulfonic acids. The effects of pH and NaNO3 concentration influence on Sr (II) complexation were studied. The Sr (II) complexation and concentration phases, followed by cation de-complexation to recover the polymer, were also taken into account. This research, combined with a potentiometric study of the polymers, offered a close understanding of the chemical systems involved, and of the operating conditions and limits of complexation-ultrafiltration. The laboratory results were also validated on a tangential ultrafiltration pilot plant. We then used complexation-ultrafiltration to treat a real effluent generated bu La Hague's STE 3 plant. This experiment demonstrated minimum 90 % decontamination of Sr (II) (with polyacrylate complexing agent), and also for 134-137Cs (with simple ultrafiltration). The use of two polyamides allowed partial decontamination of the effluent for 60Co and 106Ru. This work therefore offers a global approach to complexation-ultrafiltration, from laboratory to pilot scale, on real and simulated effluents. The future of this technique relies chiefly on the ability to solve the problem of polymer recovery. In other respect, complexation-ultrafiltration clearly offers a

  15. Present Status of the JENDL Project (May, 2014)

    The Japanese Nuclear Data Committee (JNDC) is a research committee for JAEA research activities. It has two subcommittees: Subcommittee on Nuclear Data and Subcommittee on Reactor Constants. The JENDL-4.0 Updated Files (JENDL-4.0u) have been produced to take care of errors which were found after the release of JENDL-4.0. The JENDL-4.0u includes the nuclides whose nuclear data partly revised from important and/or trivial error(s). Thirteen files for JENDL-4.0 were released in 2013. Benchmarking for fission reactor applications was done using test files of Gd-157 and Am-241, and an integral testing for Th-232 was done using KUCA critical experiments. The data which are not updated in JENDL-4.0 are continuously considered to be revised, especially for FP region nuclides. Evaluated results for 141,143Pr, 121,123-126Sb and 96,98-106Ru were published. The R-matrix analysis for O-16 is in progress. For decommissioning of nuclear power plants, evaluation of activation cross sections was planned for 569 reactions with 309 nuclides and is in progress. Evaluated files for the 246 isotopes from H to Hf have been created. As the activity of High Energy Nuclear Data Evaluation WG, development of new JENDL Photonuclear Data File is in progress. Evaluation for 181 nuclides has been finished. A Symposium on Nuclear Data was held on 14-15 November 2013 at Research Institute of Nuclear Engineering, University of Fukui, Tsuruga-shi, with topics about Progress in neutron cross-section measurement and analysis, Application of Nuclear Data, Recent topics, and Progress in studies of high-energy nuclear reaction. A total of 37 papers including 23 poster presentations were presented

  16. Subsurface radionuclide investigation of a nuclear test

    Mathews, M.; Hahn, K.; Thompson, J.; Gadeken, L.; Madigan, W.

    1994-08-01

    This paper reports on an environmental investigation into the vertical distribution of radionuclides from a nuclear test. Dalhart is the name of an underground nuclear test that was executed at the Nevada Test Site at a depth of 2100 ft on October 13, 1988. The test occurred below the static water level of 1667 ft and created multiple radioactive isotopes or fission products. These radioactive isotopes penetrated the surrounding formations and chimney region above the test and were retained there. A 19° 9- {7}/{8}-inch diameter slant hole was drilled to sample the geologic material in the chimney region above the Dalhart test for the purpose of assessing the distribution of radioactivity in and around the shot site. A 30-ft core recovered from a vertical depth of 1628 ft in the collapsed zone or chimney region and above the original static water level was found to be free of radionuclides. Drilling was completed to a vertical depth of 2156 ft with the present static water level at a vertical depth of 1644 ft. Gamma-ray spectroscopy log measurements, made within the drill pipe while drilling fluid was pumped through this pipe, indicate that radioactive material produced by the test was present from the vertical depth interval of 1746-2156 ft. Side-wall samples acquired from the vertical depth interval of 1721-2089 ft and analyzed in the field contained radionuclides such as 137Cs, 125Sb, 106Ru, plus the natural radioactive background of potassium, uranium, and thorium. These samples were sent to Los Alamos to determine the complete radionuclide content at each depth. These analyses were used with the gamma-ray spectroscopy logging data to determine the subsurface vertical radionuclide distribution at the Dalhart site.

  17. Subsurface radionuclide investigation of a nuclear test

    This paper reports on an environmental investigation into the vertical distribution of radionuclides from a nuclear test. Dalhart is the name of an underground nuclear test that was executed at the Nevada Test Site at a depth of 2100 ft on October 13, 1988. The test occurred below the static water level of 1667 ft and created multiple radioactive isotopes or fission products. These radioactive isotopes penetrated the surrounding formations and chimney region above the test and were retained there. A 19o 9-7/8-inch diameter slant hole was drilled to sample the geologic material in the chimney region above the Dalhart test for the purpose of assessing the distribution of radioactivity in and around the shot site. A 30-ft core recovered from a vertical depth of 1628 ft in the collapsed zone or chimney region and above the original static water level was found to be free of radionuclides. Drilling was completed to a vertical depth of 2156 ft with the present static water level at a vertical depth of 1644 ft. Gamma-ray spectroscopy log measurements, made within the drill pipe while drilling fluid was pumped through this pipe, indicate that radioactive material produced by the test was present from the vertical depth interval of 1746-2156 ft. Side-wall samples acquired from the vertical depth interval of 1721-2089 ft and analyzed in the field contained radionuclides such as 137Cs, 125Sb, 106Ru, plus the natural radioactive background of potassium, uranium, and thorium. These samples were sent to Los Alamos to determine the complete radionuclide content at each depth. These analyses were used with the gamma-ray spectroscopy logging data to determine the subsurface vertical radionuclide distribution at the Dalhart site

  18. Urban radionuclide contamination studied in sewage water and sludge from Lund and Gothenburg

    The concentrations of various radionuclides have been measured in the sewage treatment plant serving the town of Lund in southern Sweden. The incoming water, the outgoing water and the sludge have been studied. The measurements started already in 1983 and have gone on since then, which means both before and after the Chernobyl accident. After the accident the concentration of radionuclides was also measured at Gothenburg in western Sweden. The total deposition of the various radionuclides was almost the same 2 kBq/m2 at Lund and Gothenburg although the temporal distribution was somewhat different. The activity concentration measured in the sludge reached a peak value of 87.1 kBq/kg (d.w) for 106Ru and 3.8 kBq/kg for 137Cs at Gothenburgh and of 15.4 and 12.1 k/Bq/kg respectively at Lund. These activity concentrations were measured about 2-3 days after at Lund. The differences in the delays are due to differences in the construction of the plants. The close investigation of the sewage treatment plant at Lund makes it possible to state that about 50 per cent of the incoming 137Cs leaves the plant with the outgoing sludge. It is reasonable to believe that 50 per cent also is valid for the plant at Gothenburg. At Lund the total yearly outgoing activity of 137Cs has fallen exponentially from 900 MBq in 1986 to 100 MBq in 1989. An extrapolation reveals that the activity concentration will be back to pre-Chernobyl levels in 1992/93. But of the original deposition of 12.400 MBq 2/3 or 8.200 MBq will still be left. The same retention factor most probably goes for Gothenburg too. (authors)

  19. Field and model investigations of external gamma dose rates along the Cumbrian coast, NW England

    McDonald, P [Environmental Sciences, Westlakes Scientific Consulting Limited, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3LN (United Kingdom); Bryan, S E [Environmental Sciences, Westlakes Scientific Consulting Limited, Westlakes Science and Technology Park, Moor Row, Cumbria CA24 3LN (United Kingdom); Hunt, G J [Centre for Environment, Fisheries and Aquaculture Science, CEFAS Lowestoft Laboratory, Pakefield Road, Lowestoft, Suffolk NR33 0HT (United Kingdom); Baldwin, M [Centre for Environment, Fisheries and Aquaculture Science, CEFAS Lowestoft Laboratory, Pakefield Road, Lowestoft, Suffolk NR33 0HT (United Kingdom); Parker, T G [British Nuclear Group, Sellafield, Seascale, Cumbria CA20 1PG (United Kingdom)

    2005-03-01

    A survey of the contribution to external dose from gamma rays originating from intertidal sediments in the vicinity of the British Nuclear Group Sellafield site showed that the major anthropogenic contributions were due to {sup 137}Cs and {sup 60}Co. At some sites, traces of other anthropogenic radionuclides were detected, namely {sup 106}Ru, {sup 125}Sb, and {sup 154}Eu. The proportions of fine grained material (<63 {mu}m) were used to improve model predictions of dose contribution due to external exposure to gamma rays, using the CUMBRIA77/DOSE77 model. Model dose predictions were compared to those directly measured in the field. Using the new proportions of fine grained material (1-17.5%) in conjunction with field gamma-ray spectra, model predictions were improved considerably for most sites. Exceptions were at Drigg Barn Scar and Whitehaven Coal Sands sites, which had their own unique characteristics. The highest {sup 60}Co activity concentrations in this study were detected at Drigg Barn Scar. These relatively high activity concentrations of {sup 60}Co were due to the presence of {sup 60}Co in mussels and barnacles, hence upsetting the fine sediment relationships used in previous dose calculations. Whitehaven Coal Sands was unusual in that it contained higher levels of radionuclides than would be expected in sandy sediment. The mineralogy of these sediments was the controlling factor on {sup 137}Cs binding, rather than the proportion of fine grained material. By adjusting the effective fine grained sediment proportions for calculations involving {sup 60}Co and {sup 137}Cs at Drigg Barn Scar and Whitehaven Coal Sands respectively, the CUMBRIA77/DOSE77 model predictions could be improved upon significantly for these sites. This work highlights the influence of particle size and sediment composition on external dose rate calculations, as well as the potential for external dose contributions from biota.

  20. Sulphur containing novel extractants for extraction-separation of palladium (II)

    Extraction performance of palladium (II) by sulphur containing extragents has unequivocally established their strong extraction ability toward this thiophilic soft metal. Hence a comprehensive investigative study was initiated by us to examine selective reversible extraction-separation of trace and macro amounts of palladium (II) from both aqueous nitric acid as well as hydrochloric acid media into 1,2-dichloroethane by 1,10-dithia-18 crown-6 (1,10-DT18C6), S6-pentano-36 (S6-P-36) and bis (2-ethylhexyl) sulphoxide (BESO) dissolved in toluene. From the study of aqueous phase acidity, reagent concentration, period of equilibration, diluent, strippant and diverse ions, conditions are established from its quantitative and reversible extraction. Recovery of Pd(II) from loaded thiacrown and sulphoxide phase is easily accomplished by using sodium thiocyanate, ammonium thiocyanate, thiourea, sodium thiosulphate and mixture of (2M Na2CO3 + 0.5 NH4OH) (only for BESO) as the strippants. The lack of interference from even appreciable amounts of contaminants like 137Cs, 106Ru, 233U and 239Pu may be considered as one of the outstanding advantages of the method. Application of these extractants has been successfully tested for the recovery of palladium from high active waste matrix. The extracted complex from both the thiacrowns has been characterized by elemental analyses and UV-Visible spectra, confirmed to be PdA2.T (A = NO-3, Cl-) from dilute (pH ∼ 2) acid solutions while composition of organic species with palladium for the sulphoxide, has also been confirmed to be disolvate of the type Pd(NO3)2.2BESO. (author). 52 refs., 6 tabs., 6 figs

  1. Study of the ruthenium fission-product behavior in the containment, in the case of a nuclear reactor severe accident; Etude du comportement du produit de fission ruthenium dans l'enceinte de confinement d'un reacteur nucleaire, en cas d'accident grave

    Mun, Ch

    2007-03-15

    Ruthenium tetroxide is an extremely volatile and highly radio-toxic species. During a severe accident with air ingress in the reactor vessel, ruthenium oxides may reach the reactor containment building in significant quantities. Therefore, a better understanding of the RuO{sub 4}(g) behaviour in the containment atmosphere is of primary importance for the assessment of radiological consequences, in the case of potential releases of this species into the environment. A RuO{sub 4}(g) decomposition kinetic law was determined. Steam seems to play a catalytic role, as well as the presence of ruthenium dioxide deposits. The temperature is also a key parameter. The nature of the substrate, stainless steel or paint, did not exhibit any chemical affinities with RuO{sub 4}(g). This absence of reactivity was confirmed by XPS analyses, which indicate the presence of the same species in the Ru deposits surface layer whatever the substrates considered. It has been concluded that RuO{sub 4}(g) decomposition corresponds to a bulk gas phase decomposition. The ruthenium re-volatilization phenomenon under irradiation from Ru deposits was also highlighted. An oxidation kinetic law was determined. The increase of the temperature and the steam concentration promote significantly the oxidation reaction. The establishment of Ru behavioural laws allowed making a modelling of the Ru source term. The results of the reactor calculations indicate that the values obtained for {sup 106}Ru source term are closed to the reference value considered currently by the IRSN, for 900 MWe PWR safety analysis. (author)

  2. New techniques for the treatment of laundry and other low-level liquid wastes

    PART I: The liquid wastes arising in BWR plants are generally classified under four types. Usually, three are reused as feed water after filtration, concentration and demineralization, while laundry liquid waste is discharged into the environment. Studies were made on laundry liquid waste treatment in order to establish a closed liquid waste system by using foamless detergent and evaporation treatment. It was demonstrated in pilot plant experiments that no foaming was caused during continuous concentration test runs from 500 to 200000 ppm. Then, the concentrated liquid was dried by LUWA wiped film vertical drier. The total volume reduction ratio through this concentration-drying system was calculated to be 1/2000. This treatment system may well be expected to have a potentiality of practical application in a few years to nuclear power plants in Japan. PART II: Although it is known that iron or iron compounds are effective in removing ruthenium, any satisfactory continuous treatment method of removing ruthenium present in minute quantities in the liquid waste has not yet been reported in the published literature. Based on the preliminary batch tests, column experiments using steel wool as the filter medium with activated surface layers produced by saturated steam were carried out mainly to develop a continuous method for industrial application. Some of the results of test runs made at a space velocity of 50m3.m-3.h-1, with 106Ru spiked laboratory demineralized water clearly showed that the DFs of more than 100 were obtained even after treatment of the volume of liquid 10000 times the bed volume. (author)

  3. Summary technical report on the electrochemical treatment of alkaline nuclear wastes

    This report summarizes the laboratory studies investigating the electrolytic treatment of alkaline solutions carried out under the direction of the Savannah River Technology Center from 1985-1992. Electrolytic treatment has been demonstrated at the laboratory scale to be feasible for the destruction of nitrate and nitrite and the removal of radioactive species such as 99Tc and 106Ru from Savannah River Site (SRS) decontaminated salt solution and other alkaline wastes. The reaction rate and current efficiency for the removal of these species are dependent on cell configuration, electrode material, nature of electrode surface, waste composition, current density, and temperature. Nitrogen, ammonia, and nitrous oxide have been identified as the nitrogen-containing reaction products from the electrochemical reduction of nitrate and nitrite under alkaline conditions. The reaction mechanism for the reduction is very complex. Voltammetric studies indicated that the electrode reactions involve surface phenomena and are not necessarily mass transfer controlled. In an undivided cell, results suggest an electrocatalytic role for oxygen via the generation of the superoxide anion. In general, more efficient reduction of nitrite and nitrate occurs at cathode materials with higher overpotentials for hydrogen evolution. Nitrate and nitrite destruction has also been demonstrated in engineering-scale flow reactors. In flow reactors, the nitrate/nitrite destruction efficiency is improved with an increase in the current density, temperature, and when the cell is operated in a divided cell configuration. Nafion reg-sign cation exchange membranes have exhibited good stability and consistent performance as separators in the divided-cell tests. The membranes were also shown to be unaffected by radiation at doses approximating four years of cell operation in treating decontaminated salt solution

  4. Off-gas treatment and characterization for a radioactive in situ vitrification test

    Effluents released to the off gas during the in situ vitrification (ISV) of a test site have been characterized. The site consisted of a 19 L waste package of soil containing 600 nCi/g transuranic and 30,000 nCi/g mixed fission products surrounded by uncontaminated soil. Radioactive isotopes present in the package were 241Am, /sup 238/239/Pu, 137Cs, 106Ru, 90Sr, and 60Co. The ISV process melted the waste package and surrounding soil and immobilized the radionuclides in place, producing a durable, 8.6 metric ton glass and crystalline monolith. The test successfully demonstrated that the process provides containment of radioactive material. No release to the environment was detected during processing or cooldown. Due to the high temperatures during processing, some gases were released into the off-gas hood that was placed over the test site. The hood was maintained at a light negative pressure to contain any volatile or entrained material during processing. Gases passed from the hood to an off-gas treatment system where they were treated using a venturi-ejector scrubber, a tandem nozzle gas cleaner scrubber followed by a condenser, heater, and two stages of HEPA filters. The off-gas treatment system is located in the semi-trailer to allow transport of the process to other potential test sites. Retention of all radionuclides by the vitrified zone was greater than 99%. Soil-to-off-gas decontamination factors (DFs) for transuranic elements averaged greater than 4000 and for fission products, DFs ranged from 130 for 137Cs to 3100 for 90Sr

  5. Environmental monitoring report on radiological status of the ground water beneath the Hanford site, January--December 1974

    Evaluation of β/sub t/, 3H and NO3/sup -/ concentrations measured in well water sampled near the surface of the unconfined ground water during 1974 shows that zones of contamination extend in an easterly to south-easterly direction from 200-E Area, as has been observed in the past. Tritium and NO3- ion concentrations above background were found along the Columbia River in the vicinity of the 100 Areas. A low ground-water mound showing uranium and nitrate ion concentrations above background continues to be observed in the 300 Area. Gross beta activity in the ground water beneath the 100 Areas was detectable only at the 100-N Area from effluent discharged to the 1301-N crib. A number of radionuclides, such as 106Ru, 60Co, 129I, 137Cs and 90Sr, occur at various locations and are detectable in very low concentrations in the unconfined ground water external to the 200 Areas. In most cases, concentrations are several orders of magnitude below applicable CG's and are so close to the detection limit as to cast doubt of their existence based on a single analysis. Only in and adjacent to the 200 Areas does any radionuclide that was analyzed in CY-1974 occur in concentrations greater than 10 percent of the applicable CG for uncontrolled water use. Nitrate ion concentrations greater than 100 percent of the Public Health Service (PHS) recommended drinking water standard of 45 mg/l continued to be observed in the ground water adjacent to the 200 Areas; in the vicinity of the 100-F and 300 Areas; and in the east-central part of the Hanford site (Wells 20-20, 26-15, and 32-22). Ground water from these zones is not consumed by human beings or other animals

  6. Data summary report for fission product release test VI-4

    This was the fourth in a series of high-temperature fission product release tests in a vertical test apparatus. The test specimen, a 15.2-cm-long section of a fuel rod from the BR3 reactor in Belgium, had been irradiated to a burnup of 47 MWd/kg. In simulation of a severe accident in a light-water reactor, it was heated in hydrogen in a hot cell-mounted test apparatus to a maximum test temperature of 2400 K for a period of 20 min. The released fission products were collected on components designed to facilitate sampling and analysis. On-line radioactivity measurements and posttest inspection revealed that the fuel had partially collapsed at about the time the cladding melted. Based on fission product inventories measured in the fuel or calculated by ORIGEN2, analyses of test components showed total releases from the fuel of 85% for 85Kr, 106Ru, 3.9% for 125Sb, 96% for both 134Cs and 137Cs, and 13% for 154Eu. Large fractions of the released fission products (up to 96% of the 154Eu) were retained in the furnace. Small release fractions for several other fission products -- Rb, Br, Sr, Te, I, and Ba -- were detected also. In addition, very small amounts of fuel material -- uranium and plutonium -- were released. Total mass release from the furnace to the collection system, which included fission products, fuel material, and structural materials, was 0.40g, with 40% of this material being deposited as vapor and 60% of it being collected as aerosols. The results from this test were compared with previous tests in this series and with an in-pile test at similar conditions at Sandia National Laboratories. There was no indication that the mode of heating (fission heat vs radiant heat) significantly affected fission product release. 24 refs., 25 figs., 14 tabs

  7. Off-gas treatment and characterization for a radioactive in situ vitrification test

    Effluents released to the off gas during the in situ vitrification (ISV) of a test site have been characterized by Pacific Northwest Laboratory. The site consisted of a 19 L waste package of soil containing 600 nCi/g transuranic and 30,000 nCi/g mixed fission products surrounded by uncontaminated soil. Radioactive isotopes present in the package were 241Am, 238/239Pu, 137Cs, 106Ru, 90Sr, and 60Co. The ISV process melted the waste package and surrounding soil and immobilized the radionuclides in place, producing a durable, 8.6 metric ton glass and crystalline monolith. The test successfully demonstrated that the process provides containment of radioactive material. No release to the environment was detected during processing of cooldown. Due to the high temperature during processing, some gases were released into the off-gas hood that was over the test site. The hood was maintained at a slight negative pressure to contain any volatile or entrained material during processing. Gases passed from the hood to an off-gas treatment system where they were treated using a venturi-ejector scrubber, a tandem nozzle gas cleaner scrubber followed by a condenser, heater, and two stages of HEPA filters. The off-gas treatment system is located in the semi-trailer to allow transport of the process to other potential test sites. Retention of all radionuclides by the vitrified zone was greater than 99%. Soil-to-off-gas decontamination factors (DFs) for transuranic elements averaged greater than 4000 and for fission products, DFs ranged from 130 for 137Cs to 3100 for 90Sr. 7 references, 15 figures, 4 tables

  8. The state of the art on nuclides separation in high level liquid wastes by Truex process

    For the advancement of the back-end of nuclear fuel cycle, novel CMPO RUEX process was studied for separating minor actinides from fission products in high level liquid waste using real radioactive solutions from PUREX experiments, so as to support PNC's actinides recycling program using fast reactor. The present PUREX process was also studied to improve the separation of 237Np, 106Ru and 99Tc, the most interfering-natured nuclides in both PUREX and TRUEX processes, by utilizing electrochemistry-based salt-free methods which can eliminate the secondary radioactive waste. The state of the art of separation technologies are described by summarizing the extraction behaviors of nuclides in recent hot counter-current runs using CMPO RUEX process with mild salt-free stripping reagents. The degradation and regeneration characteristics of CMPO/TBP/n-dodecane mixture solvent were also simulated by semi-hot experiments. Several experiments to separate minor actinides and lanthanides from the TRUEX mixture product using aqueous amino-poly-carboxylate complexant, DTPA, resulted in reasonable MA/Ln separation profiles in multiple mixer-settler stages and allowed a unique separation flowsheet adaptable to the TRUEX process to be proposed. Application of electrochemistry to assist both solvent extraction processes, e.g., 'anodic oxidation' to destroy PUREX and TRUEX solvent waste in the presence of electron transfer mediator Age2+ or 'cathodic reduction' for electrolytic extraction of Pd2+, RuNO3+ and 99TcO4- from 3 M nitric acid medium is under study. (authors)

  9. The potentialities of the complexation ultrafiltration technique for the decontamination of fission product contaminated aqueous effluents; Potentialites de la complexation - ultrafiltration a la decontamination d`effluents radioactifs en produits de fission

    Thibert, V.

    1995-07-01

    Many nuclear researchers and industrial operators lay emphasis on improving the back end of the fuel cycle. A major problem concerns the liquid wastes generated by the reprocessing plant at La Hague, discharged into the sea after treatment in the Effluent Treatment Station (STE) (3), and which have become crucial matter. The activity of these wastes is well below the current legal limits, and is constantly decreasing these last years. To bring it close to zero, and ambitious goal, entails innovative new reprocessing techniques. We accordingly investigated the possibilities of complexation-ultrafiltration, a technique that uses water-soluble macromolecules to complex the target elements to be separated. We first achieved the strontium (II) separation with poly-acrylic and poly-sulfonic acids. The effects of pH and NaNO{sub 3} concentration influence on Sr (II) complexation were studied. The Sr (II) complexation and concentration phases, followed by cation de-complexation to recover the polymer, were also taken into account. This research, combined with a potentiometric study of the polymers, offered a close understanding of the chemical systems involved, and of the operating conditions and limits of complexation-ultrafiltration. The laboratory results were also validated on a tangential ultrafiltration pilot plant. We then used complexation-ultrafiltration to treat a real effluent generated bu La Hague`s STE 3 plant. This experiment demonstrated minimum 90 % decontamination of Sr (II) (with polyacrylate complexing agent), and also for {sup 134-137}Cs (with simple ultrafiltration). The use of two polyamides allowed partial decontamination of the effluent for {sup 60}Co and {sup 106}Ru. This work therefore offers a global approach to complexation-ultrafiltration, from laboratory to pilot scale, on real and simulated effluents. The future of this technique relies chiefly on the ability to solve the problem of polymer recovery. (Abstract Truncated)

  10. Laboratory development of methods for centralized treatment of liquid low-level waste at Oak Ridge National Laboratory

    Improved centralized treatment methods are needed in the management of liquid low-level waste (LLLW) at Oak Ridge National Laboratory (ORNL). LLLW, which usually contains radioactive contaminants at concentrations up to millicurie-per-liter levels, has accumulated in underground storage tanks for over 10 years and has reached a volume of over 350,000 gal. These wastes have been collected since 1984 and are a complex mixture of wastes from past nuclear energy research activities. The waste is a highly alkaline 4-5 M NaNO3 solution with smaller amounts of other salts. This type of waste will continue to be generated as a consequence of future ORNL research programs. Future LLLW (referred to as newly generated LLLW or NGLLLW) is expected to a highly alkaline solution of sodium carbonate and sodium hydroxide with a smaller concentration of sodium nitrate. New treatment facilities are needed to improve the manner in which these wastes are managed. These facilities must be capable of separating and reducing the volume of radioactive contaminants to small stable waste forms. Treated liquids must meet criteria for either discharge to the environment or solidification for onsite disposal. Laboratory testing was performed using simulated waste solutions prepared using the available characterization information as a basis. Testing was conducted to evaluate various methods for selective removal of the major contaminants. The major contaminants requiring removal from Melton Valley Storage Tank liquids are 90Sr and 137Cs. Principal contaminants in NGLLLW are 9OSr, 137Cs, and 106Ru. Strontium removal testing began with literature studies and scoping tests with several ion-exchange materials and sorbents

  11. Relation between physicomechanical properties and diffusion phenomena in composite materials

    One of the procedures for storing low and medium activity nuclear waste consists of coating the contaminated material in a thermosetting resin. The drums thus constitued are stored in concreted underground trenches, then covered with cement, bitumen or clayey soil. Although the risk of water circulation is low, this element represents on the one hand the major cause of natural deterioration of the polymer, and on the other hand the most likely vehicle for conveying the radioactive ions confined in the drums. It is for this reason that the study of the behaviour of polyester or epoxide-based macromolecular materials with regard to water constitutes the first stage of this work. The second part of the thesis is directed towards the study of compound materials. Indeed, the charges are represented in the first case by the nuclear waste itself; in the second case, they are introduced into the polymer beforehand, on the one hand to reduce costs, and on the other hand to give the mixture suitable mechanical and rheological properties. In this study, three types of mineral charge are added in an epoxide resin: glass balls surface-treated or not, and sand. Various techniques are implemented in order to assess and characterize the interfacial adhesion, in the different systems. The strongest polymer-charge bonds are sought in order to resist natural deterioration. Finally, the object of the confinement process, is to avoid dispersion of low and medium activity substances (137Cs, 90Sr, 60Co, 106Ru..) in the environment. The final stage of this work therefore consists in assessing the barrier qualities of pure or charged polymers with regard to radioactive ion diffusion. We will show in particular that the use of fine resin membranes enables the diffusion coefficient of the 137Cs to be calculated

  12. The situation of marine sediments in the pathway of radionuclides to man

    It is widely accepted that the marine sediments are the major reservoir of the radionuclides which are discharged into the coastal sea water. The radionuclides sorpted on the sediments would be recycled in the sea water and be accumulated by marine organisms. And some of the sorpted radionuclides would be transfered to the worm (a kind of benthos) habited in the sediments through their surface or digestive tract and then to the fishes which prey upon the benthos. Therefore, it is important to learn whether the sediments as a ''sink'' may not later become a ''source'' of these contaminants. In this paper, the problem is discussed refering to few reports which are published up to this time. Renfro estimated that about one per cent of 65Zn in the sediment would be transfered to Nereis diversicolor which directly contacts with the sediments: On the recycling of 65Zn from the sediments to the sea water, Seymour and Nelson determined the 65Zn level of 8/100 in the sea water after twelve months following shutdown of reactor. Thus they calculated the ecological half-lives which were affected by the radionuclides retention of the sediments. In our laboratory experiment on the interaction of sediments and Nereis diversicolor using 95Zr, 106Ru, 137Cs and 60Co, the similar results were observed except 137Cs which showed rather high rate of remobilization from the sediments to the sea water. Thus, it could be generally considered that the transfer of radionuclides via sediment would be minor to man. However, it should be born in mind that the increased amount of radionuclides by continuous discharge into sea may raise the level of radionuclides in the sediments and then benthos even with one per cent transfer rate from sediment to benthos. (auth.)

  13. Chernobyl fallout in southern and central Finland

    To study the levels and distributions of radionuclides released in the Chernobyl accident, we sampled surface peat from 62 sites in Southern and Central Finland and measured 131I, 134Cs, 137Cs, 132Te, 140Ba, 103Ru, 90Sr, 141Ce, and 95Zr. The distribution of fallout activities was highly uneven, depending on movement of the contaminated air mass and rainfall distribution during the critical days. The highest values observed were 420 kBq m-2 of 131I and 70 kBq m-2 of 137Cs. The nuclide ratios showed wide and partly unexpected variations. The high-boiling-point, or nonvolatile, elements Ce and Zr were spread mostly on a 200-km-wide zone extending across Finland from southwest to northeast. The more volatile elements, I, Ce, and Te, showed quite a different, more widespread, fallout distribution, while an intermediate behavior was observed for Ba, Ru, and possibly Sr. These results can be explained by assuming that pulverized nuclear fuel material released in the reactor explosion on 26 April reached Finland via Poland and the Baltic Sea and traversed the country along the above-mentioned narrow zone, while volatile material, evaporated in the reactor fire from 26 April to 5 May, arrived in several waves and was consequently more widely and evenly spread. From their elemental melting and boiling points, Ru and Mo would appear to belong to the nonvolatile group and Sr to the volatile. Yet, their actual behaviors were opposite; Ru in particular was found in the nonvolatile as well as the volatile fallout, possibly because Ru activities were present in the fuel partly in the metallic state and partly as volatile oxides

  14. Influence of fentanyl and morphine on intestinal circulation

    Tverskoy, M.; Gelman, S.; Fowler, K.C.; Bradley, E.L.

    1985-06-01

    The influence of fentanyl and morphine on the intestinal circulation was evaluated in an isolated loop preparation in 37 dogs anesthetized with pentobarbital intravenously. Selected intestinal segments were pumped with aortic blood at a constant pressure of 100 mm Hg. A mixture of /sup 86/Rb and 9-micron spheres labeled with /sup 141/Ce was injected into the arterial cannula supplying the intestinal loop, while mesenteric venous blood was collected for activity counting. A strong correlation was found between the clearances of rubidium and microspheres (r = 0.97, P less than 0.0001), suggesting that the shunting of 9-micron spheres through the intestines reflects the shunting of blood through nonnutritive vessels. Intravenous fentanyl decreased oxygen uptake (O/sub 2/up), and vascular resistance (VR), and increased blood flow (BF), rubidium and microsphere clearances (Cl-Rb, Cl-Sph, respectively), and permeability--surface area product (PS) in a dose-related fashion. Intravenous morphine in a dose of 1 mg X kg-1 increased Cl-Rb (nutritive BF) without changes in total (nutritive and nonnutritive) BF. This increase in nutritive BF is probably related to morphine-induced histamine release. Morphine in a dose of 5 mg X kg-1 was accompanied by vasoconstriction that was completely abolished by alpha-adrenoceptor blockade. The data suggest that morphine-induced intestinal vasoconstriction is mediated via a release of epinephrine, apparently from the adrenal medulla. It is concluded that changes in the intestinal circulation during anesthesia with narcotics might play a certain role in the cardiovascular homeostasis during anesthesia and surgery. An increase in oxygen content in portal venous blood, resulting from a decrease in intestinal oxygen uptake, should facilitate hepatic oxygenation.

  15. Influence of fentanyl and morphine on intestinal circulation

    The influence of fentanyl and morphine on the intestinal circulation was evaluated in an isolated loop preparation in 37 dogs anesthetized with pentobarbital intravenously. Selected intestinal segments were pumped with aortic blood at a constant pressure of 100 mm Hg. A mixture of 86Rb and 9-micron spheres labeled with 141Ce was injected into the arterial cannula supplying the intestinal loop, while mesenteric venous blood was collected for activity counting. A strong correlation was found between the clearances of rubidium and microspheres (r = 0.97, P less than 0.0001), suggesting that the shunting of 9-micron spheres through the intestines reflects the shunting of blood through nonnutritive vessels. Intravenous fentanyl decreased oxygen uptake (O2up), and vascular resistance (VR), and increased blood flow (BF), rubidium and microsphere clearances (Cl-Rb, Cl-Sph, respectively), and permeability--surface area product (PS) in a dose-related fashion. Intravenous morphine in a dose of 1 mg X kg-1 increased Cl-Rb (nutritive BF) without changes in total (nutritive and nonnutritive) BF. This increase in nutritive BF is probably related to morphine-induced histamine release. Morphine in a dose of 5 mg X kg-1 was accompanied by vasoconstriction that was completely abolished by alpha-adrenoceptor blockade. The data suggest that morphine-induced intestinal vasoconstriction is mediated via a release of epinephrine, apparently from the adrenal medulla. It is concluded that changes in the intestinal circulation during anesthesia with narcotics might play a certain role in the cardiovascular homeostasis during anesthesia and surgery. An increase in oxygen content in portal venous blood, resulting from a decrease in intestinal oxygen uptake, should facilitate hepatic oxygenation

  16. Determination of selenium and zinc in human serum by instrumental neutron activation analysis with a cerium internal standard

    An instrumental neutron activation analysis (INAA) method for simultaneously determining the Se and Zn concentrations in serum specimen was developed in order to study and clarify the associations between prediagnostic serum Se and Zn, and the subsequent risk of lung and stomach cancer in which the amount of available sera was quite limited. Cerium was used as an internal standard in order to maintain the accuracy and precision, even with less than 0.2 ml of a sample and short measuring time. Samples, (0.1 ∼ 0.2 ml), and Se-Zn standard solutions were mixed with exact amounts of the Ce standard solution, respectively. After lyophilization, the samples were sealed in a high-purity quartz tube. The Se-Zn standard solutions were also sealed in a quartz tube without lyophilization. The samples and standards were irradiated in the JRR-2 with a thermal neutron flux of more than 2.2 x 1013 n cm-2s-1 for 265.5 hours. After cooling for one month, about 5 μm surface layers of the quartz ampule for the samples and standards were etched with hydrofluoric acid; γ-ray spectra were then measured with a Ge(Li) detector. The contents of Se and Zn were obtained from the peak area of γ-rays of 145, 265 and 1115 keV for 141Ce, 75Se and 65Zn, respectively. The relative standard deviations of the analytical results among the 14 independent samples were 3.0 and 5.0% for Se and Zn, respectively. The accuracy of the present method was confirmed by the satisfactory agreement between the results obtained by the present method and those obtained by other methods, including the certified values of NIST Standard Reference Materials of Bovine Liver (SRM1577, SRM1577a). (author)

  17. Influence of gamma irradiation on conductivity of YBa2Cu3O7

    We report a study on influence of gamma irradiation on conductivity of YBa2Cu3O7. We have measured the mass attenuation coefficient, effective atomic number, electron density and electrical conductivity for various gamma sources of energy ranging from 0.084 MeV to 1.330 MeV (170Tm, 57Co, 141Ce, 203Hg, 51Cr, 113Sn, 22Na, 137Cs, 60Co, 22Na and 60Co). The measured values agree with the theoretical values. The values of these parameters have been found to change with energy and interaction of gamma. We find evidence for a variation of the electrical conductivity of YBa2Cu3O7 with the irradiated photon energy and this variation is shown in figures up to 105 MeV. The variations of effective atomic number and electron density with energy are shown graphically for all photon interactions. Conductivity found to vary with the energy of the irradiated gamma radiation and interaction process of gamma. This kind of studies is important in the field of superconductivity. - Highlights: • We have studied the influence of gamma irradiation on conductivity of YBa2Cu3O7. • We find evidence for a variation of the electrical conductivity of YBa2Cu3O7 with the irradiated photon energy. • The conductivity of YBa2Cu3O7 found to vary with the interaction process of gamma. • This kind of studies is important in the field of superconductivity

  18. Communication of nuclear data progress: No.14 (1995)

    Communication of Nuclear Data Progress (CNDP) in English is set up by Chinese Nuclear Data Center. This is the fourteenth issue, in which the achievements in nuclear data field for the last year in P.R. China are published. It includes the measurements of neutron activation cross sections for 64Zn(n,γ)65Zn, 23Na(n,2n)22Na, 92Mo(n,p)92mNb, 94Mo(n,2n)93mMo, 98Mo(n,p)98mNb, Ba(n,x)134Cs, 134Ba(n,2n)133Ba, 137Ba(n,p)137Cs, 140Ce(n,2n)139Ce, 142Ce(n,2n)141Ce, 179Hf(n,2n)178m2Hf and 209Bi(n,2n)208Bi reactions; calculation of neutron induced reactions on nuclides 175,176,NatLu and 89Y (emphatically on γ-production data); a γ-production data intercomparison system and intercomparison of Fe, Cr, Ni γ-production data; evaluations of n + 56Fe, 58,60,61,62,64,NatNi(n,α), 93Nb(n,2n), (n,n') and 58Ni, 87Rb, 89Y, 90Zr, 140Ce, 169Tm(n,2n) reaction cross sections; sensitivity of logft on ε branching to ground state of 197Au in decay of 197Hg; evaluated particle reflection data base, physical sputtering simulated calculation; progress on parameter and program libraries

  19. Determination of the Ce142(γ,n) cross section using quasi-monoenergetic Compton backscattered γ rays

    Sauerwein, A.; Sonnabend, K.; Fritzsche, M.; Glorius, J.; Kwan, E.; Pietralla, N.; Romig, C.; Rusev, G.; Savran, D.; Schnorrenberger, L.; Tonchev, A. P.; Tornow, W.; Weller, H. R.

    2014-03-01

    Background: Knowing the energy dependence of the (γ,n) cross section is mandatory to predict the abundances of heavy elements using astrophysical models. The data can be applied directly or used to constrain the cross section of the inverse (n,γ) reaction. Purpose: The measurement of the reaction Ce142(γ,n)141Ce just above the reaction threshold amends the existing experimental database in that mass region for p-process nucleosynthesis and helps to understand the s-process branching at the isotope Ce141. Method: The quasi-monoenergetic photon beam of the High Intensity γ-ray Source (HIγS), TUNL, USA, is used to irradiate naturally composed Ce targets. The reaction yield is determined afterwards with high-resolution γ-ray spectroscopy. Results: The experimental data are in agreement with previous measurements at higher energies. Since the cross-section prediction of the Ce142(γ,n) reaction is exclusively sensitive to the γ-ray strength function, the resulting cross-section values were compared to Hauser-Feshbach calculations using different γ-ray strength functions. A microscopic description within the framework of the Hartree-Fock-BCS model describes the experimental values well within the measured energy range. Conclusions: The measured data show that the predicted (γ,n) reaction rate is correct within a factor of 2 even though the closed neutron shell N =82 is approached. This agreement allows us to constrain the (n,γ) cross section and to improve the understanding of the s-process branching at Ce141.

  20. The activity of γ-emitters as measured by ionisation chambers the determination of the specific emission coefficient γ for some radio-elements (1961)

    The object of this work is to study techniques of measurement using the gamma ionisation chamber, making it possible either to measure the activities of radioactive sources, or to determine the specific emission coefficient γ (or the coefficient K) of a given radioelement. The ionisation chambers studied belong to two categories: graphites cavity-chambers, and 4 π γ chambers. For the cavity-chamber measurements, the different correction factors of which account must be taken have been calculated, in particular the geometric and hygrometric corrections. The absorption and auto-absorption corrections have led to the introduction of the notion of the 'effective energy γ' of a radioelement. In the case of 4 π γ chambers, it has been shown that appropriately shaped electrodes make it possible to improve their performances. One of the chambers described permits the measurement of β emitters using the associated Bremsstrahlung. In order to measure the K coefficient of some radioelements, it has been found useful a 4 π γ chamber with graphite walls, the measurement being carried out by comparison with a radium standard. The validity of the method was checked with radioelements for whom the K coefficient values are well-known (24Na, 60Co, 131I, 198Au). For other radioelements, the following values were obtained (expressed in r cm3 mc-1 h-1): 51Cr: 0,18; 56Mn: 8,8; 65Zn: 3,05; 124Sb: 9,9; 134Cs: 9,3; 137Cs: 3,35; 141Ce: 0,46; 170Tm: 0,023; 192Ir: 24,9; 203Hg: 1,18; These values have been corrected for the contribution to the dose of the fluorescent radiation which may be emitted by the source, except in the case of Tm170. In the last part of this work, the performances of the different electro-metric devices used were compared. (author)

  1. Permeability of polymer materials to compounds containing radionuclides

    The permeability of rubber and PE gloves, PE bags and strippable PVC paint to HTO, Na125I, H235SO4, H332PO4, 141CeCl3, 89SrCl2, and 137CsCl in aqueous solution was tested. All materials were permeable to HTO and Na125I. Whereas rubber gloves were permeable the other materials were impermeable to H235SO4. The remaining radioactive compounds showed no penetration. The diffusion coefficients of the penetrating compounds were calculated on the basis of the diffusion law of Fick for respective materials. The permeability to Na125I and HTO decreases in the order rubber, PVC paint, and PE. Penetration increases in the order H235SO4, Na125I, and HTO. It is assumed that liquid HTO penetrates polymer materials in molecular form according to the behaviour of gaseous HTO or normal water vapour. H235SO4 can penetrate the rubber in molecular or ionic form. The behaviour of Na125I is complex as the shape of the curve shows. The diffusion coefficients of PE are not in agreement with those obtained in the earlier experiments. It is assumed that 125I penetrates the materials in form of 125I2 molecules produced by oxidation. The permeability of PE bag foils to Na125I was decreased by addition of NaHSO3 as a reducing agent. However, the obtained values could not be interpreted because a precipitate was formed in the solution. A fUrther cause for the bad reproducibility of the diffusion coefficients can be the oxidation of iodide to iodate or periodate. (T.G.)

  2. The measurement of radioactive microspheres in biological samples

    Measurements of the distribution of radioactive microspheres are used in investigations of regional coronary blood flow, but the size and shape of the heart varies for different test animals, and the organ is frequently divided into smaller pieces for studies of regional perfusion. Errors are introduced by variations in the distribution of the radioactive source and the amount of Compton scatter in different samples. A technique has therefore been developed to allow the counting of these tissue samples in their original form, and correction factors have been derived to inter-relate the various counting geometries thus encountered. Dogs were injected with microspheres labelled with 141Ce, 51Cr or 85Sr. The tissue samples did not require remodelling to fit a standard container, and allowance was made for the inhomogeneous distribution in the blood samples. The activities in the centrifuged blood samples were correlated with those from the tissue samples by a calibration procedure involving comparisons of the counts from samples of microspheres embedded in sachets of gelatine, and similar samples mixed with blood and then centrifuged. The calibration data have indicated that 51Cr behaves anomalously, and its use as a label for microspheres may introduce unwarranted errors. A plane cylindrical 10 x 20 cm NaI detector was used, and a 'worst case' correction of 20% was found to be necessary for geometry effects. The accuracy of this method of correlating different geometries was tested by remodelling the same tissue sample into different sizes and comparing the results, and the validity of the technique was supported by agreement of the final results with previously published data. (U.K.)

  3. Selective arterialization of the coronary venous system. Encouraging long-term flow evaluation utilizing radioactive microspheres

    The long-term effectiveness of a retrograde coronary venous bypass graft (CVBG) to an ischemic left ventricle was evaluated in 18 dogs. A saphenous vein was interposed between the aorta and left anterior descending (LAD) vein. The LAD vein was ligated cephalad to the CVBG to prevent an arteriovenous fistula. The LAD artery was ligated at its origin to create anterior wall ischemia. Operative graft flow averaged 53 ml. per minute. The 14 surviving dogs were catheterized 3 to 5 months later. Ten of the 14 CVBG's were patent angiographically. The chests were opened and graft flow now averaged 50 ml. per minute. 141Ce microspheres were injected into the left atrium to measure myocardial flow to the anterior wall. In the 10 dogs with patent grafts, transmural flow was 39 +- 1 (S.E.M.) ml. per 100 Gm. of tissue per minute. The endocardial/epicardial flow ratio was 1.4/1, indicating that retrograde venous perfusion effectively delivered blood to the subendocardium. After ligation of the CVBG, microsphere measured flow dropped to 15 +- 1 ml. per 100 Gm. per minute. In 15 control dogs, anterior wall flow was 100 +- 3 ml. per 100 Gm. per minute, decreasing to 13 +- 2 ml. 45 minutes after ligation of the LAD artery and vein. None of the eight control dogs with simple ligation of the LAD artery and vein survived more than 5 days. Histologic examination of the anterior wall of the left ventricle, the area served by the CVBG's for 3 to 5 months, disclosed no evidence of venous sclerosis or thrombosis and no evidence of interstitial edema or hemorrhage. Thus a CVBG permitted long-term survival in an otherwise nonviable anatomic preparation. Moreover, restoration of flow with a CVBG was effective because it perfused all layers of the myocardium, especially the subendocardium - the crucial layer of myocardial muscle

  4. Experimental Fission Gas Release Determination at High Burnup by Means of Gamma Measurements on Fuel Rods in OL2

    This article presents the results from the gamma measurements performed on a selection of fuel rods from two SVEA-96 Optima fuel assemblies in Olkiluoto unit 2 (OL2) during February 2008. The measurements were funded by Teollisuuden Voima Oyj (TVO) and carried out by Westinghouse Electric Sweden AB (WSE). The goal of the measurements was to obtain plant specific fission gas release data from OL2 which will later be used to support TVO's burnup increase. The measurements were performed by means of detecting and recording information on gamma rays emanating from radioactive fission products within the fuel rods. A fuel assembly under operation in the reactor will be subject to fission gas release, meaning that gaseous fission products in the fuel matrix will leak out into the fuel rod free volumes, including the upper fuel rod plenum. The magnitude of fission gas release is closely related to the operation conditions, such as burnup and the pellet power/temperature history. Fission gas which is released into the plenum leads to an increased pressure within the fuel rod. Since the gas plenum is a volume free of fuel pellets, radioactive gases present here are therefore relatively easy to measure. A suitable gaseous radioactive fission product is 85Kr which has a gamma energy of 514 keV, and a half life of 10.8 years. Measuring the amount of 85Kr can then be used to quantify the amount of fission gases release during operation. Other sources of gamma rays in the plenum with similar energies are the β+-emitting 58Co and the 106Ru. The half lives of 58Co and 106Ru are 71 days and 372 days, respectively, with corresponding gamma ray energies of 511 keV and 512 keV, respectively. In total, three different gamma rays with similar energies must be resolved by the detector system. In order to perform the measurements, 58Co must have decayed to an extent that allows the 514 keV line to be resolved from the 511 keV positron annihilation gamma ray. The 106Ru is, on the other

  5. Radioecological synthesis of the various compartments of La Hague (Cotentin) marine environment

    Permits for low level radioactive liquid waste releases by the LA HAGUE (Cotentin, France) fuel reprocessing plant are based on an accurate radioecological study of the marine environment. Since 1967, the monitoring of indicators such as seawater, sediments and marine organisms (Fucus serratus, Laminaria sp., Mytilus sp., ...) have made it possible to create an important environmental data base. A statistical treatment has been used to quantify the spatio-temporal (daily, seasonal, local and regional) variabilities of these indicators from 1975 up to now. It has demonstrated the interest of F. serratus seaweed as bioindicators of radioactivity. Moreover it appears that seawater-soluble radionuclides such as 125Sb and 137Cs are monitored through longer distance from the outlet than those bound to particles such as 144Ce. A study of the sestonic load by satellite images suggested a number of geographical sites of potential accumulation through particle transport, some of which were verified by radioactivity measurements of sediments. However, such accumulation was not confirmed by the particle size distribution at the level of the Cap de LA HAGUE associated with radioactive measurements of seawater. A spectral analysis of biota radioactive levels vs radioactive waste releases showed a time delay of 2 - 4 months for F. serratus and Mytilus sp. collected in the local area of LA HAGUE after either an increase or a decrease of the releases. Modeling of marine currents fields associated with a transfer model can now be used to predict, at small time scales, the radioactivity levels inthe various Cotentin marine compartments from the liquid waste releases

  6. The behaviour of hot particles in the organism of cattle

    Radionuclide deposition in various organs of lactating cattle and their physiological effect has been studied. Model hot particles similar to those from Chernobyl accident are used. Two types of particles (washed and unwashed condensed phase) have been introduced in gastrointestinal tract (GIT) of the cattle. Particle dynamics in the GIT, radionuclide transfer to animal organism and possible biological consequences have been studied in 9-day-experiment (from the introduction of the hot particles to the slaughter). Distribution of 11 isotopes of Sr, Ru, Cs, Eu and Pu have been traced in different organs. A very small amount of radionuclides have been found in the internal organs after the slaughter: in GIT the percentage of nuclides from the amount introduced is the following: for 137Cs: 0.14 (I group) and 0.19 (II group); for 134Cs - 0.16 and 0.22; for 144Ce - 0.14 and 0.05 respectively. The removal goes mainly with faeces and much less with urine and milk. The peak of cesium concentration in milk is observed in the early period after introduction in GIT (44-68 hours). For the whole period the removed quantities are: I group - 0.173% of 134Cs and 0.166% of 137Cs; II group - 0.106% and 0.104% respectively. The percentage of cesium transfered to cows' organism is the following: I group - 1.61% of 137Cs and 1.65% for 134Cs; II group - 1.04% and 1.11%, respectively. Haematological analysis show an increased amount of leucoytes and neutrophiles. An efficient filtering of nuclides in organs and tissues have been observed. A significant difference in distribution of nuclides from hot particles compared to single introduction of radionuclides is found. Small deviations in haematological parameters have been observed and no local effects in GIT have been found. (author)

  7. RESULTS FOR THE SECOND QUARTER 2010 TANK 50 WAC SLURRY SAMPLE: CHEMICAL AND RADIONUCLIDE CONTAMINANT RESULTS

    Reigel, M.; Bibler, N.

    2010-08-04

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC).1 Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for {sup 94}Nb and {sup 144}Ce are above both the established and requested limits from References 4 and 6. (3) The reported detection limits for {sup 247}Cm and {sup 249}Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 6. (4) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (5) A measurable concentration of Norpar 13 is present in the sample. The reported concentration is greater than the requested limit from Table 4 and Attachment 8.2 of the WAC. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50. (7) The detection limit for isopropanol has been lowered from 0.5 mg/L to 0.25 mg/L{sup 7}. This revised limit now satisfies the limit in Table 4 of the WAC.

  8. Lichen (sp. Cladonia) as a deposition indicator for transuranium elements investigated with the Chernobyl fallout

    Paatero, Jussi; Jaakkola, Timo; Kulmala, Seija [Helsinki Univ., Radiochemistry Lab., Helsinki (Finland)

    1998-06-01

    The feasibility of employing carpet-forming lichens (sp. Cladonia) as a measure for the deposition of transuranium elements was investigated with the Chernobyl fallout. In Finland, the deposition of these elements after the accident was very uneven. The highest deposition values for {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 242}Cm and {sup 243,244}Cm were 5.7, 3.0, 1.3, 98 and 0.025 Bq m{sup -2}, respectively. The amount of deposited {sup 239,240}Pu was, however, only some percent of the fallout of the nuclear test explosions of the 1950s and the 1960s. Instead, practically no {sup 242}Cm was released into the environment during the weapons` testing. The correlation between the refractory nuclides {sup 238}Pu, {sup 239,240}Pu, {sup 241}Am, {sup 242}Cm, {sup 95}Zr and {sup 144}Ce in lichen was high (r = 0.709-0.979), but the correlation between the transuranium elements and volatile {sup 137}Cs was much lower (r = 0.227-0.276). The calculated biological half-lives of Pu and Am in lichen were 730 and 320 days, respectively. The {sup 238}Pu/{sup 239,240}Pu activity ratio in the top parts of lichen samples was 0.54 ``+`` 0.02 corresponding to a burn-up value of 12 MWd kg{sup -1}. The {sup 238}Pu/{sup 239,240}Pu activity ratios of 0.43 and 0.69 measured from two isolated hot particles correspond to burn-up values of 10 and 14 MWd kg{sup -1}, respectively. (author).

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

    This paper reviews 19 studies conducted by the Lovelace ITRI on the toxicity of inhaled radionuclides in beagle dogs. These studies provide information to estimate potential health effects in accidentally exposed people. Specific radionuclides (90Sr, 90Y, 91Y, 137Cs, 144Ce, 238Pu, and 239Pu), chemical forms, and particle sizes were selected for study because they are abundant in nuclear operations and deliver a wide range of radiation dose patterns. Depending upon the aerosol, one or more of the following organs or tissues received the significant irradiation: lung, nasal cavity, lung-associated lymph nodes, whole body, liver, or skeleton, with the radiation dose delivered over durations of time ranging from a few days to several years. In eight studies monodisperse particles of either 238PuO2 or 239PuO2 were used to evaluate the influence of particle number and total dose on lung cancer induction. Most studies involved single, brief exposures of young adult dogs, but two studies used immature dogs, two used aged dogs, and two studies involved repeated brief exposures. For each aerosol two types of studies were conducted. One was used to evaluate the time course of retention of radioactivity in various tissues of the body for calculating radiation doses. The second was used to determine health effects in animals exposed to achieve different initial lung burdens and observed for the remainder of their life spans. Initial lung burdens were selected to produce early morbidity and mortality at the highest levels and an excess of late-occurring diseases such as cancer at the lowest levels. The latter dogs have had an excess incidence of cancer, especially of the lung, lung-associated lymph nodes, nasal cavity, skeleton, and liver. Relationships between radiation doses to various tissues and effects have been evaluated for individual studies

  10. Impacts to nuclear utilities of 10CFR61

    The disposal of low-level waste from nuclear utilities is regulated by 10CFR61. The basic requirements are that the radionuclide content be quantified and identified and that the waste itself meet certain chemical and physical criteria. Waste packaging protocols are also delineated. In order to meet these requirements, on-site instrumental measurements and radiochemical analysis are required for each waste stream. Complex calculations, often performed by vendor computer programs, are employed to incorporate assay information into shipping manifests acceptable to low-level waste sites. Aside from the continuing increase in low-level waste site charges, 10CFR61 also added to the cost of utility waste disposal. The methodology most applicable to power plants involves scaling difficult to measure nuclides (i.e. nuclides which do not emit easily measured gamma rays) to those which are both easy to measure and possess similar chemical and physical properties. This methodology has been in use for several years in determining the transuranic content of waste based on the 144Ce concentration. The NRC has accepted this technique and has, in fact, suggested its extension to the problem nuclides listed in 10CFR61. These scaling factors are being based on the existing limited data base, engineering judgement, an preliminary data from on-going work. Important differences exist between Boiling Water Reactors (BWRs and Pressurized Water Reactors (PWRs) which preclude the use of common scaling factors. In fact, important differences between substantially similar plant types may prevent generically categorized scaling factors from being used. Uncertainties in this regard will force every nuclear plant to develop a plant specifi program for compliance with 10CFR61. requirements of this new rule

  11. Fallout radionuclides and natural radioactivity in tissues of deers from different regions in Austria

    The concentration of fallout radionuclides in bone and liver samples of deers from different regions in Austria have been investigated. The results indicate that these concentrations are correlated with the altitude and the mean annual rainfall of the region, where the animals lived. About 20 years after the Test Ban Treaty comes into force, 90-Sr and 137-Cs contaminations still can be shown in such tissue samples. In bone 0,5 - 20 pCi 90-Sr and generally less than 0,2 pCi 137-Cs have been found per g fresh weight. Related to the calcium and potassium content of this tissue, maximal values of 95 pCi 90-Sr/g Ca and 730 pCi 137-Cs/g K have been reached. Additionally small amounts of 144-Ce, 60-Co and 54-Mn have been seen, which obviously resulted from the Chinese weapon tests during the last years. In liver samples 90-Sr is below our detection level (i. e. smaller than 0,2 pCi 90-Sr/sample), 137-Cs in the range of 0,1 - 1,7 pCi/g fresh weight. Related to the potassium content of the liver, a maximal value of 190 pCi 137-Cs/g K is observed. Comparing a period of 10 years 137-Cs contaminations remained nearly the same. Also the amount of natural radioactivities like 40-K, 226-Ra, 228-Ac and 212-Pb have been determined in these samples. The results show that the radiation dose to the animals delivered from incorporated natural radioactivities is about one order of magnitude higher than those which has to be expected from fallout contaminations. (Author)

  12. Mobility of radionuclides in undisturbed and cultivated soils in Ukraine, Belarus and Russia six years after the Chernobyl fallout

    Six years after the accident at the Chernobyl Nuclear Power Plant, the behaviour of radionuclides in soils in rural areas of Ukraine, Belarus and Russia has been studied. Measurements were made to determine the total radioactive contamination, the fuel particle contribution, and the distribution and extractability of the radionuclides 137Cs and 90Sr. Inside the 30 km restriction zone around the plant, particles of highly irradiated fuel accounted for most of the radioactive contamination. The radioactivity in the soil, in decreasing order, was due to 137Cs>90Sr> 144Ce≥ 134Cs> 241Am> 125Sb> 154Eu> 155Eu. Outside the 30 km zone, condensed radionuclides were dominant and here the radionuclide content of the soil was 137Cs> 134Cs> 125Sb> 90Sr. The mobility of 137Cs in the soil increased with increasing distance from the reactor: this was in line with the fact that the 137Cs in condensed form, relative to that in fuel particles, also increased with increasing distance from the reactor. There was greater migration of the γ-emitting radionuclides 125Sb, 137Cs and 144Ce in peaty soils than in soddy podsolic, sandy and loamy soils. In undisturbed soddy podsolic sandy soils, more than 95% of the 137Cs was found in the top 6 cm layer. Not surprisingly, in the cultivated soils, the radionuclides were found more or less homogeneously distributed in the 0-25 cm layer. In the undisturbed soils, the γ-emitters had all migrated down to about the same depth except for the 125Sb which had moved rather deeper. (Author)

  13. Destructive radiochemical analysis of uraniumsilicide fuel for burnup determination

    Gysemans, M.; Bocxstaele, M. van; Bree, P. van; Vandevelde, L.; Koonen, E.; Sannen, L. [SCK-CEN, Boeretang, Mol (Belgium); Guigon, B. [CEA, Centre de Cadarache, Saint Paul lez Durance (France)

    2004-07-01

    During the design phase of the French research reactor Jules Horowitz (RJH) several types of low enriched uranium fuels (LEU), i.e. <20% {sup 235}U enrichment, are studied as possible candidate fuel elements for the reactor core. One of the LEU fuels that is taken into consideration is an uraniumsilicide based fuel with U{sub 3}Si{sub 2} dispersed in an aluminium matrix. The development and evaluation of such a new fuel for a research reactor requires an extensive testing and qualification program, which includes destructive radiochemical analysis to determine the burnup of irradiated fuel with a high accuracy. In radiochemistry burnup is expressed as atom percent burnup and is a measure for the number of fissions that have occurred per initial 100 heavy element atoms (%FIMA). It is determined by measuring the number of heavy element atoms in the fuel and the number of atoms of selected key fission products that are proportional to the number of fissions that occurred during irradiation. From the few fission products that are suitable as fission product monitor, the stable Nd-isotopes {sup 143}Nd, {sup 144}Nd, {sup 145}Nd, {sup 146}Nd, {sup 148Nd}, {sup 150}Nd and the gamma-emitters {sup 137}Cs and {sup 144}Ce are selected for analysis. Samples form two curved U{sub 3}Si{sub 2} plates, with a fuel core density of 5.1 and 6.1 g U/cm{sup 3} (35% {sup 235}U) and being irradiated in the BR2 reactor of SCK x CEN{sup [1]}, were analyzed. (orig.)

  14. Radiation and migration characteristics of the Chernobyl radionuclides causing environmental contamination in various provinces in the European sector of the USSR

    The radionuclide composition of the Chernobyl fallout has been studied over practically the whole European sector of the Union of Soviet Socialist Republics using soil sampling methods, the upper turf layer of the soil being treated as a natural planchet. Regular observation of the migration of radionuclides in the soil-plant system has been in progress since July 1986 at a stationary network of landscape-geochemical testing sites and sampling grounds; two types of natural ecosystem have been looked at - meadowland and forest. The behaviour of individual radionuclides is evaluated using the coefficient of fractionation in relation to 95Zr or 144Ce. The migration characteristics of individual radionuclides were revealed to depend both on soil conditions and on the type of radionuclide composition. The main features of the vertical profile of radionuclide concentrations in soils were clear 2-3 months after the contamination occurred. During subsequent years the migrational profiles changed depending on the individual characteristics of the radionuclides and soil conditions. Information on the radionuclide composition and evolution of the vertical distribution of radionuclides in soils was used to calculate and predict exposure gamma radiation dose from the Chernobyl fallout in various provinces in the European sector of the Soviet Union. When monitoring forest sampling grounds, samples were taken of the soil (litter, humus, mineral layer), the phytomasses of ligneous species (pine needles, leaves, bark, wood), moss and lichens. The main aim of monitoring surveys from 1986 to 1989 was to evaluate the distribution of Chernobyl radionuclides in the compartments of the forest ecosystem. In particular, 60-80% of the total amount of 137Cs was bound with the humus layer of the forest soil. 4 refs, 6 figs, 3 tabs

  15. Feasibility study of passive gamma spectrometry of molten core material from Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy - low-volatile FP and special nuclear material inventory analysis and fundamental characteristics of gamma-rays from fuel debris

    The technologies applied to the analysis of the Three Mile Island accident were examined in a feasibility study of gamma spectrometry of molten core material from the Fukushima Daiichi Nuclear Power Station unit 1, 2, and 3 cores for special nuclear material accountancy. The focus is on low-volatile fission products and heavy metal inventory analysis, and the fundamental characteristics of gamma-rays from fuel debris with respect to passive measurements. The inventory ratios of the low-volatile lanthanides, 154Eu and 144Ce, to special nuclear materials were evaluated by the entire core inventories in units 1, 2, and 3 with an estimated uncertainty of 9%-13% at the 1σ level for homogenized molten fuel material. The uncertainty is expected to be larger locally owing to the use of the irradiation cycle averaging approach. The ratios were also evaluated as a function of burnup for specific fuel debris with an estimated uncertainty of 13%-25% at the 1σ level for units 1 and 2, and most of the fuels in unit 3, although the uncertainty regarding the separated mixed oxide fuel in unit 3 would be significantly higher owing to the burnup dependence approach. Source photon spectra were also examined and cooling-time-dependent data sets were prepared. The fundamental characteristics of high-energy gamma-rays from fuel debris were investigated by a bare-sphere model transport calculation. Mass attenuation coefficients of fuel debris were evaluated to be insensitive to its possible composition in a high-energy region. The leakage photon ratio was evaluated using a variety of parameters, and a significant impact was confirmed for a certain size of fuel debris. Its correlation was summarized with respect to the leakage photopeak ratio of source 154Eu. Finally, a preliminary study using a hypothetical canister model of fuel debris based on the experience at Three Mile Island was presented, and future plans were introduced. (author)

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

    Mokrov, Yuri G

    2004-09-01

    In the period from 1949 to 1956, liquid radioactive waste was routinely and accidentally discharged by the Mayak Production Association, Southern Urals, Russia, into the Techa river. Based on a novel approach, the contamination of the Techa river water, the bottom sediments and the adjacent flood plains was modelled, and internal and external doses were estimated for two villages located downstream of the site of liquid radioactive waste release. Altogether, 11 radionuclides that occurred in the liquid radioactive waste were included in the calculations. The results suggest significantly higher doses than previously assumed, with the major contribution in the year 1951. Radionuclides with half-lives of less than 1 year, such as 89Sr, 131I, 95Zr+95Nb, 103Ru+103mRh, 140Ba+140La, and 144Ce+144Pr, represent the major sources and, in contrast, long-lived radionuclides, such as 90Sr and 137Cs that have so far been assumed to be most important, did not dominate the doses. For adults from the village Metlino, located 7 km downstream of the site of liquid radioactive waste discharge, the committed effective doses due to intake of radionuclides were calculated to be about 2.3 Sv, while the external doses were between about 1.2 Sv and 6.9 Sv. On the other hand, for adults from Muslyumovo, located 75 km downstream, the committed effective doses due to intake of radionuclides were calculated to be about 0.5 Sv, while the external doses were between 0.5 Sv and 2.0 Sv. The values for the skin doses to the Metlino and Muslyumovo populations were about 7.1 Sv and 1.3 Sv, respectively. It is concluded that the current dose estimates for the residents of the Techa river need, therefore, reevaluation. PMID:15378312

  17. Study on separation of 137Cs from 235U fission process waste - utilization of silica gel-supported ferrocyanide complex salt for 137Cs picking

    In connection with the potential domestic demand especially in the fields of industry and nuclear medicine, the separation of 137Cs from 235U fission process waste is to be of interest although its economic value could be a polemic. A preliminary study on the separation of 137Cs from the 235U fission process waste generated in the production of 99Mo in P.T. BATAN Teknologi, Serpong, was performed through experiments on 137Cs picking from sample solution of the radioactive fission waste (RFW). The presented study is aimed to gain experimental data supporting utilization of the matrix of silica gel-supported ferrocyanide complex salt for the separation of 137Cs from RFW. Subsequent step would be the recovery and purification of 137Cs as part of production technology of 137Cs. The RFW sample was batch-treated with the matrix of silica gel-supported ferrocyanide complex salt which was synthesized from silica gel, potassium hexacyanoferrate(II) and copper(II) chloride. The binding of radioisotopes in RFW on the matrix was observed by γ-spectrometry of the RFW solution before and during the treatment. The results showed that approximately 85% of 137Cs could be picked from the RFW sample into the matrix. Less amount of 95Zr and 95Nb was bound into the matrix. 103Ru was slightly bound into the matrix whereas 141/144Ce and 129mTe were not. It was observed that by using 0.2 and 0.4 g of matrix for 10 ml of RFW, the amount of matrix influenced the binding quantity of 95Zr and 95Nb but not that of 137Cs. (author)

  18. Results For The Second Quarter 2010 Tank 50 WAC Slurry Sample: Chemical And Radionuclide Contaminant Results

    This report details the chemical and radionuclide contaminant results for the characterization of the 2010 Second Quarter sampling of Tank 50 for the Saltstone Waste Acceptance Criteria (WAC).1 Information from this characterization will be used by Liquid Waste Operations (LWO) to support the transfer of low-level aqueous waste from Tank 50 to the Salt Feed Tank in the Saltstone Facility in Z-Area, where the waste will be immobilized. This information is also used to update the Tank 50 Waste Characterization System. The following conclusions are drawn from the analytical results provided in this report: (1) The concentrations of the reported chemical and radioactive contaminants were less than their respective WAC targets or limits unless noted in this section. (2) The reported detection limits for 94Nb and 144Ce are above both the established and requested limits from References 4 and 6. (3) The reported detection limits for 247Cm and 249Cf are above the requested limits from Reference 4. However, they are below the limits established in Reference 6. (4) The reported detection limit for Isopar L is greater than the limit from Table 3 of the WAC. (5) A measurable concentration of Norpar 13 is present in the sample. The reported concentration is greater than the requested limit from Table 4 and Attachment 8.2 of the WAC. (6) Isopar L and Norpar 13 have limited solubility in aqueous solutions making it difficult to obtain consistent and reliable sub-samples. The values reported in this memo are the concentrations in the sub-sample as detected by the GC/MS; however, the results may not accurately represent the concentrations of the analytes in Tank 50. (7) The detection limit for isopropanol has been lowered from 0.5 mg/L to 0.25 mg/L7. This revised limit now satisfies the limit in Table 4 of the WAC.

  19. Selection of polymer solid supports for supported liquid membrane applications

    The role of polymer support selection upon the performance and stability of a supported liquid membrane(SLM) has been evaluated in detail. Permeation experiments are carried out batch wise in a simple twin stirred cells. Several solid supports such as polytetrafluroethylene (TE-35, TE-36, TE-37), polypropylene (HF-PP), cellulose nitrate (BA-S-83) of different pore sizes and varying thickness are tested. Dicyclohexano-18-crown-6 (DC18C6) in toluene has been employed as mobile carrier in permeation of plutonium (IV) nitrate across SLM. Selectivity of plutonium transport from fission product contaminants such as 137Cs. 103Ru and 144Ce is found to be lesser with large pore size (0.45 μm) support. Chemical stability of these hydrophobic polymer membranes against organic solvents and nitric acid is evaluated. Polytetrafluroethylene supports like TE-35, TE-36, TE-37 and polypropylene HF-PP membranes have not shown any marked deterioration but cellulose nitrate membrane such as BA-S-83 is attacked by organic solvent. Such deleterious effects have been confirmed by the scanning electron microscopy which revealed that pore structure becomes completely blocked. Radiolytic stability of these polymers is also tested by irradiating them up to 3 Mrads using 60Co irradiator. No serious damage due to radiation is observed as micrographs have shown undisturbed network of polymer structure even after the irradiation. Of the different polymer supports tested, both TE-35 and HF-PP thin-film solid membranes prove to be quite suitable for SLM purposes as their optimum pore size, good physical and chemical stability including radiation stability render them relatively more useful for varied applications in liquid membranes. (author). 5 refs., 3 figs., 3 tabs

  20. Ruthenium release modelling in air under severe accident conditions using the MAAP4 code

    Beuzet, E.; Lamy, J.S. [EDF R and D, 1 avenue du General de Gaulle, F-92140 Clamart (France); Perron, H. [EDF R and D, Avenue des Renardieres, Ecuelles, F-77818 Moret sur Loing (France); Simoni, E. [Institut de Physique Nucleaire, Universite de Paris Sud XI, F-91406 Orsay (France)

    2010-07-01

    In a nuclear power plant (NPP), in some situations of low probability of severe accidents, an air ingress into the vessel occurs. Air is a highly oxidizing atmosphere that can lead to an enhanced core degradation affecting the release of Fission Products (FPs) to the environment (source term). Indeed, Zircaloy-4 cladding oxidation by air yields 85% more heat than by steam. Besides, UO{sub 2} can be oxidised to UO{sub 2+x} and mixed with Zr, which may lead to a decrease of the fuel melting temperature. Finally, air atmosphere can enhance the FPs release, noticeably that of ruthenium. Ruthenium is of particular interest for two main reasons: first, its high radiotoxicity due to its short and long half-life isotopes ({sup 103}Ru and {sup 106}Ru respectively) and second, its ability to form highly volatile compounds such as ruthenium gaseous tetra-oxide (RuO{sub 4}). Considering that the oxygen affinity decreases between cladding, fuel and ruthenium inclusions, it is of great need to understand the phenomena governing fuel oxidation by air and ruthenium release as prerequisites for the source term issues. A review of existing data on ruthenium release, controlled by fuel oxidation, leads us to implement a new model in the EDF version of MAAP4 severe accident code (Modular Accident Analysis Program). This model takes into account the fuel stoichiometric deviation and the oxygen partial pressure evolution inside the fuel to simulate its oxidation by air. Ruthenium is then oxidised. Its oxides are released by volatilisation above the fuel. All the different ruthenium oxides formed and released are taken into consideration in the model, in terms of their particular reaction constants. In this way, partial pressures of ruthenium oxides are given in the atmosphere so that it is possible to know the fraction of ruthenium released in the atmosphere. This new model has been assessed against an analytical test of FPs release in air atmosphere performed at CEA (VERCORS RT8). The

  1. Inorganic, radioisotopic and organic analysis of 241-AP-101 tank waste

    Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids. The characterization of the 241-AP-101 composite samples included: (1) Inductively-coupled plasma spectrometry for Ag, Al, Ba, Bi, Ca, Cd, Cr, Cu, Fe, K, La, Mg, Mn, Na, Nd, Ni, P, Pb, Pd, Ru, Rh, Si, Sr, Ti, U, Zn, and Zr (Note: Although not specified in the test plan, As, B, Be, Co, Li, Mo, Sb, Se, Sn, Tl, V, W, and Y were also measured and reported for information only) (2) Radioisotopic analyses for total alpha and total beta activities, 3H, 14C, 60Co, 79Se, 90Sr, 99Tc as pertechnetate, 106Ru/Rh, 125Sb, 134Cs, 137Cs, 152Eu, 154Eu, 155Eu, 238Pu, 239+240Pu, 241Am, 242Cm, and 243+244Cm; (3) Inductively-coupled plasma mass spectrometry for 237Np, 239Pu, 240Pu, 99Tc, 126Sn, 129I, 231Pa, 233U, 234U, 235U, 236U, 238U, 241AMU, 242AMU, 243AMU, As, B, Be, Ce, Co, Cs, Eu, I, Li, Mo, Pr, Rb, Sb, Se, Ta, Te, Th, Tl, V, and W; (4) total U by kinetic phosphorescence analysis; (5) Ion chromatography for Cl, F, NO2, NO3, PO4, SO4, acetate, formate, oxalate, and citrate; (6) Density, inorganic carbon and organic carbon by two different methods, mercury, free hydroxide, ammonia, and cyanide. The 241-AP-101 composite met all contract limits (molar ratio of analyte to sodium or ratio of becquerels of analyte to moles of sodium) defined in Specification 7 for Envelope A. Except for a few cases, the characterization results met or surpassed the

  2. Extensions to the Beta Secondary Standard BSS 2

    Behrens, R.; Buchholz, G.

    2011-11-01

    Since several years, the irradiation facility for beta radiation, the Beta Secondary Standard BSS 2 developed at PTB, has been in worldwide use for the performance of irradiations with calibrated beta sources. Due to recent developments in eye tumor therapy, in eye lens dosimetry, and in soft- and hardware technology, several extensions have been added to the BSS 2. These extensions are described in this paper: 1. The possibility of using a 106Ru/106Rh beta source was added as this radionuclide is often used in tumor therapy. 2. The (small) contribution due to photon radiation was included in the dose (rate) reported by the BSS 2, as this was missing in the past. 3. The quantity personal dose equivalent at a depth of 3 mm, Hp(3), was implemented due to recent findings on the radio sensitivity of the eye lens regarding cataract induction and the subsequent lowering of the dose limit from 150 mSv down to 20 mSv per year; 4. The correction for ambient conditions (air temperature, pressure, and relative humidity) was improved in order to adequately handle the quantity Hp(3) and in order to extend the range of use beyond 25°C. 5. A checksum test was added to the software to secure the calibration data against (un)intended changes. 6. The connection of the PC and the BSS 2 has been changed to a network interface (TCP/IP) in order to be able to use up-to-date computers not containing a parallel and a serial port. 7. A rod phantom was added in order to make sure the mechanical set-up is of high quality. All these extensions have been implemented in the PTB's BSS 2 model. The routine implementation of extension 1 is still under investigation by the manufacturer. The commercially available BSS 2 will contain extensions 2 to 6 starting approximately in 2012, while extension 7 has already been incorporated since 2011. Extensions 2 to 4 will also be available for old BSS 2 versions via a software update, starting approximately at the beginning of 2012. Extension 6 will be

  3. Ruthenium release at high temperature from irradiated PWR fuels in various oxidising conditions. Main findings from the VERCORS program

    Fission product release and transport in case of PWR severe accident is a major topic in reactor safety assessment due to the potential radiological consequences for surrounding populations and the environment. In this context, the Institute for Radiological Protection and Safety (IRSN) and Electricite de France (EDF) have supported the VERCORS analytical test program which was performed by the ''Commissariat a l'Energie Atomique'' (CEA). It is usually considered as complementary to the PHEBUS FP in-pile integral experimental program. 25 annealing tests were performed between 1983 and 2002 on irradiated PWR fuels under various conditions of temperature and atmospheres (oxidising or reducing conditions).The influence of the nature of the fuel (UO2 versus MOX, burn-up) and the fuel morphology (initially intact or fragmented fuels) have also been investigated. These led to an extended data base allowing on the one hand to study mechanisms which promote fission products release, and on the other hand to enhance models implemented in severe accident codes. Among all the fission products investigated, ruthenium is of specific concern because of its high radiological effects due essentially to the combination of both its short and long half-life isotopes (i.e. 103Ru and 106Ru respectively), but also by its ability to generate volatile gaseous oxides (RuO3, RuO4) in very oxidising conditions, in particular in the case of air ingress accidents. Important uncertainties still remain on the release and transport of this element in such situations, and investigations on this open issue are notably carried out in the SARNET European framework. The present communication gives a general overview of the VERCORS program and presents more deeply the main findings concerning the ruthenium release. Its global behaviour is analysed on the basis of several comparative tests: same UO2 sample (35 and 50 GWd/t) under hydrogen or steam conditions, similar MOX sample (40 GWd/t) under hydrogen

  4. Volatility of ruthenium during vitrification operations on fission products. part 1. nitric solutions distillation concentrates calcination. part 2. fixation on a steel tube. decomposition of the peroxide

    During vitrification of fission product solutions, a high percentage of the ruthenium initially present in these solutions in the form of nitrosyl-ruthenium nitrates is volatilized with the production of the peroxide which itself is decomposed to ruthenium dioxide. The aim of this work has been to study the volatility of the ruthenium during the vitrification processes. During the distillation of the nitric solutions, we have studied in particular the influence on the volatility of the temperature , of the chemical form in which the ruthenium is introduced, of the bubbling of a gas through the solution, of the nitric concentration and of the nitrate concentration. During the calcination, we have observed the influence of the temperature, of the time, of the flow rate and of the nature of the carrier gas, as well as of the action of the ruthenium bi-oxide and the iron oxide on the volatility of the ruthenium. Part 2. This report deals with the study of the thermal decomposition of ruthenium peroxide, RuO4, and its deposition on steel tubing. After a brief bibliographic review of the various properties of this substance, a study is made, in the first part, of its deposition on a steel tube. In order to do this, we pass a gas current containing RuO4 marked with 106Ru through a stainless steel tube subjected to a temperature gradient which decreases in the direction of the gas flow. The temperature at which RuO4 is deposited or is fixed on the tube is determined and the influence of the flow rate on this deposit is studied. In the second part, an attempt has been made to study by a static method the kinetics of the decomposition reaction of ruthenium peroxide to give the dioxide: RuO4 → RuO2 + O2. To do this, we have tried to introduce gaseous RuO4 into a container placed in an electric oven, and to follow the reaction by γ counting. (author)

  5. Inorganic, radioisotopic and organic analysis of 241-AP-101 tank waste

    SK Fiskum; PR Bredt; JA Campbell; LR Greenwood; OT Farmer; GJ Lumetta; GM Mong; RT Ratner; CZ Soderquist; RG Swoboda; MW Urie; JJ Wagner

    2000-06-28

    Battelle received five samples from Hanford waste tank 241-AP-101, taken at five different depths within the tank. No visible solids or organic layer were observed in the individual samples. Individual sample densities were measured, then the five samples were mixed together to provide a single composite. The composite was homogenized and representative sub-samples taken for inorganic, radioisotopic, and organic analysis. All analyses were performed on triplicate sub-samples of the composite material. The sample composite did not contain visible solids or an organic layer. A subsample held at 10 C for seven days formed no visible solids. The characterization of the 241-AP-101 composite samples included: (1) Inductively-coupled plasma spectrometry for Ag, Al, Ba, Bi, Ca, Cd, Cr, Cu, Fe, K, La, Mg, Mn, Na, Nd, Ni, P, Pb, Pd, Ru, Rh, Si, Sr, Ti, U, Zn, and Zr (Note: Although not specified in the test plan, As, B, Be, Co, Li, Mo, Sb, Se, Sn, Tl, V, W, and Y were also measured and reported for information only) (2) Radioisotopic analyses for total alpha and total beta activities, {sup 3}H, {sup 14}C, {sup 60}Co, {sup 79}Se, {sup 90}Sr, {sup 99}Tc as pertechnetate, {sup 106}Ru/Rh, {sup 125}Sb, {sup 134}Cs, {sup 137}Cs, {sup 152}Eu, {sup 154}Eu, {sup 155}Eu, {sup 238}Pu, {sup 239+240}Pu, {sup 241}Am, {sup 242}Cm, and {sup 243+244}Cm; (3) Inductively-coupled plasma mass spectrometry for {sup 237}Np, {sup 239}Pu, {sup 240}Pu, {sup 99}Tc, {sup 126}Sn, {sup 129}I, {sup 231}Pa, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 241}AMU, {sup 242}AMU, {sup 243}AMU, As, B, Be, Ce, Co, Cs, Eu, I, Li, Mo, Pr, Rb, Sb, Se, Ta, Te, Th, Tl, V, and W; (4) total U by kinetic phosphorescence analysis; (5) Ion chromatography for Cl, F, NO{sub 2}, NO{sub 3}, PO{sub 4}, SO{sub 4}, acetate, formate, oxalate, and citrate; (6) Density, inorganic carbon and organic carbon by two different methods, mercury, free hydroxide, ammonia, and cyanide. The 241-AP-101 composite met all

  6. Reference beta radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of beta radiation energy. 1. ed.

    This International Standard specifies the requirements for reference beta radiations produced by radionuclide sources to be used for the calibration of protection level dosemeters and dose ratemeters, and for the determination of their response as a function of beta energy. It gives the characteristics of radionuclides which have been used to produce reference beta radiations, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta energy and the absorbed dose rate at a depth of 7 mg·cm-2 in a semi-infinite tissue-equivalent medium. The energy range involved lies between 66 keV and 3.6 MeV and the absorbed dose rates are in the range from about 10 μGy·h-1 (1 mrad·h-1) to at least 10 Gy·h-1 (103 rad·h-1). This International Standard proposes two series of beta reference radiations from which the radiation necessary for determining the characteristics (calibration and energy response) of an instrument shall be selected. Series 1 reference radiations are produced by radionuclide sources used with beam flattening filters designed to give uniform dose rates over a large area at a specific distance. The proposed sources of 90Sr+90Y, 204TI and 147Pm produce maximum dose rates of approximately 5mGy·h-1 (0.5 rad·h-1). Series 2 reference radiations are produced without the use of beam flattening filters which allows a range of source-to-calibration plane distances to be used. Close to the sources only relatively small areas of uniform dose rate are produced but this Series has the advantage of extending the energy and dose rate ranges beyond those of Series 1. The radionuclides used are those of Series 1 with the addition of the radionuclides 14C and 106Ru+106Rh; these sources produce dose rates of up to 10 Gy·h-1 (103 rad·h-1)

  7. Results of 1999 Spectral Gamma-Ray and Neutron Moisture Monitoring of Boreholes at Specific Retention Facilities in the 200 East Area, Hanford Site

    Twenty-eight wells and boreholes in the 200 East Are% Hanford Site, Washington were monitored in 1999. The monitored facilities were past-practice liquid waste disposal facilities and consisted of six cribs and nineteen ''specific retention'' cribs and trenches. Monitoring consisted of spectral gamma-ray and neutron moisture logging. All data are included in Appendix B. The isotopes 137Cs, 60Co, 235U, 238U, and 154Eu were identified on spectral gamma logs from boreholes monitoring the PUREX specific retention facilities; the isotopes 137Cs, 60Co, 125Sb, and 154Eu were identified on the logs from boreholes at the BC Controlled Area cribs and trenches; and 137Cs, 60Co, and 125Sb were, identified on the logs from boreholes at the BX specific retention trenches. Three boreholes in the BC Controlled Area and one at the BX trenches had previous spectral gamma logs available for comparison with 1999 logs. Two of those logs showed that changes in the subsurface distribution of 137CS and/or 60Co had occurred since 1992. Although the changes are not great, they do point to continued movement of contaminants in the vadose zone. The logs obtained in 1999 create a larger baseline for comparison with future logs. Numerous historical gross gamma logs exist from most of the boreholes logged. Qualitative comparison of those logs with the 1999 logs show many substantial changes, most of which reflect the decay of deeper short-lived isotopes, such as 106Ru and 125Sb, and the much slower decay of shallower and longer-lived isotopes such as 137Cs. The radionuclides 137Cs and 60Co have moved in two boreholes since 1992. Given the amount of movement and the half-lives of the isotopes, it is expected that they will decay to insignificant amounts before reaching groundwater. However, gamma ray logging cannot detect many of the contaminants of interest such as 99Tc, NO3, or 129I, all of which can be highly mobile in the vadose zone and, for the radionuclides, have long half-lives

  8. Department of Radiation Shielding and Dosimetry: Overview

    Full text: The research activities of the Department in 1999, similarly to the previous year were focused on the following problems: -Dosimetry for medical purposes, - Microdosimetry at the nanometre level, -Numerical modelling of interaction of radiation with matter. The following activities should be emphasized: - DOSIMETRY: The method for standardisation of a scintillation detector with NE102A organic scintillator in the terms of absorbed dose has been accomplished. The method is based on the use of small size ionisation chamber ''pipe type'' with sensitive area of 0.8 cm2. The response of the chamber has been traced in SSDL laboratory against secondary standards. This scintillation detector has been used for standardisation of the of the absorbed dose depth dependence in water for the 106Ru ophthalmic applicators. A new type of an ionisation chamber, called Ring Ionisation Chamber for standardising of absorbed dose from beta-radioactive wires, used for endovascular brachytherapy has been designed. This activity is supported by Grant KBN Nr 4P05C01417. -MICRODOSIMETRY: After a prolonged time of research the success has ben achieved in developing the method for measuring the ion cluster spectra at the nanometre level. The ion clusters spectra created along nanometre size track of alpha particles with energy of 4.6 MeV were measured with the Jet Counter set up. The ion cluster spectra of nanometre size with dimension ranging from 0.15 to 13 nm (at unit density scale) have been measured. The deconvolution method, converting the measured spectra to the true ones has been developed. The results are the first of this kind ever obtained. This activity was supported by IV CEC Framework as well as by Polish Commission for Scientific Research. - NUMERICAL MODELLING: MCNP-A General Monte Carlo N-Particle Transport Code was used for modelling electron penetration in water eye ball phantom. Depth dose distributions in eye phantom have been calculated for different shapes of

  9. Non destructive determination of fuel burn up of the RA reactor at Vinca by gamma radiation spectra analysis

    The problem of non destructive determination of the burn-up of used up fuel of the powerful experimental reactor RA at Vinca, by the analysis of gamma radiation spectra using a gamma-spectrometer with a semiconductor Ge(Li) detector has been studied. The first part of this analytical problem is concerned with calculation of fuel burn up. In the preparation of its solution material and energetic balance of the fuel composition and conditions of fuel irradiation. The obtained solution uses numerical methods. In this solution fuel burn up is determined: 1) on the basis of the data on the composition of 106Ru, 134Cs and 137Cs, than 2) from a series of the data on the fuel and reactor and 3) on the basis of those, numerous, literature data which participate in defining of the balance of fuel burn up process. The second part of this problem refers to determination of the composition of the above gamma radioactive fission products from the obtained instrumental spectrum. Under strictly defined conditions of the measurement of gamma radiation from the fuel elements, when a determined type of the gamma ray collimator is used, the photo peak area of the corresponding line in the instrumental spectrum is defined as a function of the fission products activity, energy and yield of its gamma rays, the thickness of fuel and added absorbers as well as the dimensions of the collimator used. On this basis, the activity quotient of two fission products is a function of: 1) two areas of two photo peaks of their two lines and 2) some of the above cited values. Unknown magnitudes of the remaining values of the same relation are determined from the photo peak areas of the lines of the complex spectrum of one fission product by solving a system of equations. Accuracy of the solutions of these two separate parts of the observed analytical problems was confirmed experimentally. The results obtained are characterized by high repeatability. Total errors are generally greater, primarily due to

  10. Environmental radiation measurement in CTBT verification system

    This paper introduces the technical requirements of the Comprehensive Nuclear-Test-Ban Treaty (CTBT) Radionuclide Stations, the CTBT-related activities carried out by the Japan Atomic Energy Research Institute (JAERI), and the ripple effects of such acquired radionuclide data on general researches. The International Monitoring System (IMS), which is one of the CTBT verification regime. Consists of 80 radionuclide air monitoring stations (of those, 40 stations monitor noble gas as well) and 16 certified laboratories that support these stations throughout the world. For radionuclide air monitoring under the CTBT, the stations collect particulates in the atmosphere on a filter and determine by gamma-ray spectrometry the presence or absence of any radionuclides (e.g. 140Ba, 131I, 99Mo, 132Te, 103Ru, 141Ce, 147Nd, 95Zr, etc.) that offer clear evidence of possible nuclear explosion. Minimum technical requirements are stringently set for the radionuclide air monitoring stations: 500 m3/h air flow rate, 24-hour acquisition time, 10 to 30 Bq/m3 of detection sensitivity for 140Ba, and less than 7 consecutive days, or total of 15 days, a year of shutdown at the stations. For noble gas monitoring, on the other hand, the stations separate Xe from gas elements in the atmosphere and, after purifying and concentrating it, measure 4 nuclides, 131mXe, 133Xe, 133mXe, and 135Xe, by gamma-ray spectrometry or beta-gamma coincidence method. Minimum technical requirements are also set for the noble gas measurement: 0.4 m3/h air flow rate, a full capacity of 10 m3, and 1 Bq/m3 of detection sensitivity for 133Xe, etc. On the request of the Ministry of Education, Culture, Sports and Technology, the JAERI is currently undertaking the establishment of the CTBT radionuclide monitoring stations at both Takasaki (both particle and noble gas) and Okinawa (particle), the certified laboratory at JAERI Tokai, and the National Data Center (NDC 2) at JAERI Tokai, which handles radionuclide data, as

  11. Environmental gamma radiation and fallout measurements in Finland, 1986-87

    Results from a survey of environmental gamma radiation levels in Finland after the Chernobyl accident 1986 are presented. The measurements were made in 1986-87 by means of sensitive Geiger-counters and a gamma-spectrometer placed in cars. The results show the level of external radiation caused by the cesium fallout on the first of October 1987. The fallout pattern of 137Cs as well as of 95Zr and 103Ru are also presented. In the center of Southern Finland there are wide areas with exposure levels exceeding 0.03 μSv h-1, areas exceeding 0.10 μSv h-1 being very rare. The surface area weighted mean dose rate for the 461 municipalities in Finland was 0.027 μSv h-1 (range 0-0.19 μSv h-1). The population weighted mean dose rate was 0.037 μSv h-1. The corresponding estimated surface activity of 137Cs was 10.7 kBq m-2. The passage of the Chernobyl plume over Finland in 1986 led to various fallout patterns for different radionuclides. The deposition of the non-volatile nuclides, 95Zr and 141Ce, is closely related to the passage of the hot particle dust formed at the initial explosion in the reactor at 01.23 LT on 26 April. This cloud passed over Finland between the morning and the night of 27 April. The deposition of volatile fission products such as 131I, 132Te, 134Cs and 137Cs in Finland was caused by releases from the burning reactor after the initial explosion. The radioactive plume spread over Southern and Central Finland between Sunday 27 April and Tuesday 29 April. On 30 April and finally on 1 May a could northerly airstream spread into the whole of Finland purifying the atmosphere. The volatile nuclides were mainly deposited by intermittent rain on 28-30 April. The deposition pattern of 103Ru is a combination of the fallou patterns due to the initial explosion and the reactor burn, as well as the wet deposition occurring on 10-12 May caused by the releases from the burning reactor in early May

  12. Fission Yields of Some Isotopes in the Fission of Th232 by Reactor Neutrons

    The fission yields of the longer-lived isotopes produced in the fission of Th232 are not very well known; existing data show rather large discrepancies and/or uncertainties. Since we feel that at least some of these discrepancies arise from difficulties in measuring the absolute activities of the fission products, we measured the fission yield of 10 selected isotopes whose decay schemes are well understood. The thorium foils were irradiated in a position at the edge of the core of the SAPHIR swimming pool reactor. Following irradiation, the thorium was dissolved after addition of appropriate carriers. The fission products of interest were determined by conventional radiochemical methods that had to be modified slightly to ensure good decontamination from the abundantly formed Pa233 . The chemical yields were determined by gravimetric methods. Counting was done preferentially on a γ-spectrometer that had been calibrated at 11 different energies by standards either obtained from the IAEA or prepared by 4πβ-counting. In the case of Sr90, Ru106 and Ce144 a β-proportional counter was used that had been calibrated for these isotopes. In addition to the sought elements, Mo99 was isolated from each foil to serve as an internal monitor for the number of fissions taking place. The experiment thus gave the ratio of the yield of the sought element to the yield of Mo99. This ratio ''R'' was obtained for Sr90, Ru103, Ru106, Ag111, Pd112, I131, Cs137, Ba140, Ba141, Ce141 and Ce144, Results indicate the existence of a third peak in the yield mass curve in the region of symmetric fission. Yields of fission products relative to the Mo99 yields are given, and the absolute yields calculated by assuming y Mo99 = 2.78%. This number was derived from the work of Iyer et al., and was obtained by normalizing the area under the yield mass curve to 200%. (author)

  13. Deposition of Chernobyl-derived transuranium nuclides and short- lived radon-222 progeny in Finland

    In this study the atmospheric deposition of radionuclides was investigated from two different viewpoints. The Chernobyl nuclear power plant accident in April 1986 caused a widely spread plume of radionuclides, including transuranium elements. The regional deposition of these elements in Finland was assessed based on lichen and peat samples. Unlike the deposition of transuranium elements from the weapons tests in the 1950's and 1960's, the deposition from the Chernobyl accident was very unevenly distributed in Finland. Also, the Chernobyl-derived deposition of 299,240Pu even in the most contaminated regions in Finland was still only some 10 per cent of the global fallout from weapons tests. On the other hand, the measured activity concentrations of 241Pu in the upper parts of lichen samples are comparable to those found in samples comparable during the heaviest weapons-test fallout in the early 1960's. The observed average 241Pu/239,240Pu activity ratio in the upper parts of lichen, 95, can be expected to lead at its maximum in the year 2059 to 241Am/239,240Pu activity ratio of 2.8 in the Chernobyl-derived deposition, exclusive of the 241Am present in the original deposition in 1986. The deposition pattern of transuranium elements observed in this work resembles that of refractory gamma-emitting nuclides such as 95Zr and 141Ce. The sampling area of this investigation does not cover the northern part of Finland. However, the fallout pattern of 95Zr would suggest that the deposition of transuranium nuclides north of the 65th latitude was very low. Biological half-lives of 730 d and 320 d for Pu and Am, respectively, were obtained in lichen in this study. The second part of this work is concerned with the factors affecting the wet deposition efficiency of the natural short-lived radon-222 progeny. This was studied with two methods: using recordings of external gamma radiation in central Finland, and using an automatic precipitation gamma analyser in northern Finland

  14. Organization of radio-ecological monitoring of the areas of the Russian Federation contaminated due to the accident at the Chernobyl NPP (on example of the Bryansk region)

    Linnik, Vitaly; Korobova, Elena; Vakulovsky, Sergey

    2013-04-01

    A severe accident at the Chernobyl NPP on April 26th, 1986 has led to radioactive contamination of many regions of the former USSR, now belonging to the Ukraine, the Republic of Belarus and the Russian Federation. Both natural and arable ecosystems have been subjected to fallout of radioactive isotopes. However both the distribution of radionuclides that define radioecological situation has depended not only on the initial contamination density but also on the landscape geochemical features of the areas controlling biogenic and abiogenic factors of radionuclide migration. To study and monitor peculiarities of migration of the most radioecologically significant radionuclides of Cs-137 and Sr-90 in different natural landscapes the Russian Scientific and Practical Experimental Center of the former State Chernobyl Committee has organized in 1992 a network of experimental plots in the most contaminated western part of the Bryansk region. It included 19 plots 100 m x 100 m in size which characterized 8 meadow and 11 forested catenas in the basin of the Iput' river. Cs-137 contamination level of the plots varied in 1992 from 740 kBq/m2 to 1850 kBq/m2. Although the study site has been located in the remote zone and the contamination was of condensation type the sampling performed at 11 plots registered some refractory radionuclides (144Ce, 154Eu, 238,239,240Pu and 90Sr) that proved the presence of fuel particles in fallout as far as 200 km from the damaged reactors. The sampling and monitoring scheme was organized to determine: the isotopic composition and contamination density of the plots; 2) estimation of radionuclide vertical and lateral migration; 3) evaluation of radionuclide inventories in different soil horizons; 4) calculation of radionuclide transfer in soil-plant system. Radiation measurements included field gamma-spectrometry using collimated gamma spectrometer "Corad" developed in the Kurchatov Institute and laboratory spectrometry the soil and plant samples

  15. Expeditious method to determine uranium in the process control samples of chemical plant separating (233)U from thoria irradiated in power reactors.

    Kedari, C S; Kharwandikar, B K; Banerjee, K

    2016-11-01

    Analysis of U in the samples containing a significant proportion of (232)U and high concentration of Th is of great concern. Transmutation of Th in the nuclear power reactor produces a notable quantity of (232)U (half life 68.9 years) along with fissile isotope (233)U. The decay series of (232)U is initiated with (228)Th (half life 1.9 year) and it is followed by several short lived α emitting progenies, (224)Ra, (220)Rn, (216)Po, (212)Bi and (212)Po. Even at the smallest contamination of (228)Th in the sample, a very high pulse rate of α emission is obtained, which is to be counted for the radiometric determination of [U]. A commercially available anionic type of extractant Alamine®336 is used to obtain the selective extraction of U from other alpha active elements and fission products present in the sample. Experimental conditions of liquid-liquid extraction (LLE) are optimized for obtaining maximum decontamination and recovery of U in the organic phase. The effect of some interfering ionic impurities in the sample on the process of separation is investigated. Depending on the level of the concentration of U in the samples, spectrophotometry or radiometry methods are adopted for its determination after separation by LLE. Under optimized experimental conditions, i.e. 5.5M HCl in the aqueous phase and 0.27M Alamin®336 in the organic phase, the recovery of U is about 100%, the decontamination factor with respect to Th is >2000 and the extraction of fission products like (90)Sr, (144)Ce and (134,137)Cs is negligible. The detection limit for [U] using α radiometry is 10mg/L, even in presence of >100g/L of Th in the sample. Accuracy and precision for the determination of U is also assessed. Reproducibility of results is within 5%. This method shows very good agreement with the results obtained by mass spectrometry. PMID:27591623

  16. Fission Product Yields from Fission Spectrum n+239Pu for ENDF/B-VII.1

    We describe a new cumulated fission product yield (FPY) evaluation for fission spectrum neutrons on plutonium that updates the ENDF/B-VI evaluation by England and Rider, for the forthcoming ENDF/B-VII.1 database release. We focus on FPs that are needed for high accuracy burnup assessments; that is, for inferring the number of fissions in a neutron environment. Los Alamos conducted an experiment in the 1970s in the Bigten fast critical assembly to determine fission product yields as part of the Interlaboratory Reaction Rate (ILRR) collaboration, and this has defined the Laboratory's fission standard to this day. Our evaluation includes use of the LANL-ILRR measurements (not previously available to evaluators) as well as other Laboratory FPY measurements published in the literature, especially the high-accuracy mass spectrometry data from Maeck and others. Because the measurement database for some of the FPs is small - especially for 99Mo - we use a meta-analysis that incorporates insights from other accurately-measured benchmark FP data, using R-value ratio measurements. The meta-analysis supports the FP measurements from the LANL-ILRR experiment. Differences between our new evaluations and ENDF/B-VI are small for some FPs (less than 1-2%-relative for 95Zr, 140Ba, 144Ce), but are larger for 99Mo (4%-relative) and 147Nd (5%-relative, at 1.5 MeV) respectively. We present evidence for an incident neutron energy dependence to the 147Nd fission product yield that accounts for observed differences in the FPY at a few-hundred keV average energy in fast reactors versus measurements made at higher average neutron energies in Los Alamos' fast critical assemblies. Accounting for such FPY neutron energy dependencies is important if one wants to reach a goal of determining the number of fissions to accuracies of 1-2%. An evaluation of the energy-dependence of fission product yields is given for all A values based on systematical trends in the measured data, with a focus on the

  17. Leaching study of nuclear melt glass: Part I

    Ground samples of three nuclear melt glasses from underground nuclear explosions at the Nevada Test Site (NTS) were leached at 250C with natural ground water from NTS. Using our dynamic single-pass flow-through leaching system we monitored the release of radionuclides from the glasses during 420 days of leaching. We continually flowed the ground water over the melt glass at flow rates of 185 ml/day for half of the samples and 34 ml/day for the rest. Leachate solutions were collected continuously, and composite samples, collected on days 1, 2, 3, 6, 11, 32, 38, 70, 120, 230 and 420, were analyzed using low-background Ge(Li) gamma spectrometers. For most of the radionuclides the leach rate decreased smoothly throughout the experiment. Except for 95Zr, 144Ce, and 155Eu, there was no difference between the fast (185 ml/day) and slow (34 ml/day) flow-rate leach rates. The measurable leach rates ranged from a high of 1 x 10-2 g-glass/m2 day for 22Na (slow flow-rate, day 1 in glass No. 2) to a low of 1 x 6-6 g-glass/m2 day for 54Mn (slow flow-rate, day 420 in glass No. 2). Most of the leach-rate values were about 5 x 10-4 g-glass/m2 day initially, decreasing to 5 x 10-6 g-glass/m2 day after 420 days of leaching. The leach rates had not leveled off by the end of the experiment and were, in general, continuing to decrease. From the activities in the leachate solutions, we determined the percent of the pre-leach activity leached from the melt glasses during the experiment. Only 124Sb, in one fast flow-rate channel of glass No. 2, exceeded 3% of the initial activity leached. The majority of the samples released less than 1% of the pre-leach activity for a given radionuclide. The percent activity released from the samples leached at the fast and slow flow rates were nearly equal

  18. Nuclear fuel cycle and marine environment. Behavior of the Rhone river effluents in the mediterranean sea and of wastes dumped in the northeast atlantic; Cycle du combustible nucleaire et milieu marin. Devenir des effluents rhodaniens en mediterranee et des dechets immerges en atlantique nord-est

    Charmasson, S

    1998-07-01

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of {sup 106}Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment {sup 106}Ru yields to caesium isotopes ({sup 134}Cs and {sup 137}Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y{sup -1} have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the {sup 137}Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different {sup 137}Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive

  19. Volatility of ruthenium during vitrification operations on fission products. part 1. nitric solutions distillation concentrates calcination. part 2. fixation on a steel tube. decomposition of the peroxide; Volatilite du ruthenium au cours des operations de vitrification des produits de fission. 1. partie distillation des solutions nitriques calcination des concentrats 2. partie fixation sur un tube d'acier decomposition du peroxyde

    Ortins de Bettencourt, A.; Jouan, A. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1969-07-01

    During vitrification of fission product solutions, a high percentage of the ruthenium initially present in these solutions in the form of nitrosyl-ruthenium nitrates is volatilized with the production of the peroxide which itself is decomposed to ruthenium dioxide. The aim of this work has been to study the volatility of the ruthenium during the vitrification processes. During the distillation of the nitric solutions, we have studied in particular the influence on the volatility of the temperature , of the chemical form in which the ruthenium is introduced, of the bubbling of a gas through the solution, of the nitric concentration and of the nitrate concentration. During the calcination, we have observed the influence of the temperature, of the time, of the flow rate and of the nature of the carrier gas, as well as of the action of the ruthenium bi-oxide and the iron oxide on the volatility of the ruthenium. Part 2. This report deals with the study of the thermal decomposition of ruthenium peroxide, RuO{sub 4}, and its deposition on steel tubing. After a brief bibliographic review of the various properties of this substance, a study is made, in the first part, of its deposition on a steel tube. In order to do this, we pass a gas current containing RuO{sub 4} marked with {sup 106}Ru through a stainless steel tube subjected to a temperature gradient which decreases in the direction of the gas flow. The temperature at which RuO{sub 4} is deposited or is fixed on the tube is determined and the influence of the flow rate on this deposit is studied. In the second part, an attempt has been made to study by a static method the kinetics of the decomposition reaction of ruthenium peroxide to give the dioxide: RuO{sub 4} {yields} RuO{sub 2} + O{sub 2}. To do this, we have tried to introduce gaseous RuO{sub 4} into a container placed in an electric oven, and to follow the reaction by {gamma} counting. (author) [French] Au cours de la vitrification des solutions de produits de

  20. Nuclear fuel cycle and marine environment. Behavior of the Rhone river effluents in the mediterranean sea and of wastes dumped in the northeast atlantic

    Man-made radionuclides released into the marine environment by the installations from the nuclear fuel cycle are used as tracers of various bio-geochemical processes. Several installations belonging to the whole nuclear fuel cycle, except the uranium mining, are set up on the Rhone River Banks. The sea disposal of low and intermediate level radioactive waste has never been authorized in the Mediterranean sea but several sites have been used in the North-East especially in abyssal waters. Radionuclides released by the Rhone river installations are used in order to study the dynamics of the Rhone inputs into the Mediterranean Sea. In the river, freshwater samples reflect quite accurately the discharge composition with a predominance of 106Ru, a radionuclide mostly released by the spent nuclear fuel reprocessing plant in Marcoule. Conversely, at the Rhone mouth, in the sediment compartment 106Ru yields to caesium isotopes (134Cs and 137Cs) in importance. As these two isotopes demonstrate very different half-lives (30,2 and 2,1 years respectively), the temporal evolution of their ratio acts as a chronometer enabled to date sediment accumulation near the river mouth. Mean accumulation rates greater than 35 cm y-1 have been determined in the pro-deltaic zone near the Roustan buoys over the period 1983-1991. Accumulation rates decrease rapidly with distance from the mouth and therefore most of the 137Cs inventory in this part of the Gulf of Lions is limited to the pro-deltaic area. A first study about the part the different 137Cs sources in the Mediterranean Sea play in this inventory has been carried out. Direct (atmospheric) and indirect (fluviatile) inputs due to fallout from both past nuclear tests and the Chernobyl accident could contribute to this inventory at the highest to 40 % while the industrial releases could contribute at the lowest to 60 %. The last site used for the dumping of low and intermediate level radioactive waste in the North-East Atlantic has been