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Sample records for radioactive cesium isotopes

  1. Radioactive and stable cesium isotope distributions and dynamics in Japanese cedar forests.

    Science.gov (United States)

    Yoschenko, Vasyl; Takase, Tsugiko; Hinton, Thomas G; Nanba, Kenji; Onda, Yuichi; Konoplev, Alexei; Goto, Azusa; Yokoyama, Aya; Keitoku, Koji

    2018-06-01

    Dynamics of the Fukushima-derived radiocesium and distribution of the natural stable isotope 133 Cs in Japanese cedar (Cryptomeria japonica D. Don) forest ecosystems were studied during 2014-2016. For the experimental site in Yamakiya, Fukushima Prefecture, we present the redistribution of radiocesium among ecosystem compartments during the entire observation period, while the results obtained at another two experimental site were used to demonstrate similarity of the main trends in the Japanese forest ecosystems. Our observations at the Yamakiya site revealed significant redistribution of radiocesium between the ecosystem compartments during 2014-2016. During this same period radionuclide inventories in the aboveground tree biomass were relatively stable, however, radiocesium in forest litter decreased from 20 ± 11% of the total deposition in 2014 to 4.6 ± 2.7% in 2016. Radiocesium in the soil profile accumulated in the 5-cm topsoil layers. In 2016, more than 80% of the total radionuclide deposition in the ecosystem resided in the 5-cm topsoil layer. The radiocesium distribution between the aboveground biomass compartments at Yamakiya during 2014-2016 was gradually approaching a quasi-equilibrium distribution with stable cesium. Strong correlations of radioactive and stable cesium isotope concentrations in all compartments of the ecosystem have not been reached yet. However, in some compartments the correlation is already strong. An increase of radiocesium concentrations in young foliage in 2016, compared to 2015, and an increase in 2015-2016 of the 137 Cs/ 133 Cs concentration ratio in the biomass compartments with strong correlations indicate an increase in root uptake of radiocesium from the soil profile. Mass balance of the radionuclide inventories, and accounting for radiocesium fluxes in litterfall, throughfall and stemflow, enabled a rough estimate of the annual radiocesium root uptake flux as 2 ± 1% of the total inventory in the ecosystem

  2. Radioactive cesium isotope ratios as a tool for determining dispersal and re-dispersal mechanisms downwind from the Nevada Nuclear Security Site.

    Science.gov (United States)

    Snyder, Darin C; Delmore, James E; Tranter, Troy; Mann, Nick R; Abbott, Michael L; Olson, John E

    2012-08-01

    Fractionation of the two longer-lived radioactive cesium isotopes ((135)Cs and (137)Cs) produced by above ground nuclear tests have been measured and used to clarify the dispersal mechanisms of cesium deposited in the area between the Nevada Nuclear Security Site and Lake Mead in the southwestern United States. Fractionation of these isotopes is due to the 135-decay chain requiring several days to completely decay to (135)Cs, and the 137-decay chain less than one hour decay to (137)Cs. Since the Cs precursors are gases, iodine and xenon, the (135)Cs plume was deposited farther downwind than the (137)Cs plume. Sediment core samples were obtained from the Las Vegas arm of Lake Mead, sub-sampled and analyzed for (135)Cs/(137)Cs ratios by thermal ionization mass spectrometry. The layers proved to have nearly identical highly fractionated isotope ratios. This information is consistent with a model where the cesium was initially deposited onto the land area draining into Lake Mead and the composite from all of the above ground shots subsequently washed onto Lake Mead by high intensity rain and wind storms producing a layering of Cs activity, where each layer is a portion of the composite. Copyright © 2012 Elsevier Ltd. All rights reserved.

  3. The use of composite ferrocyanide materials for treatment of high salinity liquid radioactive wastes rich in cesium isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Toropov, Andrey S. [National Nuclear Centre of the Republic of Kazakhstan, Kurchatov (Kazakhstan); Shakarim Semey State Univ. (Kazakhstan); Satayeva, Aliya R. [Shakarim Semey State Univ. (Kazakhstan); Mikhalovsky, Sergey [Nazarbayev Univ. (Kazakhstan); Brighton Univ. (United Kingdom); Cundy, Andrew B. [Brighton Univ. (United Kingdom)

    2014-07-01

    The use of composite materials based on metal ferrocyanides combined with natural mineral sorbents for treatment of high salinity Cs-containing liquid radioactive waste (LRW) was investigated. The study indicated that among the investigated composites, the best sorption characteristics for Cs were shown by materials based on copper ferrocyanide. Several factors affecting the removal of cesium from LRW, namely total salt content, pH and organic matter content, were also investigated. High concentrations of complexing organic matter significantly reduced the sorption capacity of ferrocyanide sorbents.

  4. Extraction of radioactive cesium from tea leaves

    International Nuclear Information System (INIS)

    Yano, Yukiko; Kubo, M. Kenya; Higaki, Shogo; Hirota, Masahiro; Nomura, Kiyoshi

    2011-01-01

    Radioactive contamination of foodstuffs attributed to the Fukushima Daiichi nuclear disaster has become a social problem. This study investigated the extraction of radioactive cesium from the contaminated leaves to the tea. The green tea was brewed twice reusing the same leaves to study the difference in extraction of cesium between the first and second brew. Moreover, the extraction of cesium was studied in correlation to brewing time. The concentration of radioactive cesium was determined with gamma spectrometry, and the concentration of caffeine was determined with absorption spectrometry. About 40% of cesium was extracted from leaves in the first brew, and about 80% was extracted in the second brew. The extraction of cesium increased over time, and it reached about 80% after 10 minutes brew. The ratio of radioactive cesium to caffeine decreased linearly over time. This study revealed that the extraction of cesium was higher for the second brew, and a rapid increase in extraction was seen as the tea was brewed for 6 minutes and more. Therefore, the first brew of green tea, which was brewed within 5 minutes, contained the least extraction of radioactive cesium from the contaminated leaves. (author)

  5. Application of Cesium isotopes in daily life

    International Nuclear Information System (INIS)

    Jordao, B.O.; Quaresma, D.S.; Carvalho, R.J.; Peixoto, J.G.P.

    2014-01-01

    In the world of science, the desire of the scientific community to discover new chemical elements is crucial for the development of new technologies in various fields of knowledge. And the main chemical element addressed by this article is Cesium, but specifically 133 Cesium isotope and radioisotope 137 Cesium, exemplifying their physical and chemical characteristics, and their applications. This article will also show how these isotopes have provided researchers a breakthrough in the field of radiological medicine and in time and frequency metrology. (author)

  6. Radioactive cesium in Finnish mushrooms

    International Nuclear Information System (INIS)

    Kostiainen, E.; Ylipieti, J.

    2010-02-01

    Surveillance of radioactive cesium in Finnish mushrooms was started in 1986 at STUK. Results of the surveillance programs carried out in Lapland and other parts of Finland are given in this report. More than 2000 samples of edible mushrooms have been analysed during 1986-2008. The 137 Cs detected in the mushrooms mainly originates from the 137 Cs deposition due to the accident at the Chernobyl nuclear power plant in 1986. The 137 Cs concentrations of mushrooms in the end of 1970s and in the beginning of 1980s varied from some ten to two hundred becquerels per kilogram originating from the nuclear weapon test period. The uneven division of the Chernobyl fallout is seen in the areal variation of 137 Cs concentrations of mushrooms, the 137 Cs concentrations being about tenfold in the areas with the highest deposition compared to those where the deposition was lowest. After the Chernobyl accident the maximum values in the 137 Cs concentrations were reached during 1987-88 among most species of mushrooms. The 137 Cs concentrations have decreased slowly, being in 2008 about 40 per cent of the maximum values. The 137 Cs concentrations may be tenfold in the mushroom species with high uptake of cesium (Rozites caperatus, Hygrophorus camarophyllus, Lactarius trivialis) compared to the species with low uptake (Albatrellus ovinus, Leccinum sp.) picked in the same area. The 137 Cs contents in certain species of commercial mushrooms in Finland still exceed the maximum permitted level, 600 Bq/kg, recommended to be respected when placing wild game, wild berries, wild mushrooms and lake fish on the market (Commission recommendation 2003/274/Euratom). Therefore, the 137 Cs concentrations of mushrooms should be measured before placing them on the market in the areas of the highest 137 Cs deposition, except for Albatrellus ovinus, Boletus sp. and Cantharellus cibarius. The 137 Cs concentrations of common commercial mushroom species, Cantharellus tubaeformis and Craterellus

  7. Method of processing radioactive cesium liquid wastes

    International Nuclear Information System (INIS)

    Nishijima, Hiroaki; Asaoka, Sachio; Kondo, Tadami; Suzuki, Isao.

    1985-01-01

    Purpose: To convert and settle cesium, mainly, Cs-137 in liquid wastes in the form of pollucites, that is, cesium-containing ores. Constitution: Water, silica, alumina and alkali metal source are mixed with radioactive liquid wastes containing cesium as the main metal element ingredient, to which an onium compound is further added and they are brought into reaction till pollucite ores (Cs 16 (Al 16 Si 32 O 96 )) are formed. Since most portion of cesium is thus settled in the form of pollucites, storage safety can be attained. Further, the addition of the onium compound can moderate the condition and shorten the time till the pollucite ores are formed. The onium compound usable herein includes tetramethyl ammonium. (Kamimura, M.)

  8. Radioactive cesium content in selected food products. Pt. 2. Radioactive cesium in daily food rations of selected population groups

    International Nuclear Information System (INIS)

    Skibniewska, K.; Smoczynski, S.S.; Wisniewska, I.

    1993-01-01

    The content of radioactive cesium isotopes emitting beta radiation was studied in daily food rations analysed in diets of working-class and non-working-class families from food products from the regions of Olsztyn, Poznan, Lublin, Warsaw and Wroclaw in 1987 and 1988. In 1987 the highest level of radioactive cesium was found in the food rations in Olsztyn, and lowest in the rations in Poznan (3.32 and 0.65 Bq/kg respectively). In 1988 higher radiocesium content was found in rations composed according to the data on the diet consumed daily in non-working-class families. In that case the highest content was in the daily food rations composed in Warsaw - 2.35 Bq/kg and lowest in Poznan - 1.19 Bq/kg in the daily food rations of working-class families about one half of that value was found. The calculated means values of both analysed rations were: 1.35 for Olsztyn, 0.89 for Poznan, and 1.86 Bq/kg for Warsaw. The calculated mean value of the contamination with radioactive cesium was in 1988 0.93 Bq/kg for the rations in working-class families (in 1987 it was 1.80 Bq/kg). (author). 15 refs, 1 tab

  9. Radiation safety for incineration of radioactive waste contaminated by cesium

    International Nuclear Information System (INIS)

    Veryuzhs'kij, Yu.V.; Gryin'ko, O.M.; Tokarevs'kij, V.V.

    2016-01-01

    Problems in the treatment of radioactive waste contaminated by cesium nuclides are considered in the paper. Chornobyl experience in the management of contaminated soil and contaminated forests is analyzed in relation to the accident at Fukushima-1. The minimization of release of cesium aerosols into atmosphere is very important. Radiation influence of inhaling atmosphere aerosols polluted by cesium has damage effect for humans. The research focuses on the treatment of forests contaminated by big volumes of cesium. One of the most important technologies is a pyro-gasification incineration with chemical reactions of cesium paying attention to gas purification problems. Requirements for process, physical and chemical properties of treatment of radioactive waste based on the dry pyro-gasification incineration facilities are considered in the paper together with the discussion of details related to incineration facilities. General similarities and discrepancies in the environmental pollution caused by the accidents at Chornobyl NPP and Fukushima-1 NPP in Japan are analyzed

  10. Radioactive and Stable Cesium Distributions in Fukushima Forests

    Science.gov (United States)

    Ioshchenko, V.; Kivva, S.; Konoplev, A.; Nanba, K.; Onda, Y.; Takase, T.; Zheleznyak, M.

    2015-12-01

    Fukushima Dai-ichi NPP accident has resulted in release into the environment of large amounts of 134Cs and 137Cs and in radioactive contamination of terrestrial and aquatic ecosystems. In Fukushima prefecture up to 2/3 of the most contaminated territory is covered with forests, and understanding of its further fate in the forest ecosystems is essential for elaboration of the long-term forestry strategy. At the early stage, radiocesium was intercepted by the trees' canopies. Numerous studies reported redistribution of the initial fallout in Fukushima forests in the followed period due to litterfall and leaching of radiocesium from the foliage with precipitations. By now these processes have transported the major part of deposited radiocesium to litter and soil compartments. Future levels of radiocesium activities in the aboveground biomass will depend on relative efficiencies of the radiocesium root uptake and its return to the soil surface with litterfall and precipitations. Radiocesium soil-to-plant transfer factors for typical tree species, soil types and landscape conditions of Fukushima prefecture have not been studied well; moreover, they may change in time with approaching to the equilibrium between radioactive and stable cesium isotopes in the ecosystem. The present paper reports the results of several ongoing projects carried out by Institute of Environmental Radioactivity of Fukushima University at the experimental sites in Fukushima prefecture. For typical Japanese cedar (Cryptomeria japonica) forest, we determined distributions of radiocesium in the ecosystem and in the aboveground biomass compartments by the end of 2014; available results for 2015 are presented, too, as well as the results of test application of D-shuttle dosimeters for characterization of seasonal variations of radiocesium activity in wood. Based on the radiocesium activities in biomass we derived the upper estimates of its incorporation and root uptake fluxes, 0.7% and 3% of the total

  11. Decontamination of radioactive isotopes

    International Nuclear Information System (INIS)

    Despotovic, R.; Music, S.; Subotic, B.; Wolf, R.H.H.

    1979-01-01

    Removal of radioactive isotopes under controlled conditions is determined by a number of physical and chemical properties considered radiocontaminating and by the characteristics of the contaminated object. Determination of quantitative and qualitative factors for equilibrium in a contamination-decontamination system provides the basis for rational and successful decontamination. The decontamination of various ''solid/liquid'' systems is interesting from the scientific and technological point of view. These systems are of great importance in radiation protection (decontamination of various surfaces, liquids, drinking water, fixation or collection of radiocontaminants). Different types of decontamination systems are discussed. The dependence of rate and efficiency of the preparation conditions and on the ageing of the scavenger is described. The influence of coagulating electrolyte on radioactive isotope fixation efficiency was also determined. The fixation of fission radionuclide on oxide scavengers has been studied. The connection between fundamental investigations and practical decontamination of the ''solid/liquid'' systems is discussed. (author)

  12. Micro-PIXE evaluation of radioactive cesium transfer in contaminated soil samples

    International Nuclear Information System (INIS)

    Fujishiro, F.; Ishii, K.; Matsuyama, S.; Arai, H.; Ishizaki, A.; Osada, N.; Sugai, H.; Kusano, K.; Nozawa, Y.; Yamauchi, S.; Karahashi, M.; Oshikawa, S.; Kikuchi, K.; Koshio, S.; Watanabe, K.; Suzuki, Y.

    2014-01-01

    Highlights: • There are radioactively contaminated soils having a radioactive cesium transfer of 0.01. • Micro-PIXE analysis has revealed an existence of phosphorus in a contaminated soil. • Radioactive cesium captured by phosphorus compound would be due to radioactive transfer. -- Abstract: Micro-PIXE analysis has been performed on two soil samples with high cesium activity concentrations. These soil samples were contaminated by fallout from the accident at Fukushima Daiichi Nuclear Power Plant. One exhibits a radioactive cesium transfer of ∼0.01, and the other shows a radioactive cesium transfer of less than 0.001, even though both samples have high cesium activity concentrations exceeding 10,000 Bq/kg. X-ray spectra and elemental images of the soil samples revealed the presence of chlorine, which can react with cesium to produce an inorganic soluble compound, and phosphorus-containing cesium-capturable organic compounds

  13. Rechargeable radioactive isotope generator

    International Nuclear Information System (INIS)

    Thornton, A.K.; Cerone, F.E.

    1978-01-01

    The description is given of a rechargeable radioactive isotope generator having the following features: a box containing a transport shield, a shielded generator including elements for the absorption and holding of the parent isotope, an eluant tank, a first pipe causing this tank to communicate with the transport shield, a second pipe causing this transport shield to communicate with the shielded generator and a third pipe placing the shielded generator in communication with the outside of the unit. It also includes a shelf across the external front part of the unit a part of which is shielded by external components, a shielded elution flask in which the eluate is poured and a filter set at a point between the flask and the third pipe [fr

  14. Carbon, cesium and iodine isotopes in Japanese cedar leaves from Iwaki, Fukushima

    DEFF Research Database (Denmark)

    Xu, Sheng; Cook, Gordon T.; Cresswell, Alan J.

    2016-01-01

    Japanese cedar leaves from Iwaki, Fukushima were analyzed for carbon, cesium and iodine isotopic compositions before and after the 2011 nuclear accident. The Δ14C values reflect ambient atmospheric 14C concentrations during the year the leaves were sampled/defoliated, and also previous year......(s). The elevated 129I and 134,137Cs concentrations are attributed to direct exposure to the radioactive fallout for the pre-fallout-expended leaves and to internal translocation from older parts of the tree for post-fallout-expended leaves. 134Cs/137Cs and 129I/137Cs activity ratios suggest insignificant isotopic...

  15. Adsorption of Radioactive Cesium to Illite-Sericite Mixed Clays

    Science.gov (United States)

    Hwang, J. H.; Choung, S.; Park, C. S.; Jeon, S.; Han, J. H.; Han, W. S.

    2016-12-01

    Once radioactive cesium is released into aquatic environments through nuclear accidents such as Chernobyl and Fukushima, it is harmful to human and ecological system for a long time (t1/2 = 30.2 years) because of its chemical toxicity and γ-radiation. Sorption mechanism is mainly applied to remove the cesium from aquatic environments. Illite is one of effective sorbent, considering economical cost for remediation. Although natural illite is typically produced as a mixture with sericite formed by phyllic alteration in hydrothermal ore deposits, the effects of illite-sericite mixed clays on cesium sorption was rarely studied. This study evaluated the sorption properties of cesium to natural illite collected at Yeongdong in Korea as the world-largest illite producing areas (termed "Yeongdong illite"). The illite samples were analyzed by XRF, XRD, FT-IR and SEM-EDX to determine mineralogy, chemical composition, and morphological characteristics, and used for batch sorption experiments. Most of "Yeongdong illite" samples predominantly consist of sericite, quartz, albite, plagioclase feldspar and with minor illite. Cesium sorption distribution coefficients (Kd,Cs) of various "Yeongdong illite" samples ranged from 500 to 4000 L/kg at low aqueous concentration (Cw 10-7 M). Considering Kd,Cs values were 400 and 6000 using reference sericite and illite materials, respectively, in this study, these results suggested that high contents of sericite significantly affect the decrease of sorption capabilities for radiocesium by natural illite (i.e., illite-sericite mixed clay).

  16. Micro-PIXE evaluation of radioactive cesium transfer in contaminated soil samples

    Science.gov (United States)

    Fujishiro, F.; Ishii, K.; Matsuyama, S.; Arai, H.; Ishizaki, A.; Osada, N.; Sugai, H.; Kusano, K.; Nozawa, Y.; Yamauchi, S.; Karahashi, M.; Oshikawa, S.; Kikuchi, K.; Koshio, S.; Watanabe, K.; Suzuki, Y.

    2014-01-01

    Micro-PIXE analysis has been performed on two soil samples with high cesium activity concentrations. These soil samples were contaminated by fallout from the accident at Fukushima Daiichi Nuclear Power Plant. One exhibits a radioactive cesium transfer of ˜0.01, and the other shows a radioactive cesium transfer of less than 0.001, even though both samples have high cesium activity concentrations exceeding 10,000 Bq/kg. X-ray spectra and elemental images of the soil samples revealed the presence of chlorine, which can react with cesium to produce an inorganic soluble compound, and phosphorus-containing cesium-capturable organic compounds.

  17. A preliminary assessment on the use of biochar as a soil additive for reducing soil-to-plant uptake of cesium isotopes in radioactively contaminated environments

    International Nuclear Information System (INIS)

    Hamilton, T.F.; Martinelli, R.E.; Kehl, S.R.; Peters, S.K.G.; Tamblin, M.W.; Schmitt, C.L.; Hawk, Daniel

    2016-01-01

    A series of K d tracer batch experiments were conducted to assess the absorptive-desorption properties of Biochar as a potential agent to selectively sequester labile soil Cs or otherwise help reduce the uptake of Cs isotopes into plants. A parallel experiment was conducted for strontium. Fine-grained fractionated Woodlands tree Biochar was found to have a relatively high affinity for Cs ions (K d > 100) relative to coral soil (K d < 10) collected from the Marshall Islands. The Biochar material also contains an abundance of K (and Mg). These findings support a hypothesis that the addition of Biochar as a soil amendment may provide a simple yet effective method for reducing soil-to-plant transfer of Cs isotopes in contaminated environments. (author)

  18. Sources of Radioactive Isotopes for Dirty Bombs

    Science.gov (United States)

    Lubenau, Joel

    2004-05-01

    From the security perspective, radioisotopes and radioactive sources are not created equal. Of the many radioisotopes used in industrial applications, medical treatments, and scientific research, only eight, when present in relatively large amounts in radioactive sources, pose high security risks primarily because of their prevalence and physical properties. These isotopes are americium-241, californium-252, cesium-137, cobalt-60, iridium-192, radium-226, plutonium-238, and strontium-90. Except for the naturally occurring radium-226, nuclear reactors produce the other seven in bulk commercial quantities. Half of these isotopes emit alpha radiation and would, thus, primarily pose internal threats to health; the others are mainly high-energy gamma emitters and would present both external and internal health hazards. Therefore, the response to a "dirty bomb" event depends on what type of radioisotope is chosen and how it is employed. While only a handful of major corporations produce the reactor-generated radioisotopes, they market these materials to thousands of smaller companies and users throughout the world. Improving the security of the high-risk radioactive sources will require, among other efforts, cooperation among source suppliers and regulatory agencies.

  19. Radioactive isotopes on the Moon

    International Nuclear Information System (INIS)

    Davis, R. Jr.

    1975-01-01

    A limited review of experiments and studies of radioactivity and isotope ratios in lunar materials is given. Observations made on the first few millimeters of the surface where the effects of solar flare particles are important, some measurements on individual rocks, and some studies of radioactivities produced deep in the lunar soil by galactic cosmic rays, are among the experiments discussed

  20. Sintered bentonite ceramics for the immobilization of cesium- and strontium-bearing radioactive waste

    Science.gov (United States)

    Ortega, Luis Humberto

    The Advanced Fuel Cycle Initiative (AFCI) is a Department of Energy (DOE) program, that has been investigating technologies to improve fuel cycle sustainability and proliferation resistance. One of the program's goals is to reduce the amount of radioactive waste requiring repository disposal. Cesium and strontium are two primary heat sources during the first 300 years of spent nuclear fuel's decay, specifically isotopes Cs-137 and Sr-90. Removal of these isotopes from spent nuclear fuel will reduce the activity of the bulk spent fuel, reducing the heat given off by the waste. Once the cesium and strontium are separated from the bulk of the spent nuclear fuel, the isotopes must be immobilized. This study is focused on a method to immobilize a cesium- and strontium-bearing radioactive liquid waste stream. While there are various schemes to remove these isotopes from spent fuel, this study has focused on a nitric acid based liquid waste. The waste liquid was mixed with the bentonite, dried then sintered. To be effective sintering temperatures from 1100 to 1200°C were required, and waste concentrations must be at least 25 wt%. The product is a leach resistant ceramic solid with the waste elements embedded within alumino-silicates and a silicon rich phase. The cesium is primarily incorporated into pollucite and the strontium into a monoclinic feldspar. The simulated waste was prepared from nitrate salts of stable ions. These ions were limited to cesium, strontium, barium and rubidium. Barium and rubidium will be co-extracted during separation due to similar chemical properties to cesium and strontium. The waste liquid was added to the bentonite clay incrementally with drying steps between each addition. The dry powder was pressed and then sintered at various temperatures. The maximum loading tested is 32 wt. percent waste, which refers to 13.9 wt. percent cesium, 12.2 wt. percent barium, 4.1 wt. percent strontium, and 2.0 wt. percent rubidium. Lower loadings of waste

  1. Actual situation of concentration and inventory of radioactive cesium in Matsukawaura Lagoon sediment, Fukushima Prefecture

    International Nuclear Information System (INIS)

    Arita, Koichi; Yabe, Tohru; Hayashi, Seiji

    2014-01-01

    In order to qualitatively evaluate the current status of inventory of radioactive cesium in Matsukawaura Lagoon, profiles of radioactive cesium concentration in sediment cores and sediment characteristics were measured at 36 points. It was shown that sediment characteristics were different even at high concentration of radioactive cesium to the same extent. As a result, the inventory of radioactive cesium were also different. Even at high concentration of radioactive cesium, inventory in southwestern high mud content rate was less than the western. The total inventory of down to 20 cm of sediment throughout Matsukawaura Lagoon was estimated to be about 220 GBq, that more than 80% distributed to 15 cm shallower than has been revealed. (author)

  2. Decorporation of mixture of strontium and cesium isotopes with domestic mineral waters

    International Nuclear Information System (INIS)

    Slavov, S.; Filev, G.; Kiradzhiev, G.

    1990-01-01

    The possibilities of Bulgarian mineral waters to decorporate mixtures of strontium and cesium radioisotopes, simultaneous entering the body, were studied. A modified effect in respect to radioactive strontium was found. Modification of the effect of mixing two diferent types of mineral waters was not proven. No effect was found of potassium-containing mineral water on radioactive cesium kinetics. 1 tab., 7 refs

  3. Removal of radioactive cesium from soil by ammonium citrate solution and ionic liquid

    International Nuclear Information System (INIS)

    Ishiwata, Shunji; Kitakouji, Manabu; Taga, Atsushi; Ogata, Fumihiko; Ouchi, Hidekazu; Yamanishi, Hirokuni; Inagaki, Masayo

    2015-01-01

    Radioactive cesium has strongly bound soil as time proceeded, which could not be cleaved in mild condition. We have found that serial treatment of ammonium citrate solution and ionic liquid removed radioactive cesium from soil effectively. The sequence of the treatment is crucial, since inverse serial treatment or mixture of two kinds of solution did not show such an effect, which suggested that ammonium citrate unlocked trapped cesium in soil and ionic liquid solved it. We also found that repeating serial treatment and prolonged treatment time additively removed cesium from soil. (author)

  4. Carbon, cesium and iodine isotopes in Japanese cedar leaves from Iwaki, Fukushima.

    Science.gov (United States)

    Xu, Sheng; Cook, Gordon T; Cresswell, Alan J; Dunbar, Elaine; Freeman, Stewart P H T; Hou, Xiaolin; Kinch, Helen; Naysmith, Philip; Sanderson, David W C; Zhang, Luyuan

    2016-01-01

    Japanese cedar leaves from Iwaki, Fukushima were analyzed for carbon, cesium and iodine isotopic compositions before and after the 2011 nuclear accident. The Δ 14 C values reflect ambient atmospheric 14 C concentrations during the year the leaves were sampled/defoliated, and also previous year(s). The elevated 129 I and 134,137 Cs concentrations are attributed to direct exposure to the radioactive fallout for the pre-fallout-expended leaves and to internal translocation from older parts of the tree for post-fallout-expended leaves. 134 Cs/ 137 Cs and 129 I/ 137 Cs activity ratios suggest insignificant isotopic and elemental fractionation during translocation. However, fractionation between radioiodine and radiocesium is significant during transportation from the source.

  5. Carbon, cesium and iodine isotopes in Japanese cedar leaves from Iwaki, Fukushima

    International Nuclear Information System (INIS)

    Sheng Xu; Cresswell, A.J.; Cook, G.T.; Dunbar, Elaine; Freeman, S.P.H.T.; Kinch, Helen; Naysmith, Philip; Sanderson, D.W.C.; Xiaolin Hou; Luyuan Zhang; Xi'an AMS Center, SKLLQG, CAS, Xi'an

    2016-01-01

    Japanese cedar leaves from Iwaki, Fukushima were analyzed for carbon, cesium and iodine isotopic compositions before and after the 2011 nuclear accident. The Δ 14 C values reflect ambient atmospheric 14 C concentrations during the year the leaves were sampled/defoliated, and also previous year(s). The elevated 129 I and 134,137 Cs concentrations are attributed to direct exposure to the radioactive fallout for the pre-fallout-expended leaves and to internal translocation from older parts of the tree for post-fallout-expended leaves. 134 Cs/ 137 Cs and 129 I/ 137 Cs activity ratios suggest insignificant isotopic and elemental fractionation during translocation. However, fractionation between radioiodine and radiocesium is significant during transportation from the source. (author)

  6. Decreasing radioactive cesium in lodged buckwheat grain after harvest

    Directory of Open Access Journals (Sweden)

    Katashi Kubo

    2016-01-01

    Full Text Available This study assessed soil contamination with high radioactive cesium (R–Cs concentration in buckwheat grains by lodging, and assessed the possibility of R–Cs reduction in grain through post-harvest preparation. Analysis of buckwheat grain produced in farmers’ fields and reports from farmers indicated that grain from fields that had lodging showed higher R–Cs than grain from fields with no lodging. A field experiment demonstrated that R–Cs in grain after threshing and winnowing (TW was about six times higher in lodged plants than in nonlodged plants. In lodged plants, R–Cs in grain was decreased to about one-fourth by polishing, and was decreased to about one-seventh by ultrasonic cleaning, compared with R–Cs in grain after TW. These results demonstrate that R–Cs of buckwheat grain of lodged plants can be decreased by removing soil from the grain surface by polishing and winnowing.

  7. Shielding container for radioactive isotopes

    International Nuclear Information System (INIS)

    Sumi, Tetsuo; Tosa, Masayoshi; Hatogai, Tatsuaki.

    1975-01-01

    Object: To effect opening and closing bidirectional radiation used particularly for a gamma densimeter or the like by one operation. Structure: This device comprises a rotatable shielding body for receiving radioactive isotope in the central portion thereof and having at least two radiation openings through which radiation is taken out of the isotope, and a shielding container having openings corresponding to the first mentioned radiation openings, respectively. The radioactive isotope is secured to a rotational shaft of the shielding body, and the shielding body is rotated to register the openings of the shielding container with the openings of the shielding body or to shield the openings, thereby effecting radiation and cut off of gamma ray in the bidirection by one operation. (Kamimura, M.)

  8. The determination of cesium and rubidium in highly radioactive waste liquid

    International Nuclear Information System (INIS)

    Wei Songsheng

    1991-01-01

    Cesium and rubidium in high-level waste liquid were determined by atomic absorption spectrometry with the instrument modified for analyzing radioactive samples. The results show that the method is effective and safe. The error of the method is less than +- 3%, and it has been used in the production of cesium

  9. Mobility of radioactive cesium in soil originated from the Fukushima Daiichi nuclear disaster. Application of extraction experiments

    International Nuclear Information System (INIS)

    Yoshikazu Kikawada; Takao Oi; Katsumi Hirose; Masaaki Hirose; Atsushi Tsukamoto; Ko Nakamachi; Teruyuki Honda; Hiroaki Takahashi

    2015-01-01

    Extraction experiments on soil radioactively contaminated by the Fukushima Daiichi Nuclear Power Plant accident were conducted by using a variety of extractants to acquire knowledge on the mobility of radioactive cesium in soil. The experimental results revealed that cesium is tightly bound with soil particles and that radioactive cesium newly deposited on soil due to the accident had apparently a higher mobility than stable cesium commonly existing in soil. The results suggested that radioactive cesium deposited on soil hardly migrates via aqueous processes, although chemical and mineralogical conditions of soil affect their mobility. (author)

  10. Pollution by radioactive iodine and radioactive cesium in fruit fields

    International Nuclear Information System (INIS)

    Ohtsuki, Tsutomu; Kikunaga, Hidetoshi; Izumi, Yuichi

    2011-01-01

    A lot of radioactive materials were spread out by the accident of the Fukushima Daiichi nuclear power station caused by the tsunami accompanying earthquake in the area of Tohoku district-Pacific Ocean, in 2011/3/11. In early stage, short half-life nuclides, such as "1"3"2Te, "1"3"1I, "1"3"6Cs, as well as "1"3"4Cs, "1"3"7Cs were observed in fields. Now "1"3"4Cs and "1"3"7Cs which are comparatively long half-life became dominant observing nuclides. The nuclear power plant accident brought serious damages in many directions, especially, the influence of the field pollution by these nuclides is great in the agriculture, and the quick actions and the measures are needed. The influence of "1"3"4Cs and "1"3"7Cs to the fruit tree were investigated in cooperation with Fukushima agricultural center, Institute of Fruit Tree Science. We report several facts of the transfer and translocation mechanism of "1"3"4Cs and "1"3"7Cs in fruit trees. (author)

  11. Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-10-01

    The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department`s mission as stated in that document. ``The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.``

  12. Hanford Isotope Project strategic business analysis Cesium-137 (Cs-137)

    International Nuclear Information System (INIS)

    1995-10-01

    The purpose of this business analysis is to address the beneficial reuse of Cesium 137 (Cs-137) in order to utilize a valuable national asset and possibly save millions of tax dollars. Food irradiation is the front runner application along with other uses. This business analysis supports the objectives of the Department of Energy National Isotope Strategy distributed in August 1994 which describes the DOE plans for the production and distribution of isotope products and services. As part of the Department's mission as stated in that document. ''The Department of Energy will also continue to produce and distribute other radioisotopes and enriched stable isotopes for medical diagnostics and therapeutics, industrial, agricultural, and other useful applications on a businesslike basis. This is consistent with the goals and objectives of the National Performance Review. The Department will endeavor to look at opportunities for private sector to co-fund or invest in new ventures. Also, the Department will seek to divest from ventures that can more profitably or reliably be operated by the private sector.''

  13. Desorption of radioactive cesium by seawater from the suspended particles in river water.

    Science.gov (United States)

    Onodera, Masaki; Kirishima, Akira; Nagao, Seiya; Takamiya, Kouichi; Ohtsuki, Tsutomu; Akiyama, Daisuke; Sato, Nobuaki

    2017-10-01

    In 2011, the accident at the Fukushima-Daiichi nuclear power plant dispersed radioactive cesium throughout the environment, contaminating the land, rivers, and sea. Suspended particles containing clay minerals are the transportation medium for radioactive cesium from rivers to the ocean because cesium is strongly adsorbed between the layers of clay minerals, forming inner sphere complexes. In this study, the adsorption and desorption behaviors of radioactive cesium from suspended clay particles in river water have been investigated. The radioactive cesium adsorption and desorption experiments were performed with two kinds of suspended particulate using a batch method with 137 Cs tracers. In the cesium adsorption treatment performed before the desorption experiments, simulated river water having a total cesium concentration ([ 133+137 Cs + ] total ) of 1.3 nM (10 -9  mol/L) was used. The desorption experiments were mainly conducted at a solid-to-liquid ratio of 0.17 g/L. The desorption agents were natural seawater collected at 10 km north of the Fukushima-Daiichi nuclear power plant, artificial seawater, solutions of NaCl, KCl, NH 4 Cl, and 133 CsCl, and ultrapure water. The desorption behavior, which depends on the preloaded cesium concentration in the suspended particles, was also investigated. Based on the cesium desorption experiments using suspended particles, which contained about 1000 ng/g loaded cesium, the order of cesium desorption ratios for each desorption agent was determined as 1 M NaCl (80%) > 470 mM NaCl (65%) > 1 M KCl (30%) ≈ seawater (natural seawater and Daigo artificial seawater) > 1 M NH 4 Cl (20%) > 1 M 133 CsCl (15%) ≫ ultrapure water (2%). Moreover, an interesting result was obtained: The desorption ratio in the 470 mM NaCl solution was much higher than that in seawater, even though the Na + concentrations were identical. These results indicate that the cesium desorption mechanism is not a simple ion exchange reaction

  14. Advance in the study of removal of cesium from radioactive wastewater by inorganic ion exchangers

    International Nuclear Information System (INIS)

    Wang Songping; Wang Xiaowei; Du Zhihui

    2014-01-01

    The excellent performance in the removal of cesium from radioactive wastewater by inorganic ion exchangers has received extensive attention due to their characteristic physico-chemical features. The paper summarized research progress of removal of cesium by different inorganic ion exchangers such as silicoaluminate, salts of hetero polyacid, hexacyanoferrate, insoluble salts of acid with multivalent metals, insoluble hydrous oxides of multivalent metals and silicotitanate and reviewed several removal systems of cesium by inorganic ion exchangers which might offer China some reference in treatment and disposal of radioactive wastewater. (authors)

  15. Using copper hexacyanoferrate (II) impregnated zeolite for cesium removal from radioactive liquid waste

    International Nuclear Information System (INIS)

    Fumio, K.; Kenji, M.

    1982-01-01

    Experiments were performed to obtain fundamental data on cesium ion removal characteristics of metal hexacyanoferrate (II) impregnated zeolite in radioactive liquid waste containing a large amount of sodium sulfate. Copper hexacyanoferrate (II) impregnated zeolite (CuFZ) was prepared and showed a high selectivity for cesium ion. The material was suitable for use in an ion exchange column. This exchanger could selectively and efficiently remove the cesium even if there is 15 wt% Na 2 SO 4 in the solution. Cesium removal ability and stability of CuFZ were excellent over a wide pH range between 1.5 and 10. The cesium ion exchange ability was not influenced by the presence of the alkali metal ions, calcium and magnesium, and carbonate ions even at concentrations 25 times greater than the cesium ion. However, since ammonium ion behaves similarly to cesium ion and interrupts latter ion adsorption, the presence of ammonium ion is not desirable. The CuFZ offers the possibility of separating and removing cesium from liquid wastes produced in facilities handling radioactive materials

  16. MODELING AN ION EXCHANGE PROCESS FOR CESIUM REMOVAL FROM ALKALINE RADIOACTIVE WASTE SOLUTIONS

    International Nuclear Information System (INIS)

    Smith, F.; Hamm, Luther; Aleman, Sebastian; Michael, Johnston

    2008-01-01

    The performance of spherical Resorcinol-Formaldehyde ion-exchange resin for the removal of cesium from alkaline radioactive waste solutions has been investigated through computer modeling. Cesium adsorption isotherms were obtained by fitting experimental data using a thermodynamic framework. Results show that ion-exchange is an efficient method for cesium removal from highly alkaline radioactive waste solutions. On average, two 1300 liter columns operating in series are able to treat 690,000 liters of waste with an initial cesium concentration of 0.09 mM in 11 days achieving a decontamination factor of over 50,000. The study also tested the sensitivity of ion-exchange column performance to variations in flow rate, temperature and column dimensions. Modeling results can be used to optimize design of the ion exchange system

  17. Local mat-forming cyanobacteria effectively facilitate decontamination of radioactive cesium in rice fields

    International Nuclear Information System (INIS)

    Yamamoto, Atsushi; Yoshida, Shigeru; Okumura, Hiroshi; Inagaki, Masayo; Yamanishi, Hirokuni; Ito, Tetsuo; Furukawa, Michio

    2015-01-01

    The most effective and widespread method to decontaminate radioactive cesium from the Fukushima Daiichi Nuclear Power Plant Disaster was peeling topsoil. But the method had problems, such as large amounts of discarded soil and large-scale work. In nature, cyanobacteria formed biomats on the ground surface and facilitated peeling topsoil when the biomats dried. The cyanobacteria-facilitating peeling decontamination method utilized these cyanobacterial properties. Cyanobacteria are located all over Japan and 'local' cyanobacteria could be used for decontamination without introducing new species. Utilizing cyanobacteria could decrease the amount of discarded soil to about 30% and downsize the execution-scale to individual locations. Cyanobacterial biomats were easily cultivated, especially in rice fields, by maintaining wet conditions and exposure to 100 - 83% solar radiation. Shading by a thin net was helpful in maintaining an environment suitable for cyanobacteria. Nowadays, to prevent uptake of radioactive cesium into rice, K + is usually added to fertilizer in rice fields. The K + fertilization in rice fields might also enhance cyanobacterial capture of radioactive cesium, because high concentrations of K + enhanced cyanobacterial uptake of Cs + . Cyanobacteria could also mitigate the risk of radioactive cesium moving away from a decontaminating rice field. Therefore, the cyanobacteria-facilitating peeling decontamination method was proposed as an easy and safe 'D.I.Y.' method for both farmers and the environment. Besides, plowing rice fields with water before peeling improved the efficiency of this method, because plowing increased the radioactive cesium concentration in the topsoil. (author)

  18. Modeling approach to various time and spatial scale environmental issues in Fukushima. Related to radioactive cesium migration in aquatic systems

    International Nuclear Information System (INIS)

    Kurikami, Hiroshi; Kitamura, Akihiro; Yamada, Susumu; Machida, Masahiko

    2015-01-01

    Several numerical models have been prepared to deal with various time- and spatial-scale issues related to radioactive cesium migration in environment in Fukushima area. The SACT (Soil and Cesium Transport) model developed by the Japan Atomic Energy Agency (JAEA) predicts middle- to long-term evolution of radioactive cesium distribution due to soil erosion, subsequent sediment transport and deposition, and radioactive cesium migration based on the Universal Soil Loss Equation (USLE). The TODAM (Time-dependent One-dimensional Degradation and Migration) model, iRIC/Nays2D and the FLESCOT (Flow, Energy, Salinity, Sediment, Contaminant Transport) model are one-, two- and three-dimensional river/reservoir/coastal models, respectively. Based on conservation equations of sediment and radioactive cesium, they treat advection and diffusion of suspended sediment and cesium, deposition of sediment to bed, re-suspension from bed and adsorption/desorption of radioactive cesium. These models are suitable for small and short time scale issues such as high discharges of sediment and radioactive cesium from rivers due to heavy rainfall events. This paper describes fragments of the JAEA’s approaches of modeling to deal with the issues corresponding to radioactive cesium migration in environment with some case studies. (author)

  19. Accumulation of radioactive cesium released from Fukushima Daiichi Nuclear Power Plant in terrestrial cyanobacteria Nostoc commune.

    Science.gov (United States)

    Sasaki, Hideaki; Shirato, Susumu; Tahara, Tomoya; Sato, Kenji; Takenaka, Hiroyuki

    2013-01-01

    The Fukushima Daiichi Nuclear Power Plant accident released large amounts of radioactive substances into the environment and contaminated the soil of Tohoku and Kanto districts in Japan. Removal of radioactive material from the environment is an urgent problem, and soil purification using plants is being considered. In this study, we investigated the ability of 12 seed plant species and a cyanobacterium to accumulate radioactive material. The plants did not accumulate radioactive material at high levels, but high accumulation was observed in the terrestrial cyanobacterium Nostoc commune. In Nihonmatsu City, Fukushima Prefecture, N. commune accumulated 415,000 Bq/kg dry weight (134)Cs and 607,000 Bq kg(-1) dry weight (137)Cs. The concentration of cesium in N. commune tended to be high in areas where soil radioactivity was high. A cultivation experiment confirmed that N. commune absorbed radioactive cesium from polluted soil. These data demonstrated that radiological absorption using N. commune might be suitable for decontaminating polluted soil.

  20. Measurement of cesium emissions during the vitrification of simulated high level radioactive waste

    International Nuclear Information System (INIS)

    Zamecnik, J.R.; Miller, D.H.; Carter, J.T.

    1992-01-01

    In the Defense Waste Processing Facility at the Savannah River Site, it is desired to eliminate a startup test that would involve adding small amounts of radioactive cesium-137 to simulated high-level waste. In order to eliminate this test, a reliable method for measuring non-radioactive cesium in the offgas system from the glass melter is required. From a pilot scale melter system, offgas particulate samples were taken on filter paper media and analyzed by Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). The ICPMS method proved to be sufficiently sensitive to measure cesium quantities as low as 0.135 μg, with the sensitivity being limited by the background cesium present in the filter paper. Typical particulate loadings ranged from 800 μg of cesium. This sensitivity allowed determination of cesium decontamination factors for four of the five major components of the offgas system. The decontamination factors measured experimentally compared favorably with the process design basis values

  1. Decontamination of radioactive cesium in soil using nano-size metallic calcium dispersing

    International Nuclear Information System (INIS)

    Mitoma, Yoshiharu; Fukuoka, Takezo; Matsue, Hideaki; Kobayashi, Hidemasa; Shiraishi, Hiroaki; Kajitani, Mikio

    2013-01-01

    In Japan, the major concern on radioactive cesium ( 134 Cs and 137 Cs) deposition and soil contamination due to the emission form the Fukushima Dai-ichi nuclear power plant showed up after a massive quake on March 11, 2011. Soil contamination with radioactive cesium has a long-term radiological impact due to its long half-life (30 years for 137 Cs) and its high biological hazard. Therefore, much attention has been paid to decontaminate Cs-contaminated soil with washing and/or extraction by adopting solvents. However, such wet methods have some disadvantages, i.e. forming of secondary effluents and additional cost for their treatment. We have recently shown that the nano-size metallic calcium/calcium oxide/iron dispersing mixture (Fe-nCa) is most effective for heavy metals immobilization and volume reduction method under dry condition. Thus, we applied this method to treat real radioactive cesium contaminated soils in dry condition. Simple stirring of the contaminated soil with Fe-nCa achieved about above 90% of radioactive Cs decontamination rate and the volume reduction level also reached around 50-60%. In this paper, we showed the effectiveness of a Fe-nCa method for the rapid remediation and volume reduction method of real radioactive cesium contaminated soils under dry conditions and our challenges for sophistication applying machine and reagents. (author)

  2. Behavior of radioactive cesium during incineration of radioactively contaminated wastes from decontamination activities in Fukushima.

    Science.gov (United States)

    Fujiwara, Hiroshi; Kuramochi, Hidetoshi; Nomura, Kazutaka; Maeseto, Tomoharu; Osako, Masahiro

    2017-11-01

    Large volumes of decontamination wastes (DW) generated by off-site decontamination activities in Fukushima Prefecture have been incinerated since 2015. The behavior of radioactive cesium during incineration of DW was investigated at a working incineration plant. The incineration discharged bottom ash (BA) and fly ash (FA) with similar levels of radiocesium, and the leachability of the radiocesium from both types of ash was very low (incineration of contaminated municipal solid waste (CMSW) reported in earlier studies. The source of radiocesium in DW-FA is chiefly small particles derived from DW and DW-BA blown into the flue gas, not the deposition of gaseous synthesized radiocesium compounds on the surfaces of ash particles in the flue gas as observed in CMSW incineration. This source difference causes the behavior of radiocesium during waste incineration to differ between DW and CMSW. Copyright © 2017 Elsevier Ltd. All rights reserved.

  3. Preparation and characterization of cesium-137 aluminosilicate pellets for radioactive source applications

    International Nuclear Information System (INIS)

    Schultz, F.J.; Tompkins, J.A.; Haff, K.W.; Case, F.N.

    1981-07-01

    Twenty-seven fully loaded 137 Cs aluminosilicate pellets were fabricated in a hot cell by the vacuum hot pressing of a cesium carbonate/montmorillonite clay mixture at 1500 0 C and 570 psig. Four pellets were selected for characterization studies which included calorimetric measurements, metallography, scanning electron microscope and electron backscattering (SEM-BSE), electron microprobe, x-ray diffraction, and cesium ion leachability measurements. Each test pellet contained 437 to 450 curies of 137 Cs as determined by calorimetric measurements. Metallographic examinations revealed a two-phase system: a primary, granular, gray matrix phase containing large and small pores and small pore agglomerations, and a secondary fused phase interspersed throughout the gray matrix. SEM-BSE analyses showed that cesium and silicon were uniformly distributed throughout both phases of the pellet. This indicated that the cesium-silicon-clay reaction went to completion. Aluminum homogeneity was unconfirmed due to the high background noise associated with the inherent radioactivity of the test specimens. X-ray diffraction analyses of both radioactive and non-radioactive aluminosilicate pellets confirmed the crystal lattice structure to be pollucite. Cesium ion quasistatic leachability measurements determined the leach rates of fully loaded 137 Cs sectioned pollucite pellets to date to be 4.61 to 34.4 x 10 -10 kg m -2 s -1 , while static leach tests performed on unsectioned fully loaded pellets showed the leach rates of the cesium ion to date to be 2.25 to 3.41 x 10 -12 kg m -2 s -1 . The cesium ion diffusion coefficients through the pollucite pellet were calculated using Fick's first and second laws of diffusion. The diffusion coefficients calculated for three tracer level 137 Cs aluminosilicate pellets were 1.29 x 10 -16 m 2 s -1 , 6.88 x 10 -17 m 2 s -1 , and 1.35 x 10 -17 m 2 s -1 , respectively

  4. A densimeter with radioactive isotope of teaching

    International Nuclear Information System (INIS)

    Qu Guopu; Zhao Xiuliang; Cheng Pinjing

    2002-01-01

    A densimeter with radioactive isotope beseemed experiment teaching for speciality of nuclear engineering and nuclear technology in higher education is presented. Principle of work and composing of instrument system are introduced briefly

  5. Hyperfine structure, nuclear spins and magnetic moments of some cesium isotopes

    International Nuclear Information System (INIS)

    Ekstroem, C.; Ingelman, S.; Wannberg, G.

    1977-03-01

    Using an atomic-beam magnetic resonance apparatus connected on-line with the ISOLDE isotope separator, CERN, hyperfine structure measurements have been performed in the 2 Ssub(1/2) electronic ground state of some cesium isotopes. An on-line oven system which efficiently converts a mass separated ion-beam of alkali isotopes to an atomic beam is described in some detail. Experimentally determined nuclear spins of sup(120, 121, 121m, 122, 122m, 123, 124, 126, 128, 130m, 135m)Cs and magnetic moments of sup(122, 123, 124, 126, 128, 130)Cs are reported and discussed in terms of different nuclear models. The experimental data indicate deformed nuclear shapes of the lightest cesium isotopes. (Auth.)

  6. Recent advances of numerical simulation studies for radioactive cesium adsorption on soil materials

    International Nuclear Information System (INIS)

    Okumura, Masahiko; Nakamura, Hiroki; Machida, Masahiko

    2013-01-01

    Radiocesium (Cesium 134 and 137) emitted from destroyed Fukushima Daiichi Nuclear Power Production Station is known mostly to remain for a long time on earth's surfaces and to become sources of radiation exposure to habitants. Large scale decontamination work carried out by national and local governments inevitably produces tremendous amount of radioactive wastes of soils whose volume must be effectively and economically reduced based on a scientifically reliable technique. This paper employs the atomic and molecular simulation method applied to adsorption mechanism of soils and cesium ions and presents the examples of proposals with the results of this field. (S. Ohno)

  7. Intercomparison of numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster

    Energy Technology Data Exchange (ETDEWEB)

    Kawamura, H.; Kobayshi, T.; Furuno, A. [Japan Atomic Energy Agency, Ibaraki (Japan); Usui, N.; Kamachi, M. [Japan Meteorological Agency, Meteorological Research Inst., Ibaraki (Japan); Nishikawa, S.; Ishikawa, Y. [Japan Agency for Marine-Earth Science and Tech., Kanagawa (Japan)

    2014-07-01

    We conducted numerical simulations on oceanic dispersion of the radioactive cesium released because of the Fukushima disaster in the North Pacific. Two independent oceanic reanalysis data were used in the simulations. Both simulations suggested that the {sup 137}Cs concentration had been reduced to the pre-Fukushima level around 2.5 years after the disaster. The intercomparison revealed that meso-scale eddies accompanied by the Kuroshio Extension may have efficiently diluted the radioactive cesium at the sea surface. The meso-scale eddies also played an important role in transporting the surface radioactive cesium into the intermediate layer. (author)

  8. Quantitative analysis on dose to humans as a result of consuming tuna fish contaminated by cesium radionuclides

    International Nuclear Information System (INIS)

    Khani, J.; Donev, J.M.K.C.

    2014-01-01

    Quantitative empirical data is presented on the dose exposure to North Americans consuming tuna fish that have accumulated concentrations of radioactive isotopes. The two particular radioactive isotopes of interest are cesium-137 and cesium-134. Though biological effects of radiation are a widely debatable topic, the consumption of tuna fish does not support significant increased risk of cancer to humans. An important comparison is made between the elevated levels of radioactive cesium concentrations to naturally occurring radionuclides, namely potassium-40 and polonium-210. It is calculated that naturally occurring radioactive isotopes are in the orders of magnitude greater than the cesium radionuclides in tuna fish. (author)

  9. Quantitative analysis on dose to humans as a result of consuming tuna fish contaminated by cesium radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Khani, J.; Donev, J.M.K.C., E-mail: jykhani@ucalgary.ca, E-mail: jason.donev@ucalgary.ca [Univ. of Calgary, Calgary, AB (Canada)

    2014-07-01

    Quantitative empirical data is presented on the dose exposure to North Americans consuming tuna fish that have accumulated concentrations of radioactive isotopes. The two particular radioactive isotopes of interest are cesium-137 and cesium-134. Though biological effects of radiation are a widely debatable topic, the consumption of tuna fish does not support significant increased risk of cancer to humans. An important comparison is made between the elevated levels of radioactive cesium concentrations to naturally occurring radionuclides, namely potassium-40 and polonium-210. It is calculated that naturally occurring radioactive isotopes are in the orders of magnitude greater than the cesium radionuclides in tuna fish. (author)

  10. The beta strength function structure in β+ decay of lutetium, thulium and cesium isotopes

    International Nuclear Information System (INIS)

    Alkhazov, G.D.; Bykov, A.A.; Vitman, V.D.; Naumov, Yu.V.; Orlov, S.Yu.

    1981-01-01

    The spectra of total γ-absorption in the decays of some Lutecium, Thulium and Cesium isotopes have been measured. The probabilities for level population in the decay of the isotopes have been determined. The deduced beta strength functions reveal pronounced structure. Calculations of the strength functions using the Saxon-Woods potential and the residual Gamow-Teller interaction are presented. It is shown that in β + decay of light Thulium and Cesium isotopes the strength function comprises more than 70% of the Gamow-Teller excitations with μsub(tau) = +1. This result is the first direct observation of the Gamow-Teller resonance in β + decay of nuclei with Tsub(z) > O. (orig.)

  11. Monitoring dissolved radioactive cesium in Abukuma River in Fukushima Prefecture

    International Nuclear Information System (INIS)

    Yasutaka, Tetsuo; Kawabe, Yoshishige; Kurosawa, Akihiko; Komai, Takeshi

    2013-01-01

    Radioactive materials were released into the atmosphere and deposited over wide areas of farmland, forests, and cities; elevated levels of "1"3"1I, "1"3"4Cs, and "1"3"7Cs have been detected in these areas due to the accident at the Tokyo Power Fukushima Daiichi Nuclear Power Plant caused by the April 2011 earthquake and tsunami in eastern Japan. Radioactive Cs deposited on farmland and forests gradually leaches into water bodies such as mountain streams and rivers adsorbed onto particles or in a dissolved state. It is important to calrify the level of dissolved and total radioactive Cs in environmental water for forecasting the of discharge of radioactive Cs from forest and watersheds, assessing on the effect of dissolved and total radioactive Cs on not only irrigation water but also rice and other crops, and evaluating the transport of radioactive Cs from rivers to costal areas. Therefore, it is important to monitor their levels in Fukushima Prefecture over time. In this research, we monitored the levels of dissolved and total radioactive Cs in Abukuma River using a conventional evaporative concentration method. By monitoring the river waters since September 2012, it was estimated that the levels of dissolved radioactive Cs were less than 0.128 Bq/L and those of total radioactive Cs were less than 0.274 Bq/L in the main stream and branches of Abukuma River in the low suspended solid condition. (author)

  12. Measurement of cesium and mercury emissions from the vitrification of simulated high level radioactive waste

    International Nuclear Information System (INIS)

    Zamecnik, J.R.

    1992-01-01

    In the Defense Waste Processing Facility at the Savannah River Site, it is desired to measure non-radioactive cesium in the offgas system from the glass melter. From a pilot scale melter system, offgas particulate samples were taken on filter paper media and analyzed by Inductively Coupled Plasma-Mass Spectrometry (ICP-MS). The ICP-MS method proved to be sufficiently sensitive to measure cesium quantities as low as 0.135 μg, with the sensitivity being limited by the background cesium present in the filter paper. This sensitivity allowed determination of cesium decontamination factors for four of the five major components of the offgas system. In addition, total particulate measurements were also made. Measurements of mercury decontamination factors were made on the same equipment; the results indicate that most of the mercury in the offgas system probably exists as elemental mercury and HgCl 2 , with some HgO and Hg 2 Cl 2 . The decontamination factors determined for cesium, total particulate, and mercury all compared favorably with the design values

  13. Therapeutic use of radioactive isotopes

    CERN Document Server

    Caroline Duc

    2013-01-01

    In December, researchers from ISOLDE-CERN, the Paul Scherrer Institute (PSI) and the Institut Laue-Langevin (ILL) published the results of an in vivo study which successfully proved the effectiveness of four terbium isotopes for diagnosing and treating cancerous tumours.   Four terbium isotopes suitable for clinical purposes. “ISOLDE is the only installation capable of supplying terbium isotopes of such purity and intensity in the case of three out of the four types used in this study,” explains Karl Johnson, a physicist at ISOLDE.  “Producing over a thousand different isotopes, our equipment offers the widest choice of isotopes in the world!” Initially intended for fundamental physics research, ISOLDE has diversified its activities over time to invest in various projects in the materials science, biochemistry and nuclear medicine fields. The proof-of-concept study has confirmed that the four terbium isotopes 149Tb, 152Tb, 155Tb produ...

  14. Hygienic assessment of radioactive iodine isotopes

    International Nuclear Information System (INIS)

    Vasilenko, I.Ya.

    1987-01-01

    Sources of radioactive iodine isotopes and their biological significance depending on the way of intake are discussed. The degree of food contamination by radioactive iodine as well as products, which serve as the source of its intake into the human body, and results of their processing are considered. The danger of radioactive iodine intake by different groups of population as well as thyroid irradiation effects are discussed. Description of activities, directed to the human body protection against radioactive iodine and assessment of these protection measures efficiency is presented

  15. A novel role for methyl cysteinate, a cysteine derivative, in cesium accumulation in Arabidopsis thaliana

    DEFF Research Database (Denmark)

    Adams, Eri; Miyazaki, Takae; Hayaishi-Satoh, Aya

    2017-01-01

    Phytoaccumulation is a technique to extract metals from soil utilising ability of plants. Cesium is a valuable metal while radioactive isotopes of cesium can be hazardous. In order to establish a more efficient phytoaccumulation system, small molecules which promote plants to accumulate cesium we...

  16. The international comparison of radioactivity measurements on a solution of cesium-139

    International Nuclear Information System (INIS)

    Steyn, J.; Botha, S.M.; Van Staden, J.C.

    1976-03-01

    The participation by the NPRL in an intercomparison of radioactivity measurements as organised by the BIPM is fully described. The radioisotope involved, cesium 139, was made available to the BIPM by the NPRL in carrier-free form. The NPRL used the 4π gamma coincidence counting method with an internal liquid scintillation counter as 4π detector. The preliminary results released by the BIPM show the presence of relatively large systematic errors [af

  17. Polymer-inorganic composite resins for recovery of radioactive cesium from acidic media

    International Nuclear Information System (INIS)

    Park, J.I.; Kim, J.S.; Jo, A.; Jang, E.; Park, Y.J.

    2014-01-01

    In this work, our objectives are as follow: i) the development of a method to produce polymer-ammonium molybdophosphate composite resins with the size range ideal for column operations, ii) the preparation of a different type of polymer-AMP granules, other than polyacrylonitrile, with good physical and chemical stability, and iii) the investigation of sorption and recovery properties of the composite potentially useful for radioactive cesium. (author)

  18. Prussian blue as an antidote for radioactive thallium and cesium poisoning

    Directory of Open Access Journals (Sweden)

    Altagracia-Martinez M

    2012-06-01

    Full Text Available Marina Altagracia-Martínez, Jaime Kravzov-Jinich, Juan Manuel Martínez-Núñez, Camilo Ríos-Castañeda, Francisco López-NaranjoDepartments of Biological Systems and Health Care, Biological and Health Sciences Division, Universidad Autónoma Metropolitana-Xochimilco, Mexico DF, MexicoBackground: Following the attacks on the US on September 11, 2001, potentially millions of people might experience contamination from radioactive metals. However, before the specter of such accidents arose, Prussian blue was known only as an investigational agent for accidental thallium and cesium poisoning. The purpose of this review is to update the state of the art concerning use of Prussian blue as an effective and safe drug against possible bioterrorism attacks and to disseminate medical information in order to contribute to the production of Prussian blue as a biodefense drug.Methods: We compiled articles from a systematic review conducted from January 1, 1960 to March 30, 2011. The electronic databases consulted were Medline, PubMed, the Cochrane Library, and Scopus.Results: Prussian blue is effective and safe for use against radioactive intoxications involving cesium-137 and thallium. The US Food and Drug Administration has approved Prussian blue as a drug, but there is only one manufacturer providing Prussian blue to the US. Based on the evidence, Prussian blue is effective for use against radioactive intoxications involving cesium-137 and thallium, but additional clinical research on and production of Prussian blue are needed.Keywords: Prussian blue, radioactive cesium, thallium, intoxication, biodefense drug

  19. Uses of Radioactive Isotopes in Industry

    International Nuclear Information System (INIS)

    Plata, A.; Val Cob, M. del; Gamboa, J. M.

    1962-01-01

    The present report contains a list of some of the most important problems in industry that have been approached so far by the use of radioactive isotopes. The list has been compiled trough the experience gained by the authors in revising for several years the most important scientific journal and other sources of information on this subject. The classification of industries has been done in an arbitrary way, choosing those isotope uses that have reached a higher degree of development. (Author)

  20. Removal of cesium using coconut fiber in raw and modified forms for the treatment of radioactive liquid wastes

    International Nuclear Information System (INIS)

    Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar J.; Sakata, Solange K.; Di Vitta, Patricia B.

    2013-01-01

    Sorption is one of the most studied methods to reduce the volume of radioactive waste streams. Cesium-137 is a radioisotope formed by the fission of uranium and it can cause health problems due to its easy assimilation by cells. The aim of this study is to evaluate the potential of coconut fiber in removing cesium from radioactive liquid wastes; this process can help in disposing radioactive waste. The experiments were performed in batch and the particle size of the fiber ranged between 0.30 mm and 0.50 mm. The fiber was treated with hydrogen peroxide in alkaline medium. The following parameters were analyzed: contact time, pH and concentration of cesium ions in aqueous solution. After the experiments the samples were filtered and cesium remaining in solution was quantified by inductively coupled plasma optical emission spectrometry. (author)

  1. Removal of cesium using coconut fiber in raw and modified forms for the treatment of radioactive liquid wastes

    Energy Technology Data Exchange (ETDEWEB)

    Jesus, Nella N.M. de; Nobre, Vanessa B.; Potiens Junior, Ademar J.; Sakata, Solange K., E-mail: sksakata@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil); Di Vitta, Patricia B. [Universidade de Sao Paulo (USP), SP (Brazil). Instituto de Quimica

    2013-07-01

    Sorption is one of the most studied methods to reduce the volume of radioactive waste streams. Cesium-137 is a radioisotope formed by the fission of uranium and it can cause health problems due to its easy assimilation by cells. The aim of this study is to evaluate the potential of coconut fiber in removing cesium from radioactive liquid wastes; this process can help in disposing radioactive waste. The experiments were performed in batch and the particle size of the fiber ranged between 0.30 mm and 0.50 mm. The fiber was treated with hydrogen peroxide in alkaline medium. The following parameters were analyzed: contact time, pH and concentration of cesium ions in aqueous solution. After the experiments the samples were filtered and cesium remaining in solution was quantified by inductively coupled plasma optical emission spectrometry. (author)

  2. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  3. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes; Etude par spectroscopie atomique de proprietes nucleaires d'isotopes de francium et de cesium

    Energy Technology Data Exchange (ETDEWEB)

    Coc, A

    1986-04-15

    This work is based on the study of cesium ({sup 118,146}Cs) and francium ({sup 207-213}Fr,{sup 220-228}Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  4. Immobilization of aqueous radioactive cesium wastes by conversion to aluminosilicate minerals

    International Nuclear Information System (INIS)

    Barney, G.S.

    1975-05-01

    Radioactive cesium (primarily 137 Cs) is a major toxic constituent of liquid wastes from nuclear fuel processing plants. Because of the long half-life, highly penetrating radiation, and mobility of 137 Cs, it is necessary to convert wastes containing this radioisotope into a solid form which will prevent movement to the biosphere during long-term storage. A method for converting cesium wastes to solid, highly insoluble, thermally stable aluminosilicate minerals is described. Aluminum silicate clays (bentonite, kaolin, or pyrophyllite) or hydrous aluminosilicate gels are reacted with basic waste solutions to form pollucite, cesium zeolite (Cs-D), Cs-F, cancrinite, or nepheline. Cesium is trapped in the aluminosilicate crystal lattice of the mineral and is permanently immobilized. The identity of the mineral product is dependent on the waste composition and the SiO 2 /Al 2 O 3 ratio of the clay or gel. The stoichiometry and kinetics of mineral formation reactions are described. The products are evaluated with respect to leachability, thermal stability, and crystal morphology. (U.S.)

  5. Transfer of radioactive cesium from soil to rape plants, rape blossoms and rape honey

    International Nuclear Information System (INIS)

    Molzahn, D.; Klepsch, A.; Assmann-Wertmueller, U.

    1989-01-01

    Due to the test of atomic weapons and the accident in the nuclear power plant at Chernobyl, the vegetation in Germany has been exposed to cesium contamination in the soil. It was to be expected that activity would migrate from soil to plants and to food products. In this work, the transfer of radioactive cesium from soil to rape plants (Brassica napus var. oleifera), rape blossoms and further to rape honey was investigated. By measuring the gamma activity of cesium using germanium detectors with measuring capacity up to 30 h per sample (limit of detection about 0.14 Bq/kg to 0.19 Bq/kg), we determined a mean transfer factor f cs = 0,116 ± 0,080 for the system soil-rape plant, f cs = 0.065 + 0.075 for the system soil-rape blossom and F!S = 0.098 + 0.044 for the system soil-rape honey (plants and honey wet mass, soil dry mass) (Table IV). Additionally, for the transfer of cesium from rape plants to rape honey, a factor of f cs = 2.04 ± 7.23 (both wet mass) was determined. Due to some environmental circumstances, which can hardly ever be taken into account, the results obtained sometimes differ considerably. Nevertheless, the mean transfer factors are within the range of values found in literature (Table V) [de

  6. Mass measurement of radioactive isotopes

    CERN Document Server

    Kluge, H J; Scheidenberger, C

    2004-01-01

    The highest precision in mass measurements on short-lived radionuclides is obtained using trapping and cooling techniques. Here, the experimental storage ring (ESR) at GSI/Darmstadt and the tandem Penning trap mass spectrometer ISOLTRAP at ISOLDE/CERN play an important role. Status and recent results on mass measurements of radioactive nuclides with ESR and ISOLTRAP are summarized.

  7. Radioactive isotopes in solid-state physics

    CERN Document Server

    Deicher, M

    2002-01-01

    Radioactive atoms have been used in solid-state physics and in material science for many decades. Besides their classical application as tracer for diffusion studies, nuclear techniques such as M\\"ossbauer spectroscopy, perturbed angular correlation, $\\beta$-NMR, and emission channelling have used nuclear properties (via hyperfine interactions or emitted particles) to gain microscopical information on the structural and dynamical properties of solids. During the last decade, the availability of many different radioactive isotopes as a clean ion beam at ISOL facilities such as ISOLDE at CERN has triggered a new era involving methods sensitive for the optical and electronic properties of solids, especially in the field of semiconductor physics. Extremely sensitive spectroscopic techniques like deep-level transient spectroscopy (DLTS), photoluminescence (PL), and Hall effect have gained a new quality by using radioactive isotopes. Because of their decay the chemical origin of an observed electronic and optical b...

  8. Derivation of cesium-137 residual radioactive material guidelines for the Peek Street site, Schenectady, New York

    International Nuclear Information System (INIS)

    Jones, L.; Nimmagadda, M.; Yu, C.

    1992-01-01

    Residual radioactive material guidelines for cesium-137 were derived for the Peek rk. The derivation was based on the requirement that the Street site in Schenectady, New York. The derivation was based on the requirement that the 50-year committed effective dose equivalent to a hypothetical individual who lives or works in the immediate vicinity of the Peek Street site should not exceed a dose of 100 mrem/yr following remedial action. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD was used in this evaluation. Three potential scenarios were considered for the site on the assumption that for a period of 1,000 years following remedial action, the site wig be utilized without radiological restrictions. The scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. Results indicate that the basic dose limit of 100 mrem/yr will not be exceeded for cesium-137 within 1,000 years, provided that the soil concentration of cesium-137 at the Peek Street site does not exceed the following levels: 98 pCi/g for Scenario A (industrial worker: the expected scenario), 240 pCi/g for Scenario B (recreationist: a plausible scenario), and 34 pCi/g for Scenario C (resident farmer ingesting food produced in the decontaminated area: a plausible scenario)

  9. Overview of insoluble radioactive cesium particles emitted from the Fukushima Dai-ichi Nuclear Power Station

    Science.gov (United States)

    Satou, Yukihiko

    2017-04-01

    In the early stage of the Fukushima Dai-ichi Nuclear Power Station (F1NPS) accident, number of spot type contamination has been observed in computed autoradiography (Kashimura 2013, Shibata 2013, Satou 2014). It's means presence of radioactive particles, however, insoluble cesium particle was overlooked because cesium, which is dominant radioactive element in the accident, becomes ionized in the environment. Adachi et al. (2013) showed presence of cesium (Cs)-bearing particles within air dust sample collected at Tsukuba, 170 km south from the Fukushima site, in midnight of 14 to morning of 15 March 2011. These particles were micrometer order small particles and Cs was could be detectable as element using an energy dispersive X-ray spectroscopy (EDX). However, other radioactive elements such as Co-60, Ru-103 and uranium, which were dominant element of radioactive particles delivered from Chernobyl accident, could not detected. Abe et al. (2014) employed a synchrotron radiation (SR)-micro(μ)-X-ray analysis to the Cs-bearing particles, and they were concluded that (1) contained elements derived from nuclear fission processes and from nuclear reactor and fuel materials; (2) were amorphous; (3) were highly oxidized; and (4) consisted of glassy spherules formed from a molten mixture of nuclear fuel and reactor material. In addition, Satou et al. (2016) and Yamaguchi et al. (2016) disclosed that silicate is main component of Cs-bearing particles. Satou et al. (2015) discovered two types of radioactive particles from soil samples collected in the vicinity of the F1NPS. These particles were remained in the natural environment more than four years, silicate is main component in common of each group particles. Group A particles were very similar to Cs-bearing particles reported by Adachi et al. except particle shape. On the other hand, group B is big particles found in north area from the F1NPS, and the strongest particles contained 20 kBq of Cs-137 within a particle

  10. Spatiotemporal distribution of radioactive cesium released from Fukushima Daiichi Nuclear Power Station in the sediment of Tokyo Bay, Japan

    International Nuclear Information System (INIS)

    Nakagawa, Ryota; Ishida, Masanobu; Baba, Daisuke; Tanimoto, Satomi; Okamoto, Yuichi; Yamazaki, Hideo

    2013-01-01

    The spatial and temporal distribution of "1"3"4Cs and "1"3"7Cs released from Fukushima Daiichi Nuclear Power Station in the Tokyo Bay sediments were investigated. The total radioactivity of "1"3"4Cs and "1"3"7Cs detected in the Tokyo Bay sediment ranged from 240 to 870 Bq/kg-dry in the estuary of Arakawa River, but the activities detected in other sites were about 90 Bq/kg-dry or less. These results suggested that radioactive cesium, which precipitated to the ground, was carried to the river along with clay particles by rainfall and transported to the estuary. The vertical distribution of radioactive cesium showed that it invaded deeper than estimated based on the accumulation rate of the sediment. It was described that the vertical distribution of radioactive cesium was affected by physical mixing of sediments by tidal current, flood, and bioturbation of benthos. (author)

  11. Effective extraction of radioactive cesium from various pollutants with a detergent solution including Mg2+ and K+

    International Nuclear Information System (INIS)

    Noguchi, Yuki; Kida, Toshiyuki; Kato, Eiichi; Akashi, Mitsuru; Shimizu, Kikuo

    2015-01-01

    Radioactive cesium (Cs) is extracted effectively from various polluted samples such as soil, silt, and burned ash by washing with a detergent solution comprised of KCl, MgCl 2 , and hydroxyethyl cellulose in a 5% H 2 SO 4 aqueous solution. Repeatedly washing extracts more than 65% of the radioactive Cs. (author)

  12. Radioactive cesium removal from seawater using adsorptive fibers prepared by radiation-induced graft polymerization

    International Nuclear Information System (INIS)

    Goto, Shota; Kawai-Noma, Shigeko; Umeno, Daisuke; Saito, Kyoichi; Fujiwara, Kunio; Sugo, Takanobu; Kikuchi, Takahiro; Morimoto, Yasutomi

    2015-01-01

    The meltdown of three reactors of the TEPCO Fukushima Daiichi nuclear power station (NPS) caused by the Great East Japan Earthquake on March 11th 2011 resulted in the emission of radionuclides such as cesium-137 and strontium-90 to the environment. For example, radioactive cesium exceeding the legal discharge limit (90 Bq/L, 2×10 -13 M) was detected in the seawater of the seawater-intake area of the NPS at the end of September 2014. Adsorbents with a high selectivity for cesium ions over other alkali metal ions such as sodium and potassium ions are required for cesium removal from seawater because sodium and potassium ions dissolve respectively at much higher concentrations of 5×10 -1 and 1×10 -2 M than cesium ions (2×10 -9 M). In addition, the simple operations of the immersion in seawater and the recovery of the adsorbents from seawater are desirable at decontamination sites. We prepared a cobalt-ferrocyanide-impregnated fiber capable of specifically capturing cesium ions in seawater by radiation-induced graft polymerization and chemical modifications. First, a commercially available 6-nylon fiber was irradiated with γ-rays. Second, an epoxy-group-containing vinyl monomer, glycidyl methacrylate, was graft-polymerized onto the γ-ray-irradiated nylon fiber. Third, the epoxy ring of the grafted polymer chain was reacted with triethylenediamine to obtain an anion-exchange fiber. Fourth, ferrocyanide ions, [Fe(CN) 6 ] 4 - , were bound to the anion-exchange group of the polymer chains. Finally, the ferrocyanide-ion-bound-fiber was placed in contact with cobalt chloride to precipitate insoluble cobalt ferrocyanide onto the polymer chains. Insoluble cobalt ferrocyanide was immobilized at the periphery of the fiber. However, the impregnation structure remains unclear. Here, we clarified the structure of insoluble cobalt ferrocyanide impregnated onto the polymer chain grafted onto the fiber to ensure the chemical and physical stability of the adsorptive fiber in

  13. Radioactive isotopes in occupational health

    International Nuclear Information System (INIS)

    Favino, Angelo.

    1976-01-01

    It is highly desirable today to know and use for industrial medicine purposes all scientific and technological data available in the field of nuclear medicine. The present textbook is an inventory of all possibilities given to occupational doctors in order to pronounce a judgement of ability to work on the occasion of preemployment or routine medical examinations. Such applications require a high degree of competence in radiological protection and also require observation of the basic Safety Standards of Euratom and of the recommendations of the International Committee on Radiological Protection, the same safety principles having been incorporated in all the legislations of the Member States of the Community. In this book a number of chapters are devoted to the description of the basic principles for maximum permissible doses, dosimetric surveillance, medical supervision of workers exposed to ionizing radiations, and medical treatments to be used after a radioactive contamination. In addition a small number of preventive measures are described for all utilisations of radioactive substances for diagnostic or therapeutic purposes

  14. Separation of cesium from intermediate level liquid radioactive waste by solvent extraction with antioxidants

    International Nuclear Information System (INIS)

    Gulis, G.

    1989-01-01

    Antioxidants AO 2246, AO 4, AO 4K, AO 301 (Czechoslovakia) and NOCRAC 2246 (Japan) were tested as extracting agents for the separation of cesiium by solvent extraction with substituted phenols. The following effects on extraction were studied: pH of water phase, influence of diluent and of antioxidant concentration, extraction time, influence of salt content. The extraction of cesium from liquid radioactive waste was tested. The best results were obtained by NOCRAC 2246 in nitrobenzene, the extraction efficiency was 92.3% with pH 13.23. (author) 7 refs.; 5 figs.; 4 tabs

  15. Uptake and transport of radioactive cesium and strontium into grapevines after leaf contamination

    Science.gov (United States)

    Zehnder, H. J.; Kopp, P.; Eikenberg, J.; Feller, U.; Oertli, J. J.

    1995-07-01

    From 1989 to 1993 the foliar uptake of radioactive strontium (Sr-85) and cesium (Cs-134) by selected leaves of grapevine plants and the subsequent redistribution within the plants was examined under controlled conditions in a greenhouse. The radionuclides were applied as chlorides. These plants were grown in large pots containing a mixture of local soil and peat. Plant and soil samples were analyzed throughout the growing season and also during the following vegetation period. Only traces of the applied radiostrontium were taken up by the leaves. This element was essentially not redistributed within the plants. In contrast, radiocesium was easily taken up through the leaf surface, transported to other plant parts and to some extent released from the roots into the soil. Cesium reaching the soil may interact with clay particles causing a very reduced availability for plants. Therefore the soil may act as a long-term sink for radiocesium. On the other hand, grape berries represent transient sinks. The cesium levels in the berries decreased again in a late phase of maturation, but the mechanisms causing this loss are not yet identified. During the second vegetation period, only a very minor proportion of the radiocesium taken up previously by the plants was present in the above ground parts.

  16. Safe handling of radioactive isotopes. Handbook 42

    International Nuclear Information System (INIS)

    1949-09-01

    With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling and utilization. Through the courtesy of the National Research Council about a year ago, several hundred draft copies of this report were circulated to all leading workers and authorities in the field for comment and criticism. The present handbook embodies all pertinent suggestions received from these people. Further comment will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this handbook lay in the uncertainty regarding permissible radiation exposure levels - particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the two subcommittees mentioned above. The present Handbook has been prepared by the Subcommittee on the Handling of Radioactive Isotopes and Fission Products

  17. Safe handling of radioactive isotopes. Handbook 42

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1949-09-15

    With the increasing use of radioactive isotopes by industry, the medical profession, and research laboratories, it is essential that certain minimal precautions be taken to protect the users and the public. The recommendations contained in this handbook represent what is believed to be the best available opinions on the subject as of this date. As our experience with radioisotopes broadens, we will undoubtedly be able to improve and strengthen the recommendations for their safe handling and utilization. Through the courtesy of the National Research Council about a year ago, several hundred draft copies of this report were circulated to all leading workers and authorities in the field for comment and criticism. The present handbook embodies all pertinent suggestions received from these people. Further comment will be welcomed by the committee. One of the greatest difficulties encountered in the preparation of this handbook lay in the uncertainty regarding permissible radiation exposure levels - particularly for ingested radioactive materials. The establishment of sound figures for such exposure still remains a problem of high priority for many conditions and radioactive substances. Such figures as are used in this report represent the best available information today. If, in the future, these can be improved upon, appropriate corrections will be issued. The subject will be under continuous study by the two subcommittees mentioned above. The present Handbook has been prepared by the Subcommittee on the Handling of Radioactive Isotopes and Fission Products.

  18. Digitisation of radioactive isotope images

    International Nuclear Information System (INIS)

    McCready, V.R.; Chittenden, S.

    1987-01-01

    Our conclusions are that for the production of optimum hard copy digital imaging techniques are essential. For routine imaging each image can be correctly exposed and windowed to ensure accurate diagnosis. Digital imaging is ideal in difficult low activity examinations such as gallium-67 studies, labelled monoclonal antibodies or MIBG imaging. The correct choice of matrix size is important. For high information density imaging the 256x256 matrix size with a large field of view camera seems to be optimum for most types of nuclear medicine examinations. In the low information density situation it is probably better to use a 128x128 matrix with some computer smoothing. An algorithm which modulated the intensity of individual pixels based on the average counting rate along the x- or y-axis would help in accentuating small changes in radioactivity. From our experiments in digitising high photon images it is obvious that there should be no edges, lines or empty space visible on the image. To overcome this problem some form of spot wobble is suggested which will only marginally degrade the spacial information on the image. The optimum form of hard copy has yet to be found. So far all forms of paper output have yielded less than satisfactory results. Transparent films appear to be most popular. For this form of output, digital imaging is ideal since the computer can be adjusted so that the end image directly reflects what has been seen on the digital camera monitor. While instant prints are valuable for including in the patients notes, probably the ideal medium is instant hard copy in the form of a transparent image. (orig.) [de

  19. Cobalt and nickel ferrocyanide-functionalized magnetic adsorbent for the removal of radioactive cesium

    Energy Technology Data Exchange (ETDEWEB)

    Hwang, Kyu Sun; Park, Chan Woo; Lee, Kune Woo; Yang, Hee Man [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Park, So Jin [Chungnam National University, Daejeon (Korea, Republic of)

    2017-03-15

    Cobalt ferrocyanide (CoFC) or nickel ferrocyanide (NiFC) magnetic nanoparticles (MNPs) were fabricated for efficient removal of radioactive cesium, followed by rapid magnetic separation of the absorbent from contaminated water. The Fe{sub 3}O{sub 4} nanoparticles, synthesized using a co-precipitation method, were coated with succinic acid (SA) to immobilize the Co or Ni ions through metal coordination to carboxyl groups in the SA. CoFC or NiFC was subsequently formed on the surfaces of the MNPs as Co or Ni ions coordinated with the hexacyanoferrate ions. The CoFC-MNPs and NiFC-MNPs possess good saturation magnetization values (43.2 emu∙g{sup -1} for the CoFC-MNPs, and 47.7 emu∙g{sup -1} for the NiFC-MNPs). The fabricated CoFC-MNPs and NiFC-MNPs were characterized by XRD, FT-IR, TEM, and DLS. The adsorption capability of the CoFC-MNPs and NiFC-MNPs in removing cesium ions from water was also investigated. Batch experiments revealed that the maximum adsorption capacity values were 15.63 mg∙g{sup -1} (CoFC-MNPs) and 12.11 mg∙g{sup -1} (NiFC-MNPs). Langmuir/ Freundlich adsorption isotherm equations were used to fit the experimental data and evaluate the adsorption process. The CoFC-MNPs and NiFC-MNPs exhibited a removal efficiency exceeding 99.09% for radioactive cesium from {sup 137}Cs solution (18-21 Bq∙g{sup -1}). The adsorbent selectively adsorbed {sup 137}Cs, even in the presence of competing cations.

  20. High-sensitivity determination of radioactive cesium in Japanese foodstuffs. 3 years after the Fukushima accident

    International Nuclear Information System (INIS)

    Katsumi Shozugawa; Mayumi Hori; Motoyuki Matsuo

    2016-01-01

    We analyzed 134 Cs, 137 Cs and 40 K in 96 foodstuffs in supermarkets with high sensitivity over 3 years after Fukushima accident. Milk, yoghurt, rice, tea, salmon, cereal, blueberry, miso, and apples had a trace of 134 Cs and 137 Cs from 10 -3 to 100 Bq/kg, however, some mushrooms that were bought in the outer Fukushima prefecture were contaminated by radioactive cesium over the regulatory limit (100 Bq/kg). In view of the 134 Cs/ 137 Cs radioactivity ratio, we can conclude that 137 Cs detected in remote areas 300 km or more from Fukushima Nuclear power plant contained activity from Pre-Fukushima events such as Chernobyl accident (1986) and atmospheric nuclear explosions (from 1945). (author)

  1. Radioactive cesium-134 and cesium-137 measured by ChIbaraki-Kizuna No.1 in the Paleo-Kantoh great depth submarine basin

    International Nuclear Information System (INIS)

    Kimura, Kazuya; Nirei, Hisashi; Yoshida, Takeshi

    2012-01-01

    The 2011 Earthquake off the Pacific Coast of Tohoku caused serious geological disasters, on March 11th. Especially radioactive pollution by the nuclear accident at the Fukushima No. 1 nuclear power plant has the medical environmental problem. We have been researching the actual condition of that in Higashi-Kanto area by use of RT-30 (made by GEORADIS). In the result, it becomes clear that almost radiogen which diffused at a Higashi-Kantou is cesium-134 and cesium-137, and radioactive pollution is also a kind of geo-pollution. In fact, radioactive ingredients move according to mass transfer and deposition rule. For example, we verified that radiogen move and deposit on a water catchment area at a side road of Higashi-kanto Expressway in the northern Chiba prefecture. So, we must make out a unit of geological layer and characteristic features of radioactive materials when investigate and decontamination. If we do that without knowledge of geological unit and radiogen's attribution, radioactive pollution would become diffuse. Just for the record, this was written in the Katori-Narita-Itako International Declaration (IUGS-GEM). (author)

  2. Radioactive cesium elution speed in dried wild Mushrooms collected in 2015

    International Nuclear Information System (INIS)

    Yamaguchi, Toshiro; Arai, Hirotsugu; Ohnuma, Tohru; Arai, Hiromu; Takyu, Sodai; Matsuyama, Tetsuo; Ishii, Keizo

    2016-01-01

    Dried wild mushrooms (12 species, 13 samples) collected in Nagano, Fukushima, and Miyagi Prefectures, Japan, in 2015 were immersed in water for 1,440 min. The elution rate of radioactive cesium (Cs) was calculated based on its radioactivity, which was measured with a high-purity germanium semiconductor detector (GX2018; CANBERRA Industries, Meriden, CT, USA) before and after immersion for each mushroom. Immersion fluid was sampled after 10, 30, 60, 180, 360, and 1,440 min of immersion and dried on aluminum foil. Then, imaging plates (BAS-III, Fujifilm, Tokyo, Japan) exposed to the dried immersion fluid were measured with a Bio-imaging Analyzer System-1800 II (Fujifilm). The 50% elution time of each wild mushroom was calculated based on the photo stimulated luminescence density of the autoradiographs. The radioactive Cs elution rate was > 80% for 11 samples (84% of total) comprising 11 mushroom species. Moreover, the 50% elution time was < 30 min for 9 samples (69% of total) comprising 9 species. This shows that the radioactive Cs elution rate and elution speed were not constant among mushroom species. Based on these results, immersing the mushrooms, which were dried, in water for at least 120 min is an effective method for removing radioactive Cs from wild mushrooms. (author)

  3. Atomic spectroscopy study of nuclear properties of francium and cesium isotopes

    International Nuclear Information System (INIS)

    Coc, A.

    1986-04-01

    This work is based on the study of cesium ( 118,146 Cs) and francium ( 207-213 Fr, 220-228 Fr) isotopes by hyperfine atomic spectroscopy and on the interpretation of these results from the nuclear physics point of view. The measured nuclear quantities are: the spin, the magnetic moment, the electric quadrupole moment and the mean square charge radius. The experimental method which is based on hyperfine optical pumping with a tunable laser, followed by magnetic analysis of the atoms is described in the first part. Results related to atomic physics are also presented. In the second part, these data are interpreted in the framework of nuclear models. The deformation of light cesium isomers are compared to values obtained from a theoretical self-consistent calculation. Heavy francium isotopes are situated in an area where the existence of static octupole deformations have been predicted. The odd-even staggering measured on the mean square radius is abnormal in this region. However, on the basis of experimental data, no definitive conclusion can be drawn regarding the nature of these deformations. (author)

  4. Radioactive isotopes are use wide in medicine

    International Nuclear Information System (INIS)

    Vargas, Celso

    2011-01-01

    The radioactive isotopes are used in medicine to view the status of an organ under different conditions; especially in the evolution of an organism after treatment of a cancer. In this process, three key areas have combined; first, the production of isotopes by developing of accelerators or reactors both linear accelerator and cyclotrons. Second, the use of suitable equipment such as PET (Positron emission tomography) for accurate scan of internal organs at physiological and biochemical level or molecular for diagnosis and effective treatment of diseases such as cancer. Currently, the trend has been to combine PET with other technologies such as CAT (computed axial tomographic) or SPECT (Single photon emission computer tomography). Third and finally, the development of molecules increasingly specific that have allowed to obtain several chemical compounds for different uses [es

  5. The study of sorption of cesium radionuclides by 'T-55' ferrocyanide sorbent from various types of liquid radioactive wastes

    International Nuclear Information System (INIS)

    Semenischev, V.S.; Voronina, A.V.; Bykov, A.A.

    2013-01-01

    The sorption of caesium by T-55 sorbent from different types of liquid radioactive wastes is studied. It is shown that the sorbent can be used for extraction of cesium from high level acidic and saline solutions and also for decontamination of caesium contaminated waters containing surfactants and EDTA. (author)

  6. Copper ferrocyanide - polyurethane foam as a composite ion exchanger for removal of radioactive cesium

    International Nuclear Information System (INIS)

    Rao, S.V.S.; Lal, K.B.; Ahmed, J.; Narasimhan, S.V.

    1999-01-01

    A method has been developed for the removal of cesium from the aqueous radioactive waste using a composite ion-exchanger consisting of Copper-Ferrocyanide Powder (CFC) and Polyurethane (PU) Foam. Polyvinyl acetate has been used as a binder in the preparation of CFC-PU foam. The physical properties of CFC such as density, surface area, IR stretching frequency and lattice parameters have been evaluated and also its potassium and copper(II) content have been estimated. Optimization of loading of CFC on PU foam has been studied. The CFC-PU was viewed under microscope to find out the homogeneity of distribution. Exchange capacities of the CFC-PU foam in different media have been determined and column studies have been carried out. Studies have been undertaken on extraction of cesium from CFC foam and also on digestion of spent CFC-PU foam and immobilization of digested solution in cement matrix. The cement matrices have been characterized with respect to density, bio-resistance and leaching resistance. (author)

  7. Remedial measures against high levels of radioactive cesium in Swedish lake fish

    International Nuclear Information System (INIS)

    Andersson, T.; Nilsson, Aa.; Haakanson, L.; Kvarnaes, H.

    1991-01-01

    The Swedish Radiation Protection Institute (SSI) has provided funds for the testing of methods to reduce the concentration of radioactive cesium in fish. The main purpose of this report is to present to remedies tested and to give an account of the effect they had on the concentration of Cs-137 in fish. In addition, analyses are made of the lake-specific factors contributing to the Cs-uptake in fish in the tested lakes. The time interval between the remedies adopted and the latest fish analyses (about 2 years on average) is not sufficient to statistically establish the small effects of the remedies. A longer time series of data is required for this

  8. Accumulative behavior of radioactive cesium during the incineration of municipal solid waste

    International Nuclear Information System (INIS)

    Mizuhara, Shinji; Kawamoto, Katsuya; Maeseto, Tomoharu; Kuramochi, Hidetoshi; Osako, Masahiro

    2015-01-01

    Understanding the long-term accumulation behavior of radioactive cesium (r- Cs) in municipal solid waste (MSW) incineration plants is important for safety management of them. In this study, first, not only air dose rate but also r-Cs activity in wall adhesion dust at different point in the inside of a MSW incineration plant were measured. The results showed that higher amounts of the Cs were observed in the surface layer of refractory and that higher air dose ratios were obtained in the upstream region in incineration process. However, the Cs content of adhered dust onto the surface material of incineration equipment was higher in downstream than upstream because of the decrease of flue gas temperature. (author)

  9. Criteria for cesium capsules to be shipped as special form radioactive material

    International Nuclear Information System (INIS)

    Lundeen, J.E.

    1994-01-01

    The purpose of this report is to compile all the documentation which defines the criteria for Waste Encapsulation and Storage Facility (WESF) cesium capsules at the IOTECH facility and Applied Radiant Energy Corporation (ARECO) to be shipped as special form radioactive material in the Beneficial Uses Shipping System (BUSS) Cask. The capsules were originally approved as special form in 1975, but in 1988 the integrity of the capsules came into question. WHC developed the Pre-shipment Acceptance Test Criteria for capsules to meet in order to be shipped as special form material. The Department of Energy approved the criteria and directed WHC to ship the capsules at IOTECH and ARECO meeting this criteria to WHC as special form material

  10. Studies of mechanism of radioactive cesium-134 adsorption from water solutions onto tri ammonium dodecamolybdenophosphate(V)

    International Nuclear Information System (INIS)

    Choma, J.; Stasiuk, J.

    1992-01-01

    A mechanism of radioactive cesium-134 adsorption from water solutions on new, inorganic adsorbent composed from 85% of tri ammonium dodecamolibdophosphate(V) and 15% of urea resin is presented. A migration is found of Cs cations into the adsorbent grains. The absorption of Cs-134 beta radiation is studied as a function of WMF-15 tablet thickness. The penetration depth of radionuclide was found to be function of the process duration and the adsorbent density. Diffusion of cesium into the adsorbent grains explains the effect of ''recreation'' of its adsorption capacitance. (author). 2 refs, 2 figs

  11. A method for estimating radioactive cesium concentrations in cattle blood using urine samples.

    Science.gov (United States)

    Sato, Itaru; Yamagishi, Ryoma; Sasaki, Jun; Satoh, Hiroshi; Miura, Kiyoshi; Kikuchi, Kaoru; Otani, Kumiko; Okada, Keiji

    2017-12-01

    In the region contaminated by the Fukushima nuclear accident, radioactive contamination of live cattle should be checked before slaughter. In this study, we establish a precise method for estimating radioactive cesium concentrations in cattle blood using urine samples. Blood and urine samples were collected from a total of 71 cattle on two farms in the 'difficult-to-return zone'. Urine 137 Cs, specific gravity, electrical conductivity, pH, sodium, potassium, calcium, and creatinine were measured and various estimation methods for blood 137 Cs were tested. The average error rate of the estimation was 54.2% without correction. Correcting for urine creatinine, specific gravity, electrical conductivity, or potassium improved the precision of the estimation. Correcting for specific gravity using the following formula gave the most precise estimate (average error rate = 16.9%): [blood 137 Cs] = [urinary 137 Cs]/([specific gravity] - 1)/329. Urine samples are faster to measure than blood samples because urine can be obtained in larger quantities and has a higher 137 Cs concentration than blood. These advantages of urine and the estimation precision demonstrated in our study, indicate that estimation of blood 137 Cs using urine samples is a practical means of monitoring radioactive contamination in live cattle. © 2017 Japanese Society of Animal Science.

  12. Survey and decontamination trial of boat wastes contaminated with radioactive cesium

    International Nuclear Information System (INIS)

    Takigami, Hidetaka; Yamamoto, Takashi; Suzuki, Go; Takeuchi, Yukio; Tanosaki, Takao; Takata, Mitsuyasu; Okubo, Takuro

    2013-01-01

    Field survey was conducted to investigate radioactive cesium contamination status of the fiber reinforced plastic (FRP) boats which were damaged by the Great East Japan Earthquake and resulting tsunami, and further affected by nuclear fallout from the accident at the Fukushima No. 1 nuclear power plant. Radiation dose rate was measured targeted at some selected boats and the surrounding environment by using radiation survey meters (i.e., NaI (Tl) scintillation counter and GM counter) and a radiation-sensing camera in order to visualize a dose rate distribution within the area. In addition, FRP parts, sediment deposits and stagnant waters in the boats were sampled and their "1"3"4Cs and "1"3"7Cs radioactivity were measured by gamma-ray spectrometry using NaI (Tl) scintillation or Ge detector. From the monitoring results, materials or sediments in the boats enhanced the radiation levels, however, which can be significantly reduced by decontamination operations such as removal and wash-out of the materials or sediments (i.e., countermeasures for surface-deposited radioactivity). Consequently, the conducted survey and decontamination approaches became a good model and promoted a prompt dismantlement, removal and further disposal/recycle by the local authorities concerned. (author)

  13. Transporting dynamics of radioactive cesium in a forest ecosystem and its discharge processes

    Energy Technology Data Exchange (ETDEWEB)

    Iseda, Kohei; Ohte, Nobuhito; Tanoi, Keitaro; Endo, Izuki; Oda, Tomoki; Kato, Hiroyu [Graduate School of Agricultural and Life Sciences, University of Tokyo (Japan)

    2014-07-01

    A lot of radioactive substance including {sup 137}Cs, {sup 134}Cs fell out to Tohoku and Kanto region in particular Fukushima prefecture after the accident of Fukushima-daiichi nuclear power plant. Generally, cesium tends to attach to clay particle and organic matter. These clay particle and organic matter can potentially flow out from the forest through the river to the downstream not only as particulate matter but also dissolved matter. It is likely that behavior of cesium is similar to sediment locomotion. The objective of this study is to understand transporting dynamics of radioactive cesium inside and outside of the forest. We started investigations on transporting dynamics of cesium in the forest upper stream of Kami-Oguni river in Date city Fukushima prefecture located in about 50 km from the nuclear power plant since July 2012. We conducted river water sampling at 9 points along the river from the uppermost stream to the middle reaches during low flow condition once a month. We also sampled river water during storm event for 5 times in order to capture the change of {sup 137}Cs concentration in a flood stage. Samples were filtered and separated into particulate and dissolved matters using glass micro-fiber filters (GF/F). Samples were analyzed their {sup 137}Cs concentration by Germanium semiconductor detector at University of Tokyo. During low flow condition, {sup 137}Cs was detected only a very small amount both in particulate and dissolved matters. In contrast, during high flow condition, {sup 137}Cs was detected about 10-100 times higher than that of during low flow condition in particulate matter. We estimated discharge flux of {sup 137}Cs from the forest using the relations between water discharge and {sup 137}Cs concentration. It was 0.977 Bq/(m2 day ) (2012/8/31-2013/4/19). In the forest, we set 2 deciduous tree plots (Quercus serrata, Zelkova serrata and so on) and 1 evergreen confer plot (Cyptomeria japonica). Atmospheric depositions of {sup 137

  14. Evaluation of physicochemical properties of radioactive cesium in municipal solid waste incineration fly ash by particle size classification and leaching tests.

    Science.gov (United States)

    Fujii, Kengo; Ochi, Kotaro; Ohbuchi, Atsushi; Koike, Yuya

    2018-07-01

    After the Fukushima Daiichi-Nuclear Power Plant accident, environmental recovery was a major issue because a considerable amount of municipal solid waste incineration (MSWI) fly ash was highly contaminated with radioactive cesium. To the best of our knowledge, only a few studies have evaluated the detailed physicochemical properties of radioactive cesium in MSWI fly ash to propose an effective method for the solidification and reuse of MSWI fly ash. In this study, MSWI fly ash was sampled in Fukushima Prefecture. The physicochemical properties of radioactive cesium in MSWI fly ash were evaluated by particle size classification (less than 25, 25-45, 45-100, 100-300, 300-500, and greater than 500 μm) and the Japanese leaching test No. 13 called "JLT-13". These results obtained from the classification of fly ash indicated that the activity concentration of radioactive cesium and the content of the coexisting matter (i.e., chloride and potassium) temporarily change in response to the particle size of fly ash. X-ray diffraction results indicated that water-soluble radioactive cesium exists as CsCl because of the cooling process and that insoluble cesium is bound to the inner sphere of amorphous matter. These results indicated that the distribution of radioactive cesium depends on the characteristics of MSWI fly ash. Copyright © 2018 Elsevier Ltd. All rights reserved.

  15. Isotopic analysis of radioactive waste packages (an inexpensive approach)

    International Nuclear Information System (INIS)

    Padula, D.A.; Richmond, J.S.

    1983-01-01

    A computer printout of the isotopic analysis for all radioactive waste packages containing resins, or other aqueous filter media is now required at the disposal sites at Barnwell, South Carolina, and Beatty, Nevada. Richland, Washington requires an isotopic analysis for all radioactive waste packages. The NRC (Nuclear Regulatory Commission), through 10 CFR 61, will require shippers of radioactive waste to classify and label for disposal all radioactive waste forms. These forms include resins, filters, sludges, and dry active waste (trash). The waste classification is to be based upon 10 CFR 61 (Section 1-7). The isotopes upon which waste classification is to be based are tabulated. 7 references, 8 tables

  16. Hyperaccumulation of radioactive isotopes by marine algae

    International Nuclear Information System (INIS)

    Ishii, Toshiaki; Hirano, Shigeki; Watabe, Teruhisa

    2003-01-01

    Hyperaccumlators are effective indicator organisms for monitoring marine pollution by heavy metals and artificial radionuclides. We found a green algae, Bryopsis maxima that hyperaccumulate a stable and radioactive isotopes such as Sr-90, Tc-99, Ba-138, Re-187, and Ra-226. B. maxima showed high concentration factors for heavy alkali earth metals like Ba and Ra, compared with other marine algae in Japan. Furthermore, this species had the highest concentrations for Tc-99 and Re-187. The accumulation and excretion patterns of Sr-85 and Tc-95m were examined by tracer experiments. The chemical states of Sr and Re in living B. maxima were analyzed by HPLC-ICP/MS, LC/MS, and X-ray absorption fine structure analysis using synchrotron radiation. (author)

  17. Water hyacinth for phytoremediation of radioactive waste simulate contaminated with cesium and cobalt radionuclides

    International Nuclear Information System (INIS)

    Saleh, H.M.

    2012-01-01

    Highlights: ► Phytoremediation of radioactive wastes containing 137 Cs and 60 Co radionuclides. ► Using water hyacinth for radioactive waste treatment. ► Bioaccumulation of radionuclides from radioactive waste streams. ► Factors affecting bioaccumulation of 137 Cs and 60 Co using floating plants. - Abstract: Phytoremediation is based on the capability of plants to remove hazardous contaminants present in the environment. This study aimed to demonstrate some factors controlling the phytoremediation efficiency of live floating plant, water hyacinth (Eichhornia crassipes), towards the effluents contaminated with 137 Cs and/or 60 Co. Cesium has unknown vital biological role for plant while cobalt is one of the essential trace elements required for plant. The main idea of this work i.e. using undesirable species, water hyacinth, in purification of radiocontaminated aqueous solutions has been receiving much attention. The controlling factors such as radioactivity concentration, pH values, the amount of biomass and the light were studied. The uptake rate of radiocesium from the simulated waste solution is inversely proportional to the initial activity content and directly proportional to the increase in mass of plant and sunlight exposure. A spiked solution of pH ≈ 4.9 was found to be the suitable medium for the treatment process. The uptake efficiency of 137 Cs present with 60 Co in mixed solution was higher than if it was present separately. On the contrary, uptake of 60 Co is affected negatively by the presence of 137 Cs in their mixed solution. Sunlight is the most required factor for the plant vitality and radiation resistance. The results of the present study indicated that water hyacinth may be a potential candidate plant of high concentration ratios (CR) for phytoremediation of radionuclides such as 137 Cs and 60 Co.

  18. Distribution of Radioactive Cesium during Milling and Cooking of Contaminated Buckwheat.

    Science.gov (United States)

    Hachinohe, Mayumi; Nihei, Naoto; Kawamoto, Shinichi; Hamamatsu, Shioka

    2018-06-01

    To clarify the behavior of radioactive cesium (Cs) in buckwheat grains during milling and cooking processes, parameters such as processing factor (Pf) and food processing retention factor (Fr) were evaluated in two lots of buckwheat grains, R1 and R2, with different concentrations of radioactive Cs. Three milling fractions, the husk, bran, and flour fractions, were obtained using a mill and electric sieve. The radioactive Cs ( 134 Cs + 137 Cs) concentrations in husk and bran were higher than that in grain, whereas the concentration in flour was lower than that in grain. Pf values for the flours of R1 and R2 were 0.60 and 0.80, respectively. Fr values for the flours of R1 and R2 were 0.28 and 0.53, respectively. Raw buckwheat noodles (soba) were prepared using a mixture of buckwheat flour and wheat flour according to the typical recipe and were cooked with boiling water for 0.5, 1, and 2 min, followed by rinsing with water. Pf values for the soba boiled for 2 min (optimal for eating) made with R1 and R2 were 0.34 and 0.40, respectively. Fr values for these R1 and R2 samples were 0.55 and 0.66, respectively. Pf and Fr values for soba boiled for different times for both R1 and R2 were less than 0.6 and 0.8, respectively. Thus, buckwheat flour and its product, soba, cooked by boiling, are considered acceptable for human consumption according to the standard limit for radioactive Cs in buckwheat grains.

  19. Water hyacinth for phytoremediation of radioactive waste simulate contaminated with cesium and cobalt radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, H.M., E-mail: hosamsaleh70@yahoo.com [Radioisotope Department, Nuclear Research Center, Atomic Energy Authority, Dokki 12311, Giza (Egypt)

    2012-01-15

    Highlights: Black-Right-Pointing-Pointer Phytoremediation of radioactive wastes containing {sup 137}Cs and {sup 60}Co radionuclides. Black-Right-Pointing-Pointer Using water hyacinth for radioactive waste treatment. Black-Right-Pointing-Pointer Bioaccumulation of radionuclides from radioactive waste streams. Black-Right-Pointing-Pointer Factors affecting bioaccumulation of {sup 137}Cs and {sup 60}Co using floating plants. - Abstract: Phytoremediation is based on the capability of plants to remove hazardous contaminants present in the environment. This study aimed to demonstrate some factors controlling the phytoremediation efficiency of live floating plant, water hyacinth (Eichhornia crassipes), towards the effluents contaminated with {sup 137}Cs and/or {sup 60}Co. Cesium has unknown vital biological role for plant while cobalt is one of the essential trace elements required for plant. The main idea of this work i.e. using undesirable species, water hyacinth, in purification of radiocontaminated aqueous solutions has been receiving much attention. The controlling factors such as radioactivity concentration, pH values, the amount of biomass and the light were studied. The uptake rate of radiocesium from the simulated waste solution is inversely proportional to the initial activity content and directly proportional to the increase in mass of plant and sunlight exposure. A spiked solution of pH Almost-Equal-To 4.9 was found to be the suitable medium for the treatment process. The uptake efficiency of {sup 137}Cs present with {sup 60}Co in mixed solution was higher than if it was present separately. On the contrary, uptake of {sup 60}Co is affected negatively by the presence of {sup 137}Cs in their mixed solution. Sunlight is the most required factor for the plant vitality and radiation resistance. The results of the present study indicated that water hyacinth may be a potential candidate plant of high concentration ratios (CR) for phytoremediation of radionuclides

  20. Survey of environmental radiation in Kawamata-machi, Fukushima-ken (2). Radioactive cesium in wild mushroom

    International Nuclear Information System (INIS)

    Inagaki, Masayo; Yamanishi, Hirokuni; Wakabayashi, Genichiro; Hohara, Sin-ya; Itoh, Tetsuo; Shirasaka, Norifumi; Tanesaka, Eiji; Okumura, Hiroshi; Furukawa, Michio

    2013-01-01

    Large amount of radioactive cesium was emitted from the TEPCO Fukushima Dai-ichi nuclear power plant by the accident into atmospheric air, and a part of the radioactivity was brought to the ground by rain and snowfall. The Yamakiya district in Kawamata-machi, Fukushima is specified as the prepared evacuation zone. The authors collected wild mushrooms in this district as samples with gentle guide of local mushroom lovers in October, 2012. The kinds of mushroom were specified by the mushroom specialist. 16 kinds of mushrooms have been extracted. The extracted mushroom was brought back to the university. The concentration of radioactive cesium was measured by means of the hyperpure germanium semiconductor detector. The concentrations were ranged from 0.5 to 2600 Bq/g, and were different with points of sampling and kinds. The concentrations were compared with before washing and after washing by means of ultrasonic cleaning. The amount of radioactive cesium reduced to the range from 30% to 60% of the before washing. (author)

  1. Distribution of radioactive cesium ((134)Cs Plus(137)Cs) in a contaminated Japanese soybean cultivar during the preparation of tofu, natto, and nimame (Boiled Soybean).

    Science.gov (United States)

    Hachinohe, Mayumi; Kimura, Keitarou; Kubo, Yuji; Tanji, Katsuo; Hamamatsu, Shioka; Hagiwara, Shoji; Nei, Daisuke; Kameya, Hiromi; Nakagawa, Rikio; Matsukura, Ushio; Todoriki, Setsuko; Kawamoto, Shinichi

    2013-06-01

    We investigated the fate of radioactive cesium ((134)Cs plus (137)Cs) during the production of tofu, natto, and nimame (boiled soybean) from a contaminated Japanese soybean cultivar harvested in FY2011. Tofu, natto, and nimame were made from soybean grains containing radioactive cesium (240 to 340 Bq/kg [dry weight]), and the radioactive cesium in the processed soybean foods and in by-product fractions such as okara, broth, and waste water was measured with a germanium semiconductor detector. The processing factor is the ratio of radioactive cesium concentration of a product before and after processing. For tofu, natto, nimame, and for the by-product okara, processing factors were 0.12, 0.40, 0.20, and 0.18, respectively; this suggested that these three soybean foods and okara, used mainly as an animal feed, can be considered safe for human and animal consumption according to the standard limit for radioactive cesium of soybean grains. Furthermore, the ratio of radioactive cesium concentrations in the cotyledon, hypocotyl, and seed coat portions of the soybean grain was found to be approximately 1:1:0.4.

  2. Methods for removing radioactive isotopes from contaminated streams

    International Nuclear Information System (INIS)

    Hoy, D.R.; Hickey, T.N.; Spulgis, I.S.; Parish, H.C.

    1979-01-01

    Methods for removing radioactive isotopes from contaminated gas streams for use in atmospheric containment and cleanup systems in nuclear power plants are provided. The methods provide for removal of radioactive isotopes from a first portion of the contaminated stream, separated from the remaining portion of the stream, so that adsorbent used to purify the first portion of the contaminated stream by adsorption of the radioactive isotopes therefrom can be tested to determine the adsorbing efficacy of the generally larger portion of adsorbent used to purify the remaining portion of the stream

  3. Selective cesium removal from radioactive liquid waste by crown ether immobilized new class conjugate adsorbent.

    Science.gov (United States)

    Awual, Md Rabiul; Yaita, Tsuyoshi; Taguchi, Tomitsugu; Shiwaku, Hideaki; Suzuki, Shinichi; Okamoto, Yoshihiro

    2014-08-15

    Conjugate materials can provide chemical functionality, enabling an assembly of the ligand complexation ability to metal ions that are important for applications, such as separation and removal devices. In this study, we developed ligand immobilized conjugate adsorbent for selective cesium (Cs) removal from wastewater. The adsorbent was synthesized by direct immobilization of dibenzo-24-crown-8 ether onto inorganic mesoporous silica. The effective parameters such as solution pH, contact time, initial Cs concentration and ionic strength of Na and K ion concentrations were evaluated and optimized systematically. This adsorbent was exhibited the high surface area-to-volume ratios and uniformly shaped pores in case cavities, and its active sites kept open functionality to taking up Cs. The obtained results revealed that adsorbent had higher selectivity toward Cs even in the presence of a high concentration of Na and K and this is probably due to the Cs-π interaction of the benzene ring. The proposed adsorbent was successfully applied for radioactive Cs removal to be used as the potential candidate in Fukushima nuclear wastewater treatment. The adsorbed Cs was eluted with suitable eluent and simultaneously regenerated into the initial form for the next removal operation after rinsing with water. The adsorbent retained functionality despite several cycles during sorption-elution-regeneration operations. Copyright © 2014 Elsevier B.V. All rights reserved.

  4. Simultaneous solid phase extraction of cobalt, strontium and cesium from liquid radioactive waste using microcrystalline naphthalene

    International Nuclear Information System (INIS)

    Hamed, Mostafa Mohamed; Attallah, Mohamed Fathy; Metwally, Sayed Sayed

    2014-01-01

    Most of the procedures developed for the extraction of cobalt, strontium and cesium by solid phase extraction do not employ simultaneous extraction of them. In this study, rapid simultaneous removal of Co 2+ , Sr 2+ and Cs + on microcrystalline naphthalene as solid-phase extractant was investigated. These ions were allowed to form chelates with oxine and then adsorbed on freshly microcrystalline naphthalene from aqueous solutions. The solid phase extraction procedure (SPE) was optimized by using model solution containing Co 2+ , Sr 2+ and Cs + in batch system. The effects of different parameters such as variation in pH, reagent concentration, standing time, naphthalene solution concentration and contact time on the simultaneous removal of these ions was studied. The obtained results indicated that, sorption was found to be rapid, and the percentage removal of Co 2+ , Sr 2+ and Cs + was found to be 98, 79 and 68% within 10 min, respectively. The kinetics of the sorption process was investigated to understand the kinetic characteristics of sorption of metal chelates onto microcrystalline naphthalene. The developed procedure has been successfully applied to the removal and recovery of 60 Co and 134 Cs from liquid radioactive waste. The parameters can be used for designing a plant for treatment of wastewater economically.

  5. World new facilities for radioactive isotope beams

    International Nuclear Information System (INIS)

    Motobayashi, T.

    2014-01-01

    The use of unstable nuclei in the form of energetic beams for nuclear physics studies is now entering into a new era. 'New-generation' facilities are either in operation, under construction or being planned. They are designed to provide radioactive isotope (RI) beams with very high intensities over a wide range of nuclides. These facilities are expected to provide opportunities to study nuclear structure, astrophysical nuclear processes and nuclear matter with large proton-neutron imbalance in grate detail. This article reports on the current status of such new-generation RI-beam facilities around the world. In order to cover different energy domains and to meet various scientific demands, the designs of RI-beam facilities are of a wide variety. For example, RIBF in Japan, FAIR in Germany and FRIB in US are based on the fragmentation scheme for beams with energies of a few hundred MeV/nucleon to GeV/nucleon, whereas Spiral2 in France, SPES in Italy, HIE-ISOLDE in Switzerland/France, and the future facility EURISOL in Europe are based on the ISOL method, and aim at providing lower-energy RI beams. There are a many other projects including upgrades of existing facilities in the three continents, America, Asia and Europe

  6. The cobalt radioactive isotopes in environment

    International Nuclear Information System (INIS)

    2007-01-01

    For the year 1993 the total activity released in cobalt is 69 GBq for the whole of nuclear power plants. The part of activity in cobalt for La Hague in 1993 is 8 GBq of 58 Co and 2 GBq of 60 Co. The radioactive isotopes released by nuclear power plants or the reprocessing plant of La Hague under liquid effluents are shared by half between 58 Co and 60 Co. The exposure to sealed sources is the most important risk for the cobalt. The risk of acute exposure can associate a local irradiation of several decades of grays inducing a radiological burns, deep burn to treat in surgery by resection or graft even amputation. A global irradiation of organism for several grays induces an acute irradiation syndrome, often serious. At long term the stochastic effects are represented by leukemia and radio-induced cancers. The increase of probability of their occurrence is 1% by sievert. We must remind that the natural spontaneous probability is 25%. (N.C.)

  7. Latest movements on waste recycling measures. Dynamic state and risk assessment of radioactive cesium in disaster waste

    International Nuclear Information System (INIS)

    Fujikawa, Yoko

    2012-01-01

    A large amount of radioactive substances were discharge by the catastrophe of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company. From the analysis of the dynamic state of radioactive substances in the environment, the radioactive cesium in the land and freshwater environment is distributed much in soil and freshwater sediment (solid phase) rather than in aqueous phase, even though the distribution depends on the composition of liquid phase water and adsorption objects. From this fact, the problem of radioactive cesium in the living environment can be summarized in the problem of solid system disaster waste in the end, such as soil, sediment, sludge, and waste. As for the current situation of disaster waste, this paper introduces the present state of disaster waste, in which treatment operations are not smoothly proceeding due to the large amount of waste, and difficulty in the classification work of waste and incineration treatment work. Regarding the wide-area treatment measures, there are various problems such that some municipalities are cooperative and some municipalities are hesitant about the acceptance of waste with radioactive contamination. As an example, this paper introduces the reviewing process and reference information in Osaka Prefecture regarding the acceptance of waste. (O.A.)

  8. Estimation of radioactive 137-cesium transportation by litterfall, stemflow and throughfall in the forests of Fukushima

    International Nuclear Information System (INIS)

    Endo, Izuki; Ohte, Nobuhito; Iseda, Kohei; Tanoi, Keitaro; Hirose, Atsushi; Kobayashi, Natsuko I.; Murakami, Masashi; Tokuchi, Naoko; Ohashi, Mizue

    2015-01-01

    Since the Fukushima Dai-ichi Nuclear Power Plant accident in March 2011, large areas of the forests around Fukushima have become highly contaminated by radioactive nuclides. To predict the future dynamics of radioactive cesium ( 137 Cs) in the forest catchment, it is important to measure each component of its movement within the forest. Two years after the accident, we estimated the annual transportation of 137 Cs from the forest canopy to the floor by litterfall, throughfall and stemflow. Seasonal variations in 137 Cs transportation and differences between forests types were also determined. The total amount of 137 Cs transported from the canopy to the floor in two deciduous and cedar plantation forests ranged between 3.9 and 11.0 kBq m −2  year −1 . We also observed that 137 Cs transportation with litterfall increased in the defoliation period, simply because of the increased amount of litterfall. 137 Cs transportation with throughfall and stemflow increased in the rainy season, and 137 Cs flux by litterfall was higher in cedar plantation compared with that of mixed deciduous forest, while the opposite result was obtained for stemflow. - Highlights: • Annual flux of 137 Cs by litterfall, throughfall and stemflow was estimated in two types of forest in Fukushima, Japan. • Annual amount of 137 Cs transportation was 3.9–11.0 kBq m −2 year −1 in two years after the accident. • 137 Cs flux by litterfall was higher in cedar plantation than that of mixed deciduous forest. • 137 Cs transportation with throughfall and stemflow increased in rainy season.

  9. Natural radioactive isotopes in food of Polish population

    International Nuclear Information System (INIS)

    Pietrzak-Lis, Z.

    1999-01-01

    The natural radioactive isotopes contamination of basic food products and water in two regions of Poland (Central Poland and Silesia Region) have been measured. The following isotopes have been taken into account: U-234, U-238, Th-228, Th-230, Th-232, Ra-226, Ra-228, Pb-210; Po-210. The annually intake of mentioned isotopes by regional population and relative doses have been assessed for typical diet of adults in Poland

  10. Accurate hydrocarbon estimates attained with radioactive isotope

    International Nuclear Information System (INIS)

    Hubbard, G.

    1983-01-01

    To make accurate economic evaluations of new discoveries, an oil company needs to know how much gas and oil a reservoir contains. The porous rocks of these reservoirs are not completely filled with gas or oil, but contain a mixture of gas, oil and water. It is extremely important to know what volume percentage of this water--called connate water--is contained in the reservoir rock. The percentage of connate water can be calculated from electrical resistivity measurements made downhole. The accuracy of this method can be improved if a pure sample of connate water can be analyzed or if the chemistry of the water can be determined by conventional logging methods. Because of the similarity of the mud filtrate--the water in a water-based drilling fluid--and the connate water, this is not always possible. If the oil company cannot distinguish between connate water and mud filtrate, its oil-in-place calculations could be incorrect by ten percent or more. It is clear that unless an oil company can be sure that a sample of connate water is pure, or at the very least knows exactly how much mud filtrate it contains, its assessment of the reservoir's water content--and consequently its oil or gas content--will be distorted. The oil companies have opted for the Repeat Formation Tester (RFT) method. Label the drilling fluid with small doses of tritium--a radioactive isotope of hydrogen--and it will be easy to detect and quantify in the sample

  11. Radiometric report for a blast furnace tracing with radioactive isotopes

    International Nuclear Information System (INIS)

    Tanase, G.; Tanase, M.

    1995-01-01

    One of the methods to monitor refractory wall of blast furnace is its tracing with radioactive isotopes. The tracer isotope can be detected by two ways: the external dosimetric measurement at the armour of the blast furnace and/or the radiometric measurement of the iron sample charge by charge. Any change in radiometric situation of tracer radioisotope is recorded in a radiometric report. This paper presents an original concept of radiometric report based upon PARADOX and CORELDRAW soft kits. Their advantage are: quick and easy changes, easy recording of current radioactivity of tracer isotope, short history of changes, visual mapping of the tracer isotope and others. In this way we monitored 6 blast furnaces and more than 180 radioactive sources

  12. Atmospheric deposition of radioactive cesium (137Cs) associated with dust events in East Asia

    International Nuclear Information System (INIS)

    Fujiwara, H.

    2010-01-01

    Since the cessation of atmospheric nuclear testing in 1980, there has been no known serious atmospheric contamination by radioactive cesium (sup(137)Cs) apart from the Chernobyl nuclear reactor accident in 1986. There now remain only small amounts of anthropogenic radionuclides in the atmosphere that can be directly related to past testing. However, sup(137)Cs is still regularly found in atmospheric deposition samples in Japan. In this study, we analyzed sup(137)Cs monitoring data, meteorological data, and field survey results to investigate the recent transport and deposition of sup(137)Cs associated with dust phenomena. Monthly records of nationwide sup(137)Cs deposition in Japan during the 1990s show a consistent seasonal variation, with higher levels of deposition occurring in spring. In March 2002, an unexpectedly high amount of sup(137)Cs was deposited in the northwestern coastal area of Japan at the same time as an Asian dust event was observed. Analysis of land-based weather data showed that sandstorms and other dust-raising phenomena also occurred in March 2002 over areas of Mongolia and northeastern China where grassland and shrubs predominated. Furthermore, radioactivity measurements showed sup(137)Cs enrichment in the surface layer of grassland soils in the areas affected by these sandstorms. These results suggest that grasslands are potential sources of sup(137)Cs-bearing dust. Continued desertification of the East Asian continent in response to recent climate change can be expected to result in an increase in sup(137)Cs-bearing soil particles in the atmosphere, and their subsequent re-deposition in Japan. However, soil dust is also raised around Japanese monitoring sites by the strong winds that are common in Japan in spring, and this local dust might also contribute to sup(137)Cs deposition in Japan. To estimate the relative contributions of local and distant dust events to the total sup(137)Cs deposition, we monitored deposition of mineral particles

  13. Understanding of amount and dynamics of radioactive cesium deposited on trees in Fukushima

    Energy Technology Data Exchange (ETDEWEB)

    Endo, Izuki; Ohte, Nobuhito; Iseda, Kohei; Tanoi, Keitaro; Hirose, Atsushi; Kobayashi, Natsuko I. [The University of Tokyo, 113-8657, 1-1-1 Yayoi Bunkyo-ku, Tokyo (Japan); Ishii, Nobuyoshi [National Institute of Radiological Sciences, 263-8555, 4-9-1 Anagawa, Inage-ku, Chiba-shi, Chiba (Japan); Ohashi, Mizue [University of Hyogo, 670-0092, 1-1-12 Shinzaike-Honcho, Himeji, Hyogo (Japan)

    2014-07-01

    The accident of Fukushima Daiichi nuclear power plant after the earthquake and Tsunami in March 11, 2011 caused large amount of radioactive cesium ({sup 134}Cs, {sup 137}Cs) deposition onto the forest in the surrounding areas. River water from the forest area is used for food production and also for drinking water in these regions. In order to predict how radioactive Cs diffuse and discharge from the forest catchments, it is important to understand the amount and dynamics of radioactive Cs deposited on the trees. In this report, we show our preliminary results of {sup 137}Cs deposition in forest. Study was conducted in the forest at the upstream of Kami-Oguni River catchment, northern part of Fukushima Prefecture. Three plots (2 deciduous stands and 1 Japanese cedar (Cryptomeria japonica) plantation) were set in the forest. Quercus serrata and C. japonica, a representative of deciduous and evergreen tree species in this region, were chosen from each plot. Sample trees were logged in October 2012. Stem samples were collected every 2 m from above the ground to tree top and separated into bark, sapwood and heartwood. Litter traps were set in each plot and collected every month. Leaf litter was classified among species. Also, soil samples were collected in the cylinder of 5 cm in diameter and maximum 30 cm in depth from the forest floor every month. {sup 137}Cs concentration of all samples were measured by germanium semiconductor detector or NaI(Tl) scintillation counter. Deposited {sup 137}Cs was attached strongly on the bark of Q. serrata at high concentration (9-18 kBq/kg) but there were no clear relationship with tree height. In C. japonica, {sup 137}Cs concentration was about half times lower than that of Q. serrata at 0-10 m part of the tree. {sup 137}Cs concentration in wood of C. japonica was higher than Q. serrata. {sup 137}Cs concentration of sapwood was as high as that of heartwood in C. japonica, but in Q. serrata, {sup 137}Cs concentration in sapwood was

  14. Web technology in the separation of strontium and cesium from INEL-ICPP radioactive acid waste (WM-185)

    International Nuclear Information System (INIS)

    Bray, L.A.; Brown, G.N.

    1995-01-01

    Strontium and cesium were successfully removed from radioactive acidic waste (WM-185) at the Idaho National Engineering Laboratory, Idaho Chemical Processing Plant (ICPP), with web technology from 3M and IBC Advanced Technologies, Inc. (IBC). A technical team from Pacific Northwest Laboratory, ICPP, 3M and IBC conducted a very successful series of experiments from August 15 through 18, 1994. The ICPP, Remote Analytical Laboratory, Idaho Falls, Idaho, provided the hot cell facilities and staff to complete these milestone experiments. The actual waste experiments duplicated the initial 'cold' simulated waste results and confirmed the selective removal provided by ligand-particle web technology

  15. Annual report 1984. Radioactive isotope department

    International Nuclear Information System (INIS)

    Muenze, R.

    1985-11-01

    New technologies for production and application of radionuclides and synthesis of radioactive compounds are reported. Special importance is attributed to the characterization of radioactive compounds and the quality check of /sup 99m/Tc- and 14 C-labelled complexes within animal tests. An extensive list of publications and lectures illustrates the international cooperation of research in the field of radiochemistry

  16. Novel Approach for the Remediation of Radioactive Cesium Contaminated Soil with nano-Fe/Ca/CaO Dispersion Mixture in Dry Condition

    Directory of Open Access Journals (Sweden)

    Mallampati S. R.

    2013-04-01

    Full Text Available Present study, first time we developed a nano-Fe/Ca/CaO dispersion mixture based remediation and volume reduction method of real radioactive cesium contaminated soils. After soil samples treated with 10wt% of nano-Fe/Ca/CaO dispersion mixtures, emitting radiation intensity was reduced from 4.00 μSv/h to 0.95 μSv/h in non-magnetic fraction soils. While, after treatment, about 30wt% magnetic and 70wt% nonmagnetic fraction soils were separated, and it’s condensed radioactive cesium concentration was about 80% and 20%, respectively. By this way, cesium contaminated soil volume can be reduced. These preliminary results appear to be very promising and the simple mixing with the addition of nano-Fe/Ca/CaO may be considered potentially applicable for the remediation and separation of radioactive Cs contaminated soil in dry conditions.

  17. Bioaccumulation factors and the steady state assumption for cesium isotopes in aquatic foodwebs near nuclear facilities.

    Science.gov (United States)

    Rowan, D J

    2013-07-01

    Steady state approaches, such as transfer coefficients or bioaccumulation factors, are commonly used to model the bioaccumulation of (137)Cs in aquatic foodwebs from routine operations and releases from nuclear generating stations and other nuclear facilities. Routine releases from nuclear generating stations and facilities, however, often consist of pulses as liquid waste is stored, analyzed to ensure regulatory compliance and then released. The effect of repeated pulse releases on the steady state assumption inherent in the bioaccumulation factor approach has not been evaluated. In this study, I examine the steady state assumption for aquatic biota by analyzing data for two cesium isotopes in the same biota, one isotope in steady state (stable (133)Cs) from geologic sources and the other released in pulses ((137)Cs) from reactor operations. I also compare (137)Cs bioaccumulation factors for similar upstream populations from the same system exposed solely to weapon test (137)Cs, and assumed to be in steady state. The steady state assumption appears to be valid for small organisms at lower trophic levels (zooplankton, rainbow smelt and 0+ yellow perch) but not for older and larger fish at higher trophic levels (walleye). Attempts to account for previous exposure and retention through a biokinetics approach had a similar effect on steady state, upstream and non-steady state, downstream populations of walleye, but were ineffective in explaining the more or less constant deviation between fish with steady state exposures and non-steady state exposures of about 2-fold for all age classes of walleye. These results suggest that for large, piscivorous fish, repeated exposure to short duration, pulse releases leads to much higher (137)Cs BAFs than expected from (133)Cs BAFs for the same fish or (137)Cs BAFs for similar populations in the same system not impacted by reactor releases. These results suggest that the steady state approach should be used with caution in any

  18. Isotopic signature and nano-texture of cesium-rich micro-particles: Release of uranium and fission products from the Fukushima Daiichi Nuclear Power Plant.

    Science.gov (United States)

    Imoto, Junpei; Ochiai, Asumi; Furuki, Genki; Suetake, Mizuki; Ikehara, Ryohei; Horie, Kenji; Takehara, Mami; Yamasaki, Shinya; Nanba, Kenji; Ohnuki, Toshihiko; Law, Gareth T W; Grambow, Bernd; Ewing, Rodney C; Utsunomiya, Satoshi

    2017-07-14

    Highly radioactive cesium-rich microparticles (CsMPs) released from the Fukushima Daiichi Nuclear Power Plant (FDNPP) provide nano-scale chemical fingerprints of the 2011 tragedy. U, Cs, Ba, Rb, K, and Ca isotopic ratios were determined on three CsMPs (3.79-780 Bq) collected within ~10 km from the FDNPP to determine the CsMPs' origin and mechanism of formation. Apart from crystalline Fe-pollucite, CsFeSi 2 O 6  · nH 2 O, CsMPs are comprised mainly of Zn-Fe-oxide nanoparticles in a SiO 2 glass matrix (up to ~30 wt% of Cs and ~1 wt% of U mainly associated with Zn-Fe-oxide). The 235 U/ 238 U values in two CsMPs: 0.030 (±0.005) and 0.029 (±0.003), are consistent with that of enriched nuclear fuel. The values are higher than the average burnup estimated by the ORIGEN code and lower than non-irradiated fuel, suggesting non-uniform volatilization of U from melted fuels with different levels of burnup, followed by sorption onto Zn-Fe-oxides. The nano-scale texture and isotopic analyses provide a partial record of the chemical reactions that occurred in the fuel during meltdown. Also, the CsMPs were an important medium of transport for the released radionuclides in a respirable form.

  19. Dynamics of radioactive lead isotopes in the global environmental atmosphere

    International Nuclear Information System (INIS)

    Koike, Yuya; Kosako, Toshiso

    2006-01-01

    Fundamental information of radioactive lead isotopes, which used as the atmospheric tracer in the global environmental atmosphere, is reviewed. Emanation and exhalation of Rn and Tn, parent nuclide, is stated. Some reports on measurement and application of short-lived lead isotopes are reported. Transfer of radioactive lead isotopes in the atmosphere, vertical profiles of radon, thoron, and short-lived lead isotopes for different turbulent mixing conditions, deposition to aerosol, basic processes of Rn decay product behavior in air defining 'unattached' and 'aerosol-attached' activities, seasonal variation of atmospheric 210 Pb concentration at Beijing and Chengdu, seasonal variation of atmospheric 212 Pb concentration at several observation sites in Japan Islands, and variation in the atmospheric concentration of 212 Pb along with SO 2 are shown. (S.Y.)

  20. Laser spectroscopy of radioactive barium and strontium isotopes

    International Nuclear Information System (INIS)

    Martin, A.G.

    1986-01-01

    An atomic beam system and a high resolution computer controlled dye laser system were developed to perform isotope shift measurements on accelerator-produced radioactive isotopes. Two different techniques were used to transport the radioactive isotopes to the laser interaction region. The first technique was based on the thermalization and deionization of the nuclear reaction products in a helium buffer gas. The reaction products were subsequently transported in the gas to the laser beam along a capillary tube. This technique suffered from problems with chemical reactions between impurities in the buffer gas and the reaction products and proved to be unsuccessful. The second technique was based on the implantation of the reaction products into a metal lattice. Subsequent heating of the metal lattice released the implanted ions from which an atomic beam was formed. The photon burst technique was used to enable detection of the extremely weak atomic beams formed in this manner. Measurements were performed of the known isotope shifts of radioactive 128 Ba and 126 Ba to test the sensitivity of the system. The previously unmeasured isotope shift of radioactive 82 Sr also was determined, and the result obtained was compared to predictions using the droplet model

  1. Analysis of high burnup pressurized water reactor fuel using uranium, plutonium, neodymium, and cesium isotope correlations with burnup

    International Nuclear Information System (INIS)

    Kim, Jung Suk; Jeon, Young Shin; Park, Soon Dal; Ha, Yeong Keong; Song, Kyu Seok

    2015-01-01

    The correlation of the isotopic composition of uranium, plutonium, neodymium, and cesium with the burnup for high burnup pressurized water reactor fuels irradiated in nuclear power reactors has been experimentally investigated. The total burnup was determined by Nd-148 and the fractional 235 U burnup was determined by U and Pu mass spectrometric methods. The isotopic compositions of U, Pu, Nd, and Cs after their separation from the irradiated fuel samples were measured using thermal ionization mass spectrometry. The contents of these elements in the irradiated fuel were determined through an isotope dilution mass spectrometric method using 233 U, 242 Pu, 150 Nd, and 133 Cs as spikes. The activity ratios of Cs isotopes in the fuel samples were determined using gamma-ray spectrometry. The content of each element and its isotopic compositions in the irradiated fuel were expressed by their correlation with the total and fractional burnup, burnup parameters, and the isotopic compositions of different elements. The results obtained from the experimental methods were compared with those calculated using the ORIGEN-S code

  2. Decontamination of Radioactive Cesium Released from Fukushima Daiichi Nuclear Power Plant - 13277

    Energy Technology Data Exchange (ETDEWEB)

    Parajuli, Durga; Minami, Kimitaka; Tanaka, Hisashi; Kawamoto, Tohru [Nanosystem Research Institute, National Institute of Advanced Industrial Science and Technology - AIST (Japan)

    2013-07-01

    Peculiar binding of Cesium to the soil clay minerals remained the major obstacle for the immediate Cs-decontamination of soil and materials containing clay minerals like sludge. Experiments for the removal of Cesium from soil and ash samples from different materials were performed in the lab scale. For soil and sludge ash formed by the incineration of municipal sewage sludge, acid treatment at high temperature is effective while washing with water removed Cesium from ashes of plants or burnable garbage. Though total removal seems a difficult task, water-washing of wood-ash or garbage-ash at 40 deg. C removes >90% radiocesium, while >60% activity can be removed from soil and sludge-ash by acid washing at 95 deg. C. (authors)

  3. Evaluation of ambient dose equivalent rates influenced by vertical and horizontal distribution of radioactive cesium in soil in Fukushima Prefecture.

    Science.gov (United States)

    Malins, Alex; Kurikami, Hiroshi; Nakama, Shigeo; Saito, Tatsuo; Okumura, Masahiko; Machida, Masahiko; Kitamura, Akihiro

    2016-01-01

    The air dose rate in an environment contaminated with (134)Cs and (137)Cs depends on the amount, depth profile and horizontal distribution of these contaminants within the ground. This paper introduces and verifies a tool that models these variables and calculates ambient dose equivalent rates at 1 m above the ground. Good correlation is found between predicted dose rates and dose rates measured with survey meters in Fukushima Prefecture in areas contaminated with radiocesium from the Fukushima Dai-ichi Nuclear Power Plant accident. This finding is insensitive to the choice for modeling the activity depth distribution in the ground using activity measurements of collected soil layers, or by using exponential and hyperbolic secant fits to the measurement data. Better predictions are obtained by modeling the horizontal distribution of radioactive cesium across an area if multiple soil samples are available, as opposed to assuming a spatially homogeneous contamination distribution. Reductions seen in air dose rates above flat, undisturbed fields in Fukushima Prefecture are consistent with decrement by radioactive decay and downward migration of cesium into soil. Analysis of remediation strategies for farmland soils confirmed that topsoil removal and interchanging a topsoil layer with a subsoil layer result in similar reductions in the air dose rate. These two strategies are more effective than reverse tillage to invert and mix the topsoil. Copyright © 2015 Elsevier Ltd. All rights reserved.

  4. Radioactive isotopes in clinical medicine and research. Abstracts

    International Nuclear Information System (INIS)

    2007-01-01

    The review on the International Symposium on radioactive isotopes in clinical medicine and research in Bad Hofgastein, Austria, 9-12 January 2008, contains 42 papers and 29 poster contributions on the following topics: radiopharmaceutical sciences; radiopharmaceutical sciences in oncology and cardiology; therapy; endocrinology; molecular imaging; clinical PET; physics: image processing; instrumentation, neurology, psychiatry

  5. RIKEN radioactive isotope beam factory project – Present status and ...

    Indian Academy of Sciences (India)

    Programs for studying nuclear reactions and structure of exotic nuclei available at the RIKEN radioactive isotope beam factory project are introduced and discussed by demonstrating recent highlights. Special emphasis ... RIKEN Nishina Center for Accelerator-Based Science, 2-1 Hirosawa, Wako, Saitama 351-0198, Japan ...

  6. Radioactive isotopes in clinical medicine and research. Abstracts

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    The review on the International Symposium on radioactive isotopes in clinical medicine and research in Bad Hofgastein, Austria, 9-12 January 2008, contains 42 papers and 29 poster contributions on the following topics: radiopharmaceutical sciences; radiopharmaceutical sciences in oncology and cardiology; therapy; endocrinology; molecular imaging; clinical PET; physics: image processing; instrumentation, neurology, psychiatry.

  7. Diagnosis of portal hypertension with radioactive isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Lewitus, Z

    1974-01-01

    Administration of /sup 131/I in a microclysma and simultaneous recording of the radioactivity in the liver and precordium allows the diagnosis of portal hypertension in at least 90 percent of the cases. This test has been used now for more than 5 years in patients with liver diseases. The simplicity of the test makes it a valuable bedside procedure.

  8. PRAMANA Cluster radioactivity in xenon isotopes

    Indian Academy of Sciences (India)

    exotic decay or cluster radioactivity was first predicted by sandulescu et al [1] in. 1980 on the basis of ... separator by 58Ni(58Ni, 2n) reaction and carbon clusters were searched for by means of solid state nuclear ..... Lett. 55, 582 (1985). [22] D N Poenaru, W Greiner, K Depta, M Ivascu, D Mazilu and A Sandulescu, At. Data.

  9. Characterization of defects in semiconductors using radioactive isotopes

    CERN Document Server

    Deicher, Manfred

    2007-01-01

    Radioactive atoms have been used in solid-state physics and in material science for many decades. Besides their classical application as tracer for diffusion studies, nuclear techniques such as Mossbauer spectroscopy, perturbed angular correlation, and emission channeling have used nuclear properties to gain microscopical information on the structural and dynamical properties of solids. The availability of many different radioactive isotopes as a clean ion beam at facilities like ISOLDE/CERN has triggered a new era involving methods sensitive for the optical and electronic properties of solids, especially in the field of semiconductor physics. Spectroscopic techniques like photoluminescence (PL), deep-level transient spectroscopy (DLTS), and Hall effect gain a new quality by using radioactive isotopes. Due to their decay the chemical origin of an observed electronic and optical behavior of a specific defect or dopant can be unambiguously identified. This contribution will highlight a few examples to illustrat...

  10. Fractionation of cesium isotopes and 90Sr in snowmelt run-off and lake waters from a contaminated Norwegian mountain catchment

    International Nuclear Information System (INIS)

    Salbu, B.; Bjoernstad, H.E.; Brittain, J.E.

    1992-01-01

    Cesium isotopes and 90 Sr have been determined in the inflow and outflow rivers of a Norwegian subalpine lake. The lake is situated in an area contaminated by Chernobyl fallout. Sampling was carried out during the spring peak discharge period associated with snowmelt. Transported coarse particulate plant material was collected by traps. Particles and colloids were removed from water samples by hollow fibre ultrafiltration. The results illustrate that run-off during the spring snowmelt is an important pathway for these radionuclides. The cesium isotopes are predominantly transported as colloids, while 90 Sr is present in the form of low molecular weight mobile species. Based on lake budget calculations, more than 50% of the cesium input is retained in the lake, while more than 90% of the 90 Sr is transported through the lake and into lower parts of the drainage system. (author) 16 refs.; 6 figs.; 3 tabs

  11. Bench-scale treatability studies for simulated incinerator scrubber blowdown containing radioactive cesium and strontium

    International Nuclear Information System (INIS)

    Coroneos, A.C.; Taylor, P.A.; Arnold, W.D. Jr.; Bostick, D.A.; Perona, J.J.

    1994-12-01

    The purpose of this report is to document the results of bench-scale testing completed to remove 137 Cs and 90 Sr from the Oak Ridge K-25 Site Toxic Substances Control Act (TSCA) Incinerator blowdown at the K-25 Site Central Neutralization Facility, a wastewater treatment facility designed to remove heavy metals and uranium from various wastewaters. The report presents results of bench-scale testing using chabazite and clinoptilolite zeolites to remove cesium and strontium; using potassium cobalt ferrocyanide (KCCF) to remove cesium; and using strontium chloride coprecipitation, sodium phosphate coprecipitation, and calcium sulfate coprecipitation to remove strontium. Low-range, average-range, and high-range concentration blowdown surrogates were used to complete the bench-scale testing

  12. Cesium-134 assimilation and retention in the landsnail Helix aspersa Muller 1974. Its potential usefulness as bioindicator for radioactive contamination

    International Nuclear Information System (INIS)

    Alfonso, L.A.; Carvalho, F.P.

    1986-01-01

    Cesium-134 retention was experimentally studied on two groups (n=20 in each) of the land-snail Helix aspersa, labelled either through ingestion of labelled food or the radionuclide injection into the foot muscle. Cesium elimination was found to be not dependent from the labelling technique used. The mean biological half-life for Cs retention in both Helix groups was 53.6+- 0.8 d for the largest retention component, accounting for 0.88 of the initally absorbed Cs. Another experiment runned on a similar size Helix group allowed the gravimetric determination of food ingestion rate (8.8 mg/ g/day) and food assimilation efficiency (0.70+-0.20). Predictive modelling of Cs accumulation by Helix indicates a relatively high bioaccumulation potential in this species. This fact, together with the long biological half-life found for Cs retention, indicate that land snails could be used as suitable bioindicators for radioactive pollution in restrict terrestrial areas. (author)

  13. Selective cesium removal from radioactive liquid waste by crown ether immobilized new class conjugate adsorbent

    OpenAIRE

    Awual, M. R.; 矢板 毅; 田口 富嗣; 塩飽 秀啓; 鈴木 伸一; 岡本 芳浩

    2014-01-01

    Conjugate materials can provide chemical functionality, enabling an assembly of the ligand complexation ability to metal ions that are important for applications, such as separation and removal devices. In this study, we developed ligand immobilized conjugate adsorbent for selective cesium (Cs) removal from wastewater. The adsorbent was synthesized by direct immobilization of DB24C8 onto inorganic mesoporous silica. The obtained results revealed that adsorbent had higher selectivity towards C...

  14. Derivation of strontium-90 and cesium-137 residual radioactive material guidelines for the Laboratory for Energy-Related Health Research, University of California, Davis

    International Nuclear Information System (INIS)

    Nimmagadda, M.; Yu, C.

    1993-04-01

    Residual radioactive material guidelines for strontium-90 and cesium-137 were derived for the Laboratory for Energy-Related Health Research (LEHR) site in Davis, California. The guideline derivation was based on a dose limit of 100 mrem/yr. The US Department of Energy (DOE) residual radioactive material guideline computer code, RESRAD, was used in this evaluation; this code implements the methodology described in the DOE manual for implementing residual radioactive material guidelines. Three potential site utilization scenarios were considered with the assumption that, for a period of 1,000 years following remedial action, the site will be utilized without radiological restrictions. The defined scenarios vary with regard to use of the site, time spent at the site, and sources of food consumed. The results of the evaluation indicate that the basic dose limit of 100 mrem/yr will not be exceeded within 1,000 years for either strontium-90 or cesium-137, provided that the soil concentrations of these radionuclides at the LEHR site do not exceed the following levels: 71,000 pCi/g for strontium-90 and 91 pCi/g for cesium-137 for Scenario A (researcher: the expected scenario); 160,000 pCi/g for strontium-90 and 220 pCi/g for cesium-137 for Scenario B (recreationist: a plausible scenario); and 37 pCi/g for strontium-90 and 32 pCi/g for cesium-137 for Scenario C (resident farmer ingesting food produced in the contaminated area: a plausible scenario). The derived guidelines are single-radionuclide guidelines and are linearly proportional to the dose limit used in the calculations. In setting the actual strontium-90 and cesium-137 guidelines for the LEHR site, DOE will apply the as low as reasonably achievable (ALARA) policy to the decision-making process, along with other factors such as whether a particular scenario is reasonable and appropriate

  15. Radium-based estimates of cesium isotope transport and total direct ocean discharges from the Fukushima Nuclear Power Plant accident

    Energy Technology Data Exchange (ETDEWEB)

    Charette, M.A.; Breier, C.F.; Henderson, P.B.; Pike, S.M.; Buesseler, K.O. [Woods Hole Oceanographic Institution, Woods Hole, MA (United States). Dept. of Marine Chemistry and Geochemistry; Rypina, I.I.; Jayne, S.R. [Woods Hole Oceanographic Institution, Woods Hole, MA (United States). Dept. of Physical Oceanography

    2013-07-01

    Radium has four naturally occurring isotopes that have proven useful in constraining water mass source, age, and mixing rates in the coastal and open ocean. In this study, we used radium isotopes to determine the fate and flux of runoff-derived cesium from the Fukushima Dai-ichi Nuclear Power Plant (FNPP). During a June 2011 cruise, the highest cesium (Cs) concentrations were found along the eastern shelf of northern Japan, from Fukushima south, to the edge of the Kuroshio Current, and in an eddy ∝ 130 km from the FNPP site. Locations with the highest cesium also had some of the highest radium activities, suggesting much of the direct ocean discharges of Cs remained in the coastal zone 2-3 months after the accident. We used a short-lived Ra isotope ({sup 223}Ra, t{sub 1/2} = 11.4 d) to derive an average water mass age (T{sub r}) in the coastal zone of 32 days. To ground-truth the Ra age model, we conducted a direct, station-by-station comparison of water mass ages with a numerical oceanographic model and found them to be in excellent agreement (model avg. T{sub r} = 27 days). From these independent T{sub r} values and the inventory of Cs within the water column at the time of our cruise, we were able to calculate an offshore {sup 134}Cs flux of 3.9-4.6 x 10{sup 13} Bq d{sup -1}. Radium-228 (t{sub 1/2} = 5.75 yr) was used to derive a vertical eddy diffusivity (K{sub z}) of 0.7 m{sup 2} d{sup -1} (0.1 cm{sup 2} s{sup -1}); from this K{sub z} and {sup 134}Cs inventory, we estimated a {sup 134}Cs flux across the pycnocline of 1.8 x 10{sup 4} Bq d{sup -1} for the same time period. On average, our results show that horizontal mixing loss of Cs from the coastal zone was ∝ 10{sup 9} greater than vertical exchange below the surface mixed layer. Finally, a mixing/dilution model that utilized our Ra-based and oceanographic model water mass ages produced a direct ocean discharge of {sup 134}Cs from the FNPP of 11-16 PBq at the time of the peak release in early April 2011

  16. A numerical study on oceanic dispersion and sedimentation of radioactive cesium-137 from Fukushima Daiichi Nuclear Power Plant

    International Nuclear Information System (INIS)

    Higashi, Hironori; Morino, Yu; Ohara, Toshimasa

    2014-01-01

    We discussed a numerical model for oceanic dispersion and sedimentation of radioactive cesium-137 (Cs-137) in shallow water regions to clarify migration behavior of Cs-137 from Fukushima Daiichi Nuclear Power Plant. Our model considered oceanic transport by three dimensional ocean current, adsorption with large particulate matter (LPM), sedimentation and resuspension. The simulation well reproduced the spatial characteristics of sea surface concentration and sediment surface concentration of Cs-137 off Miyagi, Fukushima, and Ibaraki Prefectures during May-December 2011. The simulated results indicated that the adsorption-sedimentation of Cs-137 significantly occurred during strong wind events because the large amount of LPM was transported to upward layer by resuspension and vertical mixing. (author)

  17. Effect of decontamination of planting soil using zeolite slurry that inhibits transition of radioactive cesium from soil to plant bodies

    International Nuclear Information System (INIS)

    Ikeda, Yutaka; Akita, Hiroyuki; Kikawada, Kazuya

    2013-01-01

    The accident of Fukushima Daiichi nuclear energy plant by the tsunami resulting from the Great Eastern Japan Earthquake in 2011 caused the radiation contamination of cultivated field in Fukushima Prefecture. Some decontamination techniques such as surface soil grab, deep cultivation, and adding zeolite to the soil were tested in the rice fields of Fukushima Prefecture. Zeolite is usually used in the form of particle. It inhibits the transition of radioactive cesium from soil to plant bodies. Here, zeolite slurry was also used. The inhibition effect of the zeolite slurry was checked not only in the field but also in a laboratory experiment using some vegetables. The laboratory test results proved the effect of decontamination for vegetable; however, the field test showed uncertainness owing to the low passage coefficient of rice. (author)

  18. Extraction processes and solvents for recovery of cesium, strontium, rare earth elements, technetium and actinides from liquid radioactive waste

    Science.gov (United States)

    Zaitsev, Boris N.; Esimantovskiy, Vyacheslav M.; Lazarev, Leonard N.; Dzekun, Evgeniy G.; Romanovskiy, Valeriy N.; Todd, Terry A.; Brewer, Ken N.; Herbst, Ronald S.; Law, Jack D.

    2001-01-01

    Cesium and strontium are extracted from aqueous acidic radioactive waste containing rare earth elements, technetium and actinides, by contacting the waste with a composition of a complex organoboron compound and polyethylene glycol in an organofluorine diluent mixture. In a preferred embodiment the complex organoboron compound is chlorinated cobalt dicarbollide, the polyethylene glycol has the formula RC.sub.6 H.sub.4 (OCH.sub.2 CH.sub.2).sub.n OH, and the organofluorine diluent is a mixture of bis-tetrafluoropropyl ether of diethylene glycol with at least one of bis-tetrafluoropropyl ether of ethylene glycol and bis-tetrafluoropropyl formal. The rare earths, technetium and the actinides (especially uranium, plutonium and americium), are extracted from the aqueous phase using a phosphine oxide in a hydrocarbon diluent, and reextracted from the resulting organic phase into an aqueous phase by using a suitable strip reagent.

  19. A theoretical study of cluster radioactivity in platinum isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Joseph, Deepthy Maria; Ashok, Nithu; Joseph, Antony [University of Calicut, Department of Physics, Malappuram, Kerala (India)

    2018-01-15

    The probable cluster decay modes in platinum isotopes are predicted with the help of effective liquid drop model. The calculated half-lives are compared with those of universal decay law model and with the experimental data. The investigation affirms the decisive role of neutron magicity in the phenomenon of cluster radioactivity. It is found that the probability of cluster emission decreases with the increase in the neutron number of parent nucleus. Geiger-Nuttall plots of the probable decay modes show linear behaviour, which in turn leads to the equation for logarithmic half-life for the clusters emitted from Pt isotopes. (orig.)

  20. Dosage of cesium 137 in radioactive wastes by the application of sodium tetraphenylborate; Dosage du cesium 137 dans les effluents radioactifs par le tetraphenylborate de sodium

    Energy Technology Data Exchange (ETDEWEB)

    Testemale, G; Girault, J [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1967-07-01

    A simple technique of the dosage of {sup 137}Cs has been developed. The technique consists in the formation of cesium tetraphenyl borate, followed by a double extraction with isoamyl acetate, and washing of the organic phase. The counting of known parts of the cesium solution assaying of its purity by {gamma} spectrometry enable the determination of the {sup 137}Cs. The yield is about 98 per cent. (authors) [French] Une technique simple du dosage du {sup 137}Cs a ete mise au point. Elle consiste en une double extraction du tetraphenylborate de cesium forme par l'acetate d'isoamyle suivie d'un lavage de la phase organique. Des comptages sur des parties aliquotes de la solution de cesium et un controle de purete par spectrometrie {gamma} permettent la determination de cet element. Rendement: environ 98 pour cent. (auteurs)

  1. A new class of medicament: radioactivity isotopes (1962)

    International Nuclear Information System (INIS)

    Cohen, Y.

    1962-01-01

    Very many radioelement are used in medicine, either for diagnosis or as therapeutics. The development of medicine has entailed an increase in the number of application of radioactive isotopes. Firstly used in the form of simple inorganic molecules for diagnosis or as anticancer therapeutics, radioelements are now used for labelling organic molecules, allowing functional specific studies of any kind of nature. Their production is made difficult by their radio-active properties. Their pharmaceutical properties, determined by tests and controls, depend either from radiochemistry and from medicine. The author reminds, in this report, the methods for the preparation and analysis, and set out the medical application. (author) [fr

  2. Radioactive cesium deposition on rice, wheat, peach tree and soil after nuclear accident in Fukushima

    International Nuclear Information System (INIS)

    Nakanishi, T.M.; Kobayashi, N.I.; Tanoi, K.

    2013-01-01

    We present how radioactive Cs was deposited on wheat, rice, peach tree and soil after nuclear accident in Fukushima. The deposition of radioactive Cs was found as spots at the surface of the leaves, branch or trunk of the trees, as well as in soil using one of the imaging method, autoradiography. The deposited radioactive Cs was not easily washed out, even with the treatment of acid solution. When the wheat was harvested 2 months after the accident, high radioactivity of Cs was found only on the leaves developed and expanded at the time of the accident. In the case of the rice grain, most of the radioactivity was found in bran and the radioactivity was drastically reduced in milled rice. Most of the radioactive Cs accumulation in rice plants was estimated from the absorption of the Cs ion dissolved in water, rather than Cs adsorbed in soil. (author)

  3. Radioactive isotopes in clinical medicine and research. Abstracts

    International Nuclear Information System (INIS)

    2005-01-01

    The contribution displays 44 abstracts and 35 posters from the 27th International Symposium on ''radioactive isotopes in clinical medicine and research'', organized by the Austrian society of nuclear medicine and the department of nuclear medicine and the center for biomedical engineering and physics of the Vienna medical university. The abstracts are sorted according to lecture headers: radiopharmaceutical sciences, endocrinology, clinical PET, neurology, oncology, physics and instrumentation, cardiology, inflammation, therapy and varia. (uke)

  4. Chapter 2. Peculiarities of radioactive particle formation and isotope fractionation resulted from underground nuclear explosions

    International Nuclear Information System (INIS)

    1996-01-01

    Radioactive particles, forming terrain fallouts from underground nuclear explosion differ sufficiently from radioactive particles, produced by atmospheric nuclear explosions. Patterns of underground nuclear explosion development, release of radioactivity to the atmosphere, formation of a cloud and base surge, peculiarities of formed radioactive particles, data on isotope fractionation in radioactive particles are presented. Scheme of particle activation, resulted from underground explosions is given

  5. A major technological accident: the dispersion of a radioactive cesium - 137 pellet in Goiania, Brazil (1987)

    International Nuclear Information System (INIS)

    Guertzon, C.

    1994-01-01

    This study concerns the accidental dispersion of cesium 137 chloride via an abandoned radiotherapy device in Brazil, in september 1987. Since the accident occurred recently in a confined area and concerned a single radiochemical agent, it was possible to delimit the study parameters in each discipline: post-accident management, physics, medicine, environment, law, psychology, socio-economics and communication. Costs are difficult to evaluate but obviously very important. It is difficult to analyze all consequences. No official has been accused, there were no sentence. The results demonstrate the critical importance of the human factor in technological accidents. (A.L.B.)

  6. Radioactive isotopes and radiation in South Africa: a bibliographic review

    International Nuclear Information System (INIS)

    Basson, J.K.

    1985-12-01

    The development of isotope applications has been a main theme of the erstwhile Atomic Energy Board which organized a national conference in Pretoria in 1963 'to take stock of the work done in the country so far'. Radioactive isotopes and radiation have achieved widespread use in all fields of medicine, agriculture, science and technology. It was recommended that the AEC publish a review of relevant South African work. This publication therefore consists of listings of available publications by South African-based scientists since the 1963 Conference and is divided into the four categories: radiotherapy, clinical and laboratory medicine, agriculture, and industry, preceded by overviews. The terms of reference were construed not to include stable isotopes and it was accordingly decided to concentrate only on radioisotope applications

  7. Development of a water purifier for radioactive cesium removal from contaminated natural water by radiation-induced graft polymerization

    Science.gov (United States)

    Seko, Noriaki; Hoshina, Hiroyuki; Kasai, Noboru; Shibata, Takuya; Saiki, Seiichi; Ueki, Yuji

    2018-02-01

    Six years after the Fukushima-nuclear accident, the dissolved radioactive cesium (Cs) is now hardly detected in environmental natural waters. These natural waters are directly used as source of drinking and domestic waters in disaster-stricken areas in Fukushima. However, the possibility that some radioactive Cs adsorbed on soil or leaves will contaminate these natural waters during heavy rains or typhoon is always present. In order for the returning residents to live with peace of mind, it is important to demonstrate the safety of the domestic waters that they will use for their daily life. For this purpose, we have synthesized a material for selective removal of radioactive Cs by introducing ammonium 12-molybdophosphate (AMP) onto polyethylene nonwoven fabric through radiation-induced emulsion graft polymerization technique. Water purifiers filled with the grafted Cs adsorbent were installed in selected houses in Fukushima. The capability of the grafted adsorbent to remove Cs from domestic waters was evaluated for a whole year. The results showed that the tap water filtered through the developed water purifier contained no radioactive Cs, signifying the very effective adsorption performance of the developed grafted adsorbent. From several demonstrations, we have commercialized the water purifier named "KranCsair®". Furthermore, we have also developed a method for the mass production of the grafted nonwoven fabric. Using a 30 L grafting reactor, it was possible to produce the grafted nonwoven fabric with a suitable range of degree of grafting. When an irradiated roll of nonwoven trunk fabric with a length of 10 m and a width of 30 cm was set in the reactor filled with glycidyl methacrylate (GMA), AMP, Tween 80 monomer emulsion solution at 40 °C for 1 h, the difference of Dgs in the length and the width on roll of fabrics was negligible.

  8. Modelling the transport of radioactive cesium released from the Fukushima Dai-ichi NPP with sediments through the hydrologic system

    Science.gov (United States)

    Kinouchi, T.; Omata, T.; Wei, L.; Liu, T.; Araya, M.

    2013-12-01

    Due to the accident of the Fukushima Dai-ichi Nuclear Power Plant on March 2011, a huge amount of radionuclides including Cesium-134 and Cesium-137 was deposited over the main island of Japan and the Pacific Ocean, resulting in further transfer and diffusion of Cesium through the atmospheric flow, watershed hydrological processes, and terrestrial ecosystem. Particularly, for the transfer of Cesium-134 and Cesium-137, sediments eroded and transported by the rainfall-runoff processes play an important role as Cesium tends to be strongly adsorbed to soil particles such as clay and silt. In this study, we focus on the transport of sediment and adsorbed Cesium in the watershed-scale hydrologic system to predict the long-term change of distribution of Cesium and its discharge to rivers and ocean. We coupled a physically-based distributed hydrological model with the modules of erosion and transport of sediments and adsorbed Cesium, and applied the coupled model to the Abukuma River watershed, which is located over the area of higher deposition of Cesium. In the model, complex land use and land cover distributions, and the effect of human activities such as irrigation, dam control and urban drainage system are taken into accounts. Simulation was conducted for the period of March 2011 until August 2012, with initial spatial distribution of Cesium-134 and Cesium-137 obtained by the airborne survey. Simulated flow rates and sediment concentrations agreed well with observed, and found that since the accident, two major storms in July and September 2011 transported about 50% of total sediments transported during the simulated periods. Cesium concentration in the sediment was reproduced well except for the difference in the initial periods. This difference is attributable to the uncertainty arisen from the initial distribution of Cesium in the soil and the transfer of Cesium from the forest canopy.

  9. A kinematic-based methodology for radiological protection: Runoff analysis to calculate the effective dose for internal exposure caused by ingestion of radioactive isotopes

    Science.gov (United States)

    Sasaki, Syota; Yamada, Tadashi; Yamada, Tomohito J.

    2014-05-01

    We aim to propose a kinematic-based methodology similar with runoff analysis for readily understandable radiological protection. A merit of this methodology is to produce sufficiently accurate effective doses by basic analysis. The great earthquake attacked the north-east area in Japan on March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power plant was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive isotopes had leaked and been diffused in the vicinity of the plant. Radiological internal exposure caused by ingestion of food containing radioactive isotopes has become an issue of great interest to the public, and has caused excessive anxiety because of a deficiency of fundamental knowledge concerning radioactivity. Concentrations of radioactivity in the human body and internal exposure have been studied extensively. Previous radiologic studies, for example, studies by International Commission on Radiological Protection(ICRP), employ a large-scale computational simulation including actual mechanism of metabolism in the human body. While computational simulation is a standard method for calculating exposure doses among radiology specialists, these methods, although exact, are too difficult for non-specialists to grasp the whole image owing to the sophistication. In this study, the human body is treated as a vessel. The number of radioactive atoms in the human body can be described by an equation of continuity, which is the only governing equation. Half-life, the period of time required for the amount of a substance decreases by half, is only parameter to calculate the number of radioactive isotopes in the human body. Half-life depends only on the kinds of nuclides, there are no arbitrary parameters. It is known that the number of radioactive isotopes decrease exponentially by radioactive decay (physical outflow). It is also known that radioactive isotopes

  10. Determination of local-area distribution and relocation of radioactive cesium in trees from Fukushima Daiichi Nuclear Power Plant by autoradiography analysis

    International Nuclear Information System (INIS)

    Sakamoto, Fuminori; Ohnuki, Toshihiko; Kozai, Naofumi; Yamasaki, Shinya; Yoshida, Zenko; Nanba, Kenji

    2013-01-01

    The local area distribution and relocation of radioactive cesium deposited in trees after the 2011 tsunami-related accident at the Fukushima Daiichi Nuclear Power Plant (FDNPP) have been studied by measuring the spatial distribution of cesium on/in trees by autoradiography analysis. Samples of trees were collected from places located between 4 and 55 km from FDNPP approximately 2, 8, 20, and 22 months after the accident. The autoradiography analyses of Cryptomeria japonica, Torreya nucifera, and Thujopsis dolabrata var. hondae samples collected approximately 2 and 8 months after the accident showed that radioactive Cs was mainly distributed as spots on the branches and leaves of the trees emerged before the accident, and was detected in negligible amounts in new branch and leaves that emerged after the accident. On the contrary, radioactive Cs was detected at the outermost tip of the branches in the trees collected 20 months after the accident. Morus alba samples collected 22 months after the accident contained radioactive Cs inside and outside their stems, even though no radioactive Cs was detected in their roots, strongly suggesting that a certain amount of radioactive Cs was translocated from the outside to the inside of stems. These results indicate that the distribution of radioactive Cs deposited on/in the trees gradually changes with time (scale: year). (author)

  11. Efficient removal of cesium from low-level radioactive liquid waste using natural and impregnated zeolite minerals.

    Science.gov (United States)

    Borai, E H; Harjula, R; Malinen, Leena; Paajanen, Airi

    2009-12-15

    The objective of the proposed work was focused to provide promising solid-phase materials that combine relatively inexpensive and high removal capacity of some radionuclides from low-level radioactive liquid waste (LLRLW). Four various zeolite minerals including natural clinoptilolite (NaNCl), natural chabazite (NaNCh), natural mordenite (NaNM) and synthetic mordenite (NaSM) were investigated. The effective key parameters on the sorption behavior of cesium (Cs-134) were investigated using batch equilibrium technique with respect to the waste solution pH, contacting time, potassium ion concentration, waste solution volume/sorbent weight ratio and Cs ion concentration. The obtained results revealed that natural chabazite (NaNCh) has the higher distribution coefficients and capacity towards Cs ion rather than the other investigated zeolite materials. Furthermore, novel impregnated zeolite material (ISM) was prepared by loading Calix [4] arene bis(-2,3 naphtho-crown-6) onto synthetic mordenite to combine the high removal uptake of the mordenite with the high selectivity of Calix [4] arene towards Cs radionuclide. Comparing the obtained results for both NaSM and the impregnated synthetic mordenite (ISM-25), it could be observed that the impregnation process leads to high improvement in the distribution coefficients of Cs+ ion (from 0.52 to 27.63 L/g). The final objective in all cases was aimed at determining feasible and economically reliable solution to the management of LLRLW specifically for the problems related to the low decontamination factor and the effective recovery of monovalent cesium ion.

  12. Efficient removal of cesium from low-level radioactive liquid waste using natural and impregnated zeolite minerals

    International Nuclear Information System (INIS)

    Borai, E.H.; Harjula, R.; Malinen, Leena; Paajanen, Airi

    2009-01-01

    The objective of the proposed work was focused to provide promising solid-phase materials that combine relatively inexpensive and high removal capacity of some radionuclides from low-level radioactive liquid waste (LLRLW). Four various zeolite minerals including natural clinoptilolite (NaNCl), natural chabazite (NaNCh), natural mordenite (NaNM) and synthetic mordenite (NaSM) were investigated. The effective key parameters on the sorption behavior of cesium (Cs-134) were investigated using batch equilibrium technique with respect to the waste solution pH, contacting time, potassium ion concentration, waste solution volume/sorbent weight ratio and Cs ion concentration. The obtained results revealed that natural chabazite (NaNCh) has the higher distribution coefficients and capacity towards Cs ion rather than the other investigated zeolite materials. Furthermore, novel impregnated zeolite material (ISM) was prepared by loading Calix [4] arene bis(-2,3 naphtho-crown-6) onto synthetic mordenite to combine the high removal uptake of the mordenite with the high selectivity of Calix [4] arene towards Cs radionuclide. Comparing the obtained results for both NaSM and the impregnated synthetic mordenite (ISM-25), it could be observed that the impregnation process leads to high improvement in the distribution coefficients of Cs + ion (from 0.52 to 27.63 L/g). The final objective in all cases was aimed at determining feasible and economically reliable solution to the management of LLRLW specifically for the problems related to the low decontamination factor and the effective recovery of monovalent cesium ion.

  13. Chemistry of radioactive cesium in the hydrosphere and in the geosphere

    International Nuclear Information System (INIS)

    Lieser, K.H.; Steinkopff, T.

    1989-01-01

    Cesium is sorbed with relatively high selectivity by clay minerals. Accordingly, in groundwaters Cs is found in high amounts in suspended matter or in colloids, if these consist of or contain clay minerals. The sorption of Cs in sediments is also mainly determined by the presence of clay minerals and the sorption ratio at low salinity is found to be roughly proportional to the clay content in the sediments. Furthermore, with the same sediment the sorption ratio is inversily proportional to the concentration of NaCl which proves that ion exchange on the clay minerals is the prevailing sorption mechanism for Cs. It shown that the sediments contain small amounts of sorption sites of high selectivity for Cs + which govern the sorptions behaviour at very small concentrations of Cs + ions. These sorption sites are also responsible for Cs + sorption on suspended particulates of clay in the groundwaters. (orig.)

  14. Cesium removal and kinetics equilibrium: Precipitation kinetics

    International Nuclear Information System (INIS)

    Barnes, M.J.

    1999-01-01

    This task consisted of both non-radioactive and radioactive (tracer) tests examining the influence of potentially significant variables on cesium tetraphenylborate precipitation kinetics. The work investigated the time required to reach cesium decontamination and the conditions that affect the cesium precipitation kinetics

  15. Cesium-137 as a radiation source

    International Nuclear Information System (INIS)

    McMullen, W.H.; Sloan, D.P.

    1985-01-01

    The U.S. Department of Energy (DOE) Byproducts Utilization Program (BUP) seeks to develop and encourage widespread commercial use of defense byproducts that are produced by DOE. Cesium-l37 is one such byproduct that is radioactive and decays with emission of gamma rays. The beneficial use of this radiation to disinfect sewage sludge or disinfest food commodities is actively being pursued by the program. The radiation produced by cesium-l37(Cs-l37) is identical in form to that produced by cobalt-60(Co-60), an isotope that is widely used in commercial applications such as medical product sterilization. The choice of isotope to use depends on several factors ranging from inherent properties of the isotopes to availability and cost. The BUP, although centrally concerned with the beneficial use of Cs-l37, by investigating and assessing the feasibility of various uses hopes to define appropriate circumstances where cesium or cobalt might best be used to accomplish specific objectives. This paper discusses some of the factors that should be considered when evaluating potential uses for isotopic sources

  16. Study of Cesium and Strontium sorption in Brazilian clays for their use as a barrier in repositories of radioactive wastes

    International Nuclear Information System (INIS)

    Freire, Carolina Braccini

    2007-01-01

    Wastes in general should be properly treated and stored. Then the radioactive wastes also require suitable and safe management beginning in their generation until the storage in repository. The main purpose of the radioactive waste management is to preserve the human beings and the environment. The objective of this research was to characterize some Brazilian clays in order to evaluate the viability of their use in the backfill layer, one of the radioactive waste repository barriers. The main function of this barrier is to contribute in the delay of the radionuclides movement, and to prevent their release into the environment. Four clays provided by national suppliers were selected for the research: Ca-Montmorillonite (Dol 01), Na-Montmorillonite (Dol 02), Kaolinite (Ind 01) and Vermiculite (Ubm 04). Their physical, chemical and mineralogical characteristics were determined, and also their sorption potential of Cesium and Strontium cations. It was confirmed through these results a direct relationship among their specific surface (SS), the capacity of cationic exchange (CCE) and pH. The CCE results followed this increasing order: Ind 01, Dol 01, and Dol 02. In accordance with the models of Freundlich (KJ) and Langmuir (M), the clays Dol 01 and Dol 02 were the best sorbers of Sr 2+ . The Ind 01 and Ubm 04 were the best ones in the case of Cs + . The Gibbs free energy change (ΔG deg) was calculated for the sorption reactions between the clays and the cations, and it was negative for all clays, confirming the sorption reaction spontaneity. (author)

  17. Preferential removal and immobilization of stable and radioactive cesium in contaminated fly ash with nanometallic Ca/CaO methanol suspension

    Energy Technology Data Exchange (ETDEWEB)

    Mallampati, Srinivasa Reddy, E-mail: srireddys@ulsan.ac.kr [Department of Civil and Environmental Engineering, University of Ulsan, Ulsan 680-749 (Korea, Republic of); Mitoma, Yoshiharu, E-mail: mitomay@pu-hiroshima.ac.jp [Department of Environmental Sciences, Faculty of Life and Environmental Sciences, Prefectural University of Hiroshima, 562 Nanatsuka-Cho, Shobara City, Hiroshima 727-0023 (Japan); Okuda, Tetsuji [Environmental Research and Management Center, Hiroshima University, 1-5-3 Kagamiyama, Higashi-Hiroshima, Hiroshima 739-8513 (Japan); Sakita, Shogo [Department of Environmental Sciences, Faculty of Life and Environmental Sciences, Prefectural University of Hiroshima, 562 Nanatsuka-Cho, Shobara City, Hiroshima 727-0023 (Japan); Simion, Cristian [Politehnica University of Bucharest, Department of Organic Chemistry, Bucharest 060042 (Romania)

    2014-08-30

    Graphical abstract: Schematic representation of possible mechanisms determining the Cs extraction and immobilization in fly ash during water, methanol or n-MCaS extraction. - Highlights: • nMCaS suspension for cesium extraction and immobilization in fly ash was developed. • Enhanced cesium immobilization was done by nanometallic Ca/CaO methanol suspension. • By SEM analysis the amount of cesium detectable on soil particle surface decreases. • Leachable cesium concentrations reduced, lower than the standard regulatory limit. • nMCaS unique and a highly potential amendment for the remediation of Cs. - Abstract: In this work, the capability of nanometallic Ca/CaO methanol suspension in removing and/or immobilizing stable ({sup 133}Cs) and radioactive cesium species ({sup 134}Cs and {sup 137}Cs) in contaminated fly ash was investigated. After a first methanol and second water washing yielded only 45% of {sup 133}Cs removal. While, after a first methanol washing, the second solvent with nanometallic Ca/CaO methanol suspension yielded simultaneous enhanced removal and immobilization about 99% of {sup 133}Cs. SEM-EDS analysis revealed that the mass percent of detectable {sup 133}Cs on the fly ash surface recorded a 100% decrease. When real radioactive cesium contaminated fly ash (containing an initial 14,040 Bq kg{sup −1134}Cs and {sup 137}Cs cumulated concentration) obtained from burning wastes from Fukushima were reduced to 3583 Bq kg{sup −1} after treatment with nanometallic Ca/CaO methanol suspension. Elution test conducted on the treated fly ash gave 100 Bq L{sup −1} total {sup 134}Cs and {sup 137}Cs concentrations in eluted solution. Furthermore, both ash content and eluted solution concentrations of {sup 134}Cs and {sup 137}Cs were much lower than the Japanese Ministry of the Environment regulatory limit of 8000 Bq kg{sup −1} and 150 Bq L{sup −1} respectively. The results of this study suggest that the nanometallic Ca/CaO methanol suspension is

  18. Simulation of radioactive cesium transfer in the southern Fukushima coastal biota using a dynamic food chain transfer model

    International Nuclear Information System (INIS)

    Tateda, Yutaka; Tsumune, Daisuke; Tsubono, Takaki

    2013-01-01

    The Fukushima Dai-ichi Nuclear Power Plant (1F NPP) accident occurred on 11 March 2011. The accident introduced 137 Cs into the coastal waters which was subsequently transferred to the local coastal biota thereby elevating the concentration of this radionuclide in coastal organisms. In this study, the radioactive cesium levels in coastal biota from the southern Fukushima area were simulated using a dynamic biological compartment model. The simulation derived the possible maximum radioactive cesium levels in organisms, indicating that the maximum 137 Cs concentrations in invertebrates, benthic fish and predator fish occurred during late April, late May and late July, respectively in the studied area where the source was mainly the direct leakage of 137 Cs effluent from the 1F NPP. The delay of a 137 Cs increase in fish was explained by the gradual food chain transfer of 137 Cs introduced to the ecosystem from the initial contamination of the seawater. The model also provided the degree of radionuclide depuration in organisms, and it demonstrated the latest start of the decontamination phase in benthic fish. The ecological half-lives, derived both from model simulation and observation, were 1–4 months in invertebrates, and 2–9 months in plankton feeding fish and coastal predator fish from the studied area. In contrast, it was not possible to similarly calculate these parameters in benthic fish because of an unidentified additional radionuclide source which was deduced from the biological compartment model. To adequately reconstruct the in-situ depuration of radiocesium in benthic fish in the natural ecosystem, a contamination source associated with the bottom sediments is necessary. -- Highlights: • Cs-137 in the southern Fukushima coastal biota were simulated using a dynamic biological compartment model. • Simulation derived contamination phase of marine biota was completed until late April to July 2011. • The delay of Cs-137 concentration increase in fish

  19. The level of cesium radioactivity after the Chernobyl accident on the tea plantation in Turkey

    International Nuclear Information System (INIS)

    Elinc, F.; Antep, S.; Tuekenmez, I.; Celenk, I.; Demirel, H.

    1996-01-01

    The Eastern Black Sea coastal region in Turkey was contaminated with radionuclides after the Chernobyl accident.The radioactive Cs contamination was serious in the tea crop. The objective of this study was to find out the level of Cs contamination in the leaf of tea crop and the soil in years following the accident. The study was conducted on the sixty-two representative sampling units where leaf and soil samples were taken in 1987,1988 and 1989. The results obtained showed that although the levels of Cs radioactivity in the leaf of tea crop and in the soil were relatively high in June 1987, the level tended to decrease in September 1987 and the decrease was abrupt in 1988 and 1989, such that 2%, 63% and 94% of the leaf samples contained less than 600 Bq/kg Cs radioactivity in June of 1987,1988 and 1989, respectively. Although all the soil samples had Cs radioactivity June and September 1987 and in June 1988, 32% and 26% of the soils had no Cs radioactivity in September 1988 and 1989. The results showed that the amount of Cs radioactivity in the soil had positive correlation with the soil organic matter (P<0.01) in 1987 and 1988 but the correlation was not significant in 1989. The amount of Cs activity in the leaf samples had positive correlation (P<0.01) with the level of Cs activity in soil in 1987, the level of Cs radioactivity in the leaf of tea crop had inverse correlation (P<-0.05) with the exchangeable magnesium and calcium contents in the soil in 1987

  20. Proton Radioactivity Measurements at HRIBF: Ho, Lu, and Tm Isotopes

    International Nuclear Information System (INIS)

    Akovali, Y.; Batchelder, J.C.; Bingham, C.R.; Davinson, T.; Ginter, T.N.; Gross, C.J.; Grzywacz, R.; Hamilton, J.H.; Janas, Z.; Karny, M.; Kim, S.H.; MacDonald, B.D.; Mas, J.F.; McConnell, J.W.; Piechaczek, A.; Ressler, J.J.; Rykaczewski, K.; Slinger, R.C.; Szerypo, J.; Toth, K.S.; Weintraub, W.; Woods, P.J.; Yu, C.-H.; Zganjar, E.F.

    1998-01-01

    Two new isotopes, 145 Tm and 140 Ho and three isomers in previously known isotopes, 141m Ho, 150m Lu and 151m Lu have been discovered and studied via their decay by proton emission. These proton emitters were produced at the Holifield Radioactive Ion Beam Facility (HRIBF) by heavy-ion fusion-evaporation reactions, separated in A/Q with a recoil mass spectrometer (RMS), and detected in a double-sided silicon strip detector (DSSD). The decay energy and half-life was measured for each new emitter. An analysis in terms of a spherical shell model is applied to the Tm and Lu nuclei, but Ho is considerably deformed and requires a collective model interpretation

  1. Kinetics of isotopic exchanges by using radioactive indicators

    International Nuclear Information System (INIS)

    May, S.

    1958-12-01

    After having noticed that iodine 131 under the form of sodium iodide has always been used as radioactive indicator in the CEA atomic pile located in Chatillon, this research report recalls the counting technique and some historical aspects of the notion of isotopic exchange and qualitative works, and presents some generalities on isotopic exchanges (reactions and calculation of rate constants of order 1 and 2, calculation of activation energy, spectro-photometric studies, Walden inversion, alkaline hydrolysis, influence of solvent on exchange kinetics, influence of the nature of the mineral halide). The author then addresses exchanges in aliphatic series (exchange with sodium iodide and with molecular iodine), exchanges in olefin series, exchanges in alicyclic series, and exchanges in aromatic series

  2. Tomogram forming process and apparatus using radioactive isotopes

    International Nuclear Information System (INIS)

    Stoddart, H.F.

    1980-01-01

    This invention relates to nuclear medicine and particularly to a tomogram forming apparatus which permits, with great efficiency, the very sensitive quantitative determination and the accurate spatial localization of the radioactivity of a body section of a patient to whom a substance labelled with radioactive isotopes has been administered. This scanner is characterized in that it includes several highly focused collimators placed one after the other, according to an arrangement which surrounds a scanning field. Each collimator is mobile with respect to the adjacent one and a system enables the arrangement to be rotated about the scanning field from one scanning position to another. Another device enables the collimators to be moved so that, for each scanning position, the focus of each collimator uniformly samples at least half the scanning field [fr

  3. Isotopic dependence of photoneutron cross sections around Strontium (Z=38) and Cesium (Z=55) nuclei

    International Nuclear Information System (INIS)

    Nakamura, T.; Uno, Y.; Yamadera, A.; Kase, T.

    1992-01-01

    We measured the average cross sections of (γ,n) reactions for 84 Sr, 86 Sr, 88 Sr, 85 Rb, 87 Rb, 98 Ru and 104 Ru isotopes in giant resonance region (9 to 25 MeV) using Bremsstrahlung radiation of 60 MeV maximum energy. We investigated the isotopic dependence of the average (γ,n) cross sections in giant resonance region from our experimental data and those estimated from other experimental data for Ge, Se, Zr, Mo, Sn, Te, Ce, Nd and Sm isotopes. As a result, we found that the average cross section data become highest for nuclei of neutron magic number of N = 50 and 82 except for Mo nucleus

  4. Restoration of water environment contaminated by radioactive cesium released from Fukushima Daiichi NPP

    Energy Technology Data Exchange (ETDEWEB)

    Takeshita, K.; Takahashi, H. [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 157-8550 (Japan); Jinbo, Y. [CDM Cosulting Co.Ltd., 1-13-13 Tsukiji Chuo-ku Tokyo 104-0045 (Japan); Ishido, A. [Radwaste and Decommissioning Center, 1-7-6 Toranomon, Minato-ku, Tokyo 105-0001 (Japan)

    2013-07-01

    In the Fukushima Daiichi NPP Accident, large amounts of volatile radioactive nuclides, such as {sup 131}I, {sup 134}Cs and {sup 137}Cs, were released to the atmosphere and huge areas surrounding the nuclear site were contaminated by the radioactive fallout. In this study, a combined process with a hydrothermal process and a coagulation settling process was proposed for the separation of radioactive Cs from contaminated soil and sewage sludge. The coagulation settling operation uses Prussian Blue (Ferric ferrocyanide) and an inorganic coagulant. The recovery of Cs from sewage sludge sampled at Fukushima city (100.000 Bq/kg) and soil at a nearby village (55.000 Bq/kg), was tested. About 96% of Cs in the sewage sludge was removed successfully by combining simple hydrothermal decomposition and coagulation settling. However, Cs in the soil was not removed sufficiently by the combined process (Cs removal is only 56%). The hydrothermal decomposition with blasting was carried out. The Cs removal from the soil was increased to 85%. When these operations were repeated twice, the Cs recovery was over 90%. The combined process with hydrothermal blasting and coagulation settling is applicable to the removal of Cs from highly contaminated soil.

  5. A new route to the stable capture and final immobilization of radioactive cesium.

    Science.gov (United States)

    Yang, Jae Hwan; Han, Ahreum; Yoon, Joo Young; Park, Hwan-Seo; Cho, Yung-Zun

    2017-10-05

    Radioactive Cs released from damaged fuel materials in the event of nuclear accidents must be controlled to prevent the spreading of hazardous Cs into the environment. This study describes a simple and novel process to safely manage Cs gas by capturing it within ceramic filters and converting it into monolithic waste forms. The results of Cs trapping tests showed that CsAlSiO 4 was a reaction product of gas-solid reactions between Cs gas and our ceramic filters. Monolithic waste forms were readily prepared from the Cs-trapping filters by the addition of a glass frit followed by thermal treatment at 1000°C for 3h. Major findings revealed that the Cs-trapping filters could be added up to 50wt% to form durable monoliths. In 30-50wt% of waste fraction, CsAlSiO 4 was completely converted to pollucite (CsAlSi 2 O 6 ), which is a potential phase for radioactive Cs due to its excellent thermal and chemical stability. A static leaching test for 28 d confirmed the excellent chemical resistance of the pollucite structure, with a Cs leaching rate as low as 7.21×10 -5 gm -2 /d. This simple scheme of waste processing promises a new route for radioactive Cs immobilization by synthesizing pollucite-based monoliths. Copyright © 2017 Elsevier B.V. All rights reserved.

  6. Application of GelGreen™ in Cesium Chloride Density Gradients for DNA-Stable Isotope Probing Experiments.

    Directory of Open Access Journals (Sweden)

    Jingfeng Gao

    Full Text Available In this study, GelGreen™ was investigated as a replacement for SYBR® Safe to stain DNA in cesium chloride (CsCl density gradients for DNA-stable isotope probing (SIP experiments. Using environmental DNA, the usage of GelGreen™ was optimized for sensitivity compared to SYBR® Safe, its optimal concentration, detection limit for environmental DNA and its application in environmental DNA-SIP assay. Results showed that GelGreen™ was more sensitive than SYBR® Safe, while the optimal dosage (15X concentration needed was approximately one-third of SYBR® Safe, suggesting that its sensitivity was three times more superior than SYBR® Safe. At these optimal parameters, the detection limit of GelGreen™-stained environmental DNA was as low as 0.2 μg, but the usage of 0.5 μg environmental DNA was recommended to produce a more consistent DNA band. In addition, a modified needle extraction procedure was developed to withdraw DNA effectively by fractionating CsCl density gradients into four or five fractions. The successful application of GelGreen™ staining with 13C-labeled DNA from enriched activated sludge suggests that this stain was an excellent alternative of SYBR® Safe in CsCl density gradients for DNA-SIP assays.

  7. Decoding Environmental Processes Using Radioactive Isotopes for the Post-Radioactive Contamination Recovery Assessment

    Science.gov (United States)

    Yasumiishi, Misa; Nishimura, Taku; Osawa, Kazutoshi; Renschler, Chris

    2017-04-01

    The continual monitoring of environmental radioactive levels in Fukushima, Japan following the nuclear plant accident in March 2011 provides our society with valuable information in two ways. First, the collected data can be used as an indicator to assess the progress of decontamination efforts. Secondly, the collected data also can be used to understand the behavior of radioactive isotopes in the environment which leads to further understanding of the landform processes. These two aspects are inseparable for us to understand the effects of radioactive contamination in a dynamic environmental system. During the summer of 2016, 27 soil core samples were collected on a farmer's land (rice paddies and forest) in Fukushima, about 20 km northwest of the nuclear plant. Each core was divided into 2.0 - 3.0 cm slices for the Cs-134, Cs-137, and I-131 level measurement. The collected data is being analyzed from multiple perspectives: temporal, spatial, and geophysical. In the forest area, even on the same hillslope, multiple soil types and horizon depths were observed which indicates the challenges in assessing the subsurface radioactive isotope movements. It appears that although highly humic soils show higher or about the same level of radioactivity in the surface layers, as the depth increased, the radioactivity decreased more in those samples compared with more sandy soils. With regard to the direction a slope faces and the sampling altitudes, the correlation between those attributes and radioactivity levels is inconclusive at this moment. The altitude might have affected the fallout level on a single hillslope-basis. However, to determine the correlation, further sampling and the detailed analysis of vegetation and topography might be necessary. Where the surface soil was scraped and new soil was brought in, former rice paddy surface layers did show three-magnitude levels lower of radioactivity in the top layer when compared with forest soils. At the foot of forest

  8. Cement materials for cesium and iodine confinement

    International Nuclear Information System (INIS)

    Nicolas, G.; Lequeux, N.; Boch, P.; Prene, S.

    2001-01-01

    The following topics were dealt with: radioactive waste storage, cement materials reacting with radioactive cesium and iodine, chemical barrier formation against radioactive pollution, ceramization, long term stability, XRD, PIXE analysis

  9. Distribution of radioactive Cesium in trees and effect of decontamination of forest contaminated by the Fukushima nuclear accident

    International Nuclear Information System (INIS)

    Iijima, K.; Funaki, H.; Tokizawa, T.; Nakayama, S.

    2013-01-01

    In decontamination pilot projects conducted by Japan Atomic Energy Agency (JAEA), many different techniques were tested to determine their applicability to remediate areas evacuated after the Fukushima Daiichi nuclear accident following the Great Tohoku earthquake and tsunami of March 11, 2011. In addition to buildings, roads and farmland, the forest adjacent to living areas was one of the main decontamination targets. The projects evaluated the radioactive contamination of trees and the effectiveness of decontaminating a highly contaminated evergreen forest. This forest was located 1.3 km southwest of the Fukushima Daiichi Nuclear Power Plant and is dominated by Japanese cedar trees and fir trees. As the first step, three Japanese cedar trees and three fir trees were cut down and the distributions of radioactive cesium (Cs) were measured in each. The total concentrations of 134 Cs and 137 Cs in the leaves and branches were about 1 MBq/kg for both cedar and fir trees, and were appreciably higher than in the bark for cedar. The concentrations in the outer part of the trunks (under the bark) were lower, on the order of 10 kBq/kg, and those in the core of the trunks were lower than 1 kBq/kg for both kinds of trees. The observation that the Cs concentrations are higher in the outer part of trees, is compatible with the assumption that radio-Cs was mostly adsorbed on the surface of trees and partly penetrated into the trunks through the bark. Evolution of air dose rates in a 100 x 60 m pasture adjacent to the forest was monitored during decontamination of the forest and of the pasture itself. The dose rates in the pasture decreased drastically after stripping contaminated topsoil from the pasture and decreased slightly more after stripping contaminated topsoil of the forest floor and pruning the trees. Cutting down and removing 84 trees in the outermost area (10- m width) of the forest also slightly decreased these dose rates. After decontamination, the residual dose

  10. The Study of some nutritional and pharmacological aspects of human radioactive contamination by cesium and plutonium

    International Nuclear Information System (INIS)

    Bittel, R.

    1988-04-01

    Foodchains are significant vectors of internal human radioactive contamination. Way of life, especially feeding habits are at present strikingly evolving under the influence of a better knowledge of food requirements and availability, greater use of additives, new technologies, economical, social and psychological factors. As a consequence, Cs and Pu in the diet vary, in spite of their unchanged concentration in the environment. Between source term and effective dose rate, many factors arise that lead to dose factor variability which must be quantified. These considerations should lead to a new optimization of radiological food control [fr

  11. Uptake of cesium and cobalt radionuclides from simulated radioactive wastewater by Ludwigia stolonifera aquatic plant

    Energy Technology Data Exchange (ETDEWEB)

    Saleh, H.M., E-mail: hosamsaleh70@yahoo.com [Radioisotope Department, Nuclear Research Center, Atomic Energy Authority, Dokki 12311, Giza (Egypt); Bayoumi, T.A. [Radioisotope Department, Nuclear Research Center, Atomic Energy Authority, Dokki 12311, Giza (Egypt); Mahmoud, H.H. [Radioisotope Department, Nuclear Research Center, Atomic Energy Authority, Dokki 12311, Giza (Egypt); Central Laboratory for Elemental and Isotopic Analysis, Nuclear Research Center, Atomic Energy Authority (Egypt); Aglan, R.F. [Department of Analytical Chemistry, Hot Laboratories Center, Atomic Energy Authority, 13759 (Egypt)

    2017-04-15

    Highlights: • Radioactive contamination is a serious environmental problem. • Phytoremediation is a proper technique for soil and water decontamination. • Aquatic plant, Ludwigia stolonifera, for bioaccumulation of radionuclides. • Factors affecting uptake efficiency of {sup 137}Cs and {sup 60}Co radionuclides. - Abstract: The article reported herein was conducted as part of comprehensive study considered to evaluate the efficiency of Ludwigia stolonifera as a local aquatic plant located in the Egyptian environment for phytoremediation of hazardous toxic and radioactive elements dissolved in aqueous wastes dispersed from industrial and urban applications through the human activities. Ludwigia stolonifera was immersed in single and binary solution of {sup 60}Co and {sup 137}Cs. The specific uptake rate of plant was determined at various activity contents of radionuclides, multiplied masses of plant, lighting exposure and different pH values. Accumulation of {sup 60}Co and {sup 137}Cs in mixture was more than 95% and 65% respectively. pH was less effective than the other evaluated parameters.

  12. ''Crown molecules'' for separating cesium

    International Nuclear Information System (INIS)

    Dozol, J.F.; Lamare, V.

    2002-01-01

    After the minor actinides, the second category of radionuclides that must be isolated to optimize nuclear waste management concerns fission products, especially two cesium isotopes. If the cesium-135 isotope could be extracted, it could subsequently be transmuted or conditioned using a tailor-made process. Eliminating the 137 isotope from reprocessing and nuclear facility-dismantling waste would allow to dispose of most of this waste in near-surface facilities, and simply process the small remaining quantity containing long-lived elements. CEA research teams and their international partners have thought up crown molecules that could be used to pick out the cesium and meet these objectives. (authors)

  13. Preliminary Estimation of Radioactive Cesium Concentration due to Hypothetical Accident in East Sea

    Energy Technology Data Exchange (ETDEWEB)

    Min, Byung-Il; Kim, Sora; Park, Kihyun; Suh, Kyung-suk [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2015-10-15

    The sea has no large islands, bays or capes. Its water balance is mostly determined by the inflow (Korea Strait) and outflow (Tsugaru Strait and Soya Strait) through the straits connecting it to the neighboring seas and Pacific Ocean. All of the Korean nuclear power plants are located in the coastal area, 3 sites in the east coast and 1 site in the west coast. So the Korean nuclear power plants there may be possibility that such dangerous substances spread out of the East Sea. The East Sea is a fertile fishing ground for surrounding counties. The environmental radionuclides concentration estimation is important for fish and sea plants may be contaminated by those radioactive materials. In order to simplify the problem, the experiment has been considered the many simplifying assumptions. The bed sediments are uniform over all the model domain, using the monthly mean ocean current data set and ignored effect of the facilities for damage preventions.

  14. Radiography of light alloy castings using radioactive isotopes

    International Nuclear Information System (INIS)

    Lakshminarayana, A.R.; Ramamurthy, D.

    1977-01-01

    One of the most important causes for setback of nation's economy is loss of productive elements as a result of avoidable accidents. Particularly in a complicated field such as aircraft production, failure of a single part may cause the loss of men, money and materials which are all productive elements. To reduce such a loss, to increase productivity and to earn customer confidence, it is absolutely necessary to find out tools for quality assurance of defect prone castings. Radioactive isotopes can judiciously be employed inspite of its lower contrast, provided the radiographer understands : (1) the various types of defects characteristics of each alloy and (2) the limitations and possibilities of detecting such defects by this method. (author)

  15. Development of an ion-exchange process for removing cesium from high-level radioactive liquid wastes

    International Nuclear Information System (INIS)

    Baumgarten, P.K.; Wallace, R.M.; Whitehurst, D.A.; Steed, J.M.

    1979-11-01

    Methods to determine resin characteristics, i.e., cesium equilibria and diffusion rates, were developed. These parameters can now guide resin selection and aid in interpreting column performance. The K/sub D/ cesium ion concentration relation gives evidence of three different types of ion exchange sites. The countercurrent load/elution/regeneration cycle for the removal of cesium by ion exchange repeatedly reached the goal decontamination factor (DF) of 10,000 at throughputs up to 60 column volumes. Resin backwashing appears feasible, but further development of column geometry will be required. The proposed ammonium elutriant is satisfactory. Regeneration end-point can be controlled by electrical conductivity monitoring

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

    Directory of Open Access Journals (Sweden)

    Takeki Hamasaki

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

  17. Accumulation of strontium 90 and cesium 137 in some hydrobionts

    International Nuclear Information System (INIS)

    Boyadzhiev, A.; Keslev, D.; Kerteva, A.; Novakova, E.

    1974-01-01

    Factors responsible for the accumulation of strontium 90 and cesium 137 in some plant organisms, characteristic for fishes in Bulgarian fresh-water reservoirs and in Black Seawater, were examined. The investigated samples were taken during spring, summer and autumn-winter seasons 1967/1968. Each sample burnt to ashes at 450 0 C was examined for strontium 90 and cesium 137 content as well as stable isotopes of calcuim and potassium. Accumulation factors for strontium 90 and cesium 137 were significantly higher in freshwater hydrobionts than in seawater hydrobionts. This could be explained by variations in the concentration of stable isotopes of calcium and potassium from freshwater reservoirs and from seawater. Potassium and calcium concentrations were relatively constant in seawater while in freshwater they were significantly variable. Accumulation factors for these radionuclides increased according to the amount of rain and the altitude above sea level. Strontium 90 was deposited mostly in fins, less in scales and least in the meat of fishes; cesium 137 was mainly deposited in the meat and less in the other parts of fishes. The highest accumulation factors for strontium 90 were determined in fishes and for cesium 137 in plant organisms. The most convenient plant and fish species for tracing radioactive contamination of freshwater reservoirs and in the Black Sea were indicated. (A.B.)

  18. Preparation and use of polymeric materials containing hydrophobic anions and plasticizers for separation of cesium and strontium

    International Nuclear Information System (INIS)

    Abney, K.D.; Kinkead, S.A.; Mason, C.F.V.; Rais, J.

    1997-01-01

    Preparation and use is described for polymeric materials containing hydrophobic anions and plasticizers for extraction of cesium and strontium. The use of polymeric materials containing plasticizers which are solvents for hydrophobic anions such as derivatives of cobalt dicarbollide or tetraphenylborate which are capable of extracting cesium and strontium ions from aqueous solutions in contact with the polymeric materials, is described. The polymeric material may also include a synergistic agent for a given ion like polyethylene glycol or a crown ether, for removal of radioactive isotopes of cesium and strontium from solutions of diverse composition and, in particular, for solutions containing large excess of sodium nitrate

  19. Laser fluorescence on radioactive isotopes produced in very low yield

    International Nuclear Information System (INIS)

    Wells, S.A.; Evans, D.E.; Griffith, J.A.R.; Eastham, D.A.; Groves, J.; Tolfree, D.W.L.; Warner, D.D.; Dancy, M.P.; Billowes, J.; Grant, I.S.; Walker, P.M.

    1990-01-01

    Heavy ion accelerators such as the NSF at Daresbury Laboratory are capable of producing a wide variety of radio-active beams. The intensities of the beams of atoms or ions are always modest, and ultra-sensitive methods are needed to observe laser-induced fluorescence. The fast ion-photon coincidence technique has been applied to neutron-deficient barium ions down to 120 Ba. Nuclear moments and changes in charge radii have been determined from the measured hyperfine splittings and isotope shifts. An abrupt increase in the mean square radius is observed at 121 Ba, large enough to disrupt the systematic staggering seen for the isotopic series. The hyperfine structure has also been observed for an isomeric state of 127 Ba which has a lifetime of about 2 seconds. The measurements lead to an unambiguous assignment of the spin of the isomer. Another technique has been tested with stable krypton atoms. Fluorescent photons in the VUV wavelength region are detected with a high efficiency using a channel plate detector. The background is small enough that it should be possible to measure hyperfine spectra on beams with fewer than 10 3 atoms per second

  20. Radiological impact assessment of the domestic on-road transportation of radioactive isotope wastes

    Energy Technology Data Exchange (ETDEWEB)

    Seo, Myung Hwan; Hong, Sung Wook; Park, Jin Beak [Korea Radioactive Waste Agency, Technology Institute, Daejeon (Korea, Republic of)

    2016-09-15

    Korea Radioactive Waste Agency (KORAD) began to operate the low and intermediate level radioactive waste disposal facility in Gyeongju and to transport the radioactive waste containing radioactive isotopes from Daejeon to the disposal facility for the first time at 2015. For this radioactive waste transportation, in this study, radiological impact assessment is carried out for workers and public. The dose rate to workers and public during the transportation is estimated with consideration of the transportation scenarios and is compared with the Korean regulatory limit. The sensitivity analysis is carried out by considering both the variation of release ratios of the radioactive isotopes from the waste and the variation of the distances between the radioactive waste drum and worker during loading and unloading of radioactive waste. As for all the transportation scenarios, radiological impacts for workers and public have met the regulatory limits.

  1. Barium and xenon isotope yields in photopion reactions in cesium-133

    International Nuclear Information System (INIS)

    Sakamoto, K.; Hamajima, Y.; Soto, M.

    1989-09-01

    The radiochemical yield measurements are reported of barium isotopes from 133 Cs(γ, π - xn) 133-x Ba for x=0, 2, 4, 5, 6, 7 and 9 for bremsstrahlung maximum end-point energies (E 0 )=30∼1050 MeV and of 133 Xe from 133 Cs(γ, π + ) 133m,g Xe for E 0 =300∼1000 MeV. An emphasis was placed on Ba measurements around pion threshold and on runs for different target thickness to assess the interfering secondary particle-induced reactions. A clear evidence of the secondary reactions was found in a form of a shoulder of the yield curves in a range of E 0 π -, the Q value of 133 Cs(γ, π - xn) reaction, and used for the correction at E 0 π - with aids of the reported measurements of the photoprotons from 12 C and other complex nuclei and the cross sections of ( 133 Cs+p) reactions. The yields corrected for the secondaries, σ q (E 0 ), were unfolded into cross sections per photon of energy k, σ(k). The characteristic features of σ q (E 0 ) and/or σ(k) are then discussed in terms of E 0 - and k-dependence and product mass (A P =133-x), by comparing the present results with those currently obtained in our group. It was found that the present results of σ(k) are grossly reproduced by a cascade-evaporation calculation based on the PICA code by Gabriel and Alsmiller, only if the calculated ones are shifted in photon energy by k=30 MeV higher and the cutoff energy for neutron is chosen to be 1 MeV. (author)

  2. Optimization and validation of a chemical process for uranium, mercury and cesium leaching from cemented radioactive wastes

    International Nuclear Information System (INIS)

    Reynier, N.; Riveros, P.; Lastra, R.; Laviolette, C.; Bouzoubaa, N.; Chapman, M.

    2015-01-01

    Atomic Energy of Canada Limited (AECL) is developing a treatment and long-term management strategy for a legacy cemented radioactive waste that contains uranium, mercury and fission products. Extracting the uranium would be advantageous for decreasing the waste classification and reducing the cost of long-term management. Consequently, there are safety and economic and environmental incentives for the extraction of uranium, mercury and cesium before subjecting the cemented waste to a stabilization process. The mineralogical analysis of the surrogate cemented waste (SCW) indicated that uranium forms calcium uranate, CaUO 4 , occurring as layers of several millimeters or as grains of 20 μm. Hg is found mostly as large (∼50 μm) and small grains (5-8 μm) of HgO. The chemical leachability of three key elements (U, Hg, and Cs) from a SCW was studied with several leaching materials. The results showed that the most promising approach to leach and recover U, Hg, and Cs is the direct leaching of the SCW with H 2 SO 4 in strong saline media. Operating parameters such as particle size, temperature, pulp density, leaching time, acid and salt concentrations, number of leaching/rinsing step, etc. were optimized to improve key elements solubilization. Sulfuric leaching in saline media of a SCW (U5) containing 1182 ppm of U, 1598 ppm of Hg, and 7.9 ppm of Cs in the optimized conditions allows key elements recovery of 98.5 ± 0.4%, 96.6 ± 0.1%, and 93.8 ± 1.1% of U, Hg, and Cs respectively. This solubilization process was then applied in triplicate to seven other SCW prepared with different cement, liquid ratio and at different aging time and temperature. Concentrated sulfuric acid is added to the slurry until the pH is about 2, which causes the complete degradation of cement and the formation of CaSO 4 . At this pH, the acid consumption is moderate and the formation of amorphous silica gel is avoided. Sulfuric acid is particularly useful because it produces a leachate that

  3. Cooling of radioactive isotopes for Schottky mass spectrometry

    International Nuclear Information System (INIS)

    Steck, M.; Beckert, K.; Eickhoff, H.; Franzke, B.; Nolden, F.; Reich, H.; Schlitt, B.; Winkler, T.

    1999-01-01

    Nuclear masses of radioactive isotopes can be determined by measurement of their revolution frequency relative to the revolution frequency of reference ions with well-known masses. The resolution of neighboring frequency lines and the accuracy of the mass measurement is dependent on the achievable minimum longitudinal momentum spread of the ion beam. Electron cooling allows an increase of the phase space density by several orders of magnitude. For high intensity beams Coulomb scattering in the dense ion beam limits the beam quality. For low intensity beams a regime exists in which the diffusion due to intrabeam scattering is not dominating any more. The minimum momentum spread δp/p=5x10 -7 which is observed by Schottky noise analysis is considerably higher than the value expected from the longitudinal electron temperature. The measured frequency spread results from fluctuations of the magnetic field in the storage ring magnets. Systematic mass measurements have started and can be presently used for ions with half-lives of some ten seconds. For shorter-lived nuclei a stochastic precooling system is in preparation

  4. Radioactive 85Kr in krypton enriched with a light isotope

    International Nuclear Information System (INIS)

    Kuz'minov, V.V.; Novikov, V.M.; Pomanskii, A.A.; Pritychenko, B.V.; Vieiar, J.; Garcia, E.; Morales, A.; Morales, J.; Nunes-Lagos, R.; Piumendon, J.

    1993-01-01

    Radioactive krypton 85, a product of nuclear power generation, is known to be accumulating in the atmosphere continuously. Its volumetric activity in natural krypton is 700-800 Bq/liter. This can cause difficulties, e.g., in the fabrication of nuclear radiation detector for high-mass krypton. Krypton with a reduced 85 Kr content can be obtained by isotope separation. As part of an experiment to look for two-positron decay and conversion of an atomic electron to a positron in 78 Kr, Saenz measured the 85 Kr content in 78 Kr-enriched krypton. A mixture of two 85 Kr samples was used as the working substance of a cylindrical ionization chamber. The useful volume (1.33 liter) of the chamber contained 35.3 liters of gas at ∼2.5 kPa. The energy resolution of the detector at an energy of 0.511 MeV was 3.8%. The measurements were made in a passive lead shield 20 cm thick in an underground laboratory at a depth of 675 m water equivalent. Results are presented for counting rates in low-energy regions, contribution of krypton-85 to background, and the volumetric activity of krypton-85

  5. Yields and spectroscopy of radioactive isotopes at LOHENGRIN and ISOLDE

    CERN Document Server

    Köster, U

    1999-01-01

    Yields of radioactive nuclei were measured at two facilities: the recoil separator LOHENGRIN at the Institut Laue Langevin in Grenoble and the on-line isotope separator ISOLDE at CERN in Geneva. At LOHENGRIN the yields of light charged particles were measured from thermal neutron induced ternary fission of several actinide targets: 233U, 235U, 239Pu, 241Pu and 245Cm. Thin targets are brought into a high neutron flux. The produced nuclei leave these with the recoil obtained in the fission reaction. They are measured at different energies and ionic charge states. After corrections for the experimental acceptance, the time behaviour of the fission rate and the ionic charge fraction, the yields are integrated over the kinetic energy distribution. Comparing these yields with the predictions of various ternary fission models shows that the most abundant nuclides are well reproduced. On the other hand the models overestimate significantly the production of more "exotic" nuclides with an extreme N/Z ratio. Therefore ...

  6. Development of cementitious grouts for the incorporation of radioactive wastes. Part 2. Continuation of cesium and strontium leach studies. [Hydrofracture

    Energy Technology Data Exchange (ETDEWEB)

    Moore, J.G.

    1976-09-01

    Additional leach studies were completed on the leachability of cesium and strontium from simulated hydrofracture grout. These studies followed the test method proposed by IAEA or a modification which exposed smaller specimens with a higher surface-to-volume ratio to a larger volume of leachant. Results showed that the amount of cesium or strontium leached from the grout varied directly with the degree of drying during curing and inversely with the time of curing. The leachability also depends on the composition of the leachant and varies in the order: distilled water greater than tap water greater than grout water. The total waste concentration had little effect on the leachability of either cesium or strontium. The credibility of the laboratory results was substantiated by a short-term continuous leach test made on a fragment of a core sample of actual hydrofracture grout. The modified effective diffusivities (10/sup -11/ to 10/sup -10/ cm/sup 2//s) calculated from these limited data were comparable to those obtained from laboratory studies containing Grundite clay. These tests also confirmed the effect of various clays on the leachability of cesium and the importance of leachant renewal frequency on the leach rate.

  7. Decorporation of cesium-137

    International Nuclear Information System (INIS)

    Le Fleche, Ph.; Destombe, C.; Grasseau, A.; Mathieu, J.; Chancerelle, Y.; Mestries, J.C.

    1997-01-01

    Cesium radio-isotopes, especially cesium-137 ( 137 Cs) are among the radionuclides of main importance produced by a fission reaction in reactor or a nuclear weapon explosion. In the environment, 137 Cs is a major contaminant which can cause severe β, γirradiations and contaminations. 137 Cs is distributed widely and relatively uniformly throughout the body with the highest concentration in skeletal muscles. A treatment becomes difficult afterwards. The purposes of this report are Firstly to compare the Prussian blue verses cobalt and potassium ferrocyanide (D.I. blue) efficiency for the 137 Cs decorporation and secondly to assess a chronological treatment with D.I. blue. (author)

  8. Radioactive isotope and isomer separation with using light induced drift effect

    International Nuclear Information System (INIS)

    Hradecny, C.; Slovak, J.; Tethal, T.; Ermolaev, I.M.; Shalagin, A.M.

    1991-01-01

    The isotope separation with using light induced drift (LID) is discussed. The basic theoretical characteristics of the method are deduced: separation simultaneously with an arbitrary high enrichment and without significant losses; separation productivity up to 100 μg/h. These characteristics are sufficient and very convenient for separation of expensive radioactive isotopes and isomers which are applied in medicine and science. The first experimental separation of the radioactive isotopes ( 22,24 Na) by using the LID effect is reported. 13 refs.; 5 figs

  9. Reactor, radioactive isotopes and nuclear energy: their avatars in Venezuela

    Energy Technology Data Exchange (ETDEWEB)

    Roche, M

    1981-03-01

    The decision to bring a fair sized (3MW) research reactor to Venezuela, made in 1954 by a single, ambitious and prestige seeking individual working with a dictatorial government, is a clear case of cargo cult, an implicit desire to import industralized countries' science and technology by purchasing key in hand their expensive machine. The reactor has never ceased to experience difficulties since then, not so much of a physical or mechanical, but rather of a human nature and due to the almost grotesque distance between the machine's potentialities and the quantity and quality of personnel available. Demand and motivation have been scarce, because fossil and hydro energy have been so far plentiful. Military motivation was in theory absent. Perspectives have apparently improved, not that a scientific community has been trained and an infrastructure exists. Radioactive isotopes have been widely used in Venezuela, beginning in 1953, for medical practice and biological research. At present about 2.5 million bolivars worth of radioisotopes are imported annually, mostly from the US and to a lesser extent, from UK. Steps are being taken to train nuclear engineers, since most studies thus far indicate the last few years of the century as the time when nuclear energy will begin to enter the picture, and since a period of at least ten years is needed between the decision to build an atomic power plant and the time it goes into operation. Choice of technique has not been made, but an active, although still small, uranium prospecting program has been initiated. It seems as if, by the end of the century, either nuclear energy will have to supplement other sources, or standard of living of Venezuelans - at least that relative minority who can afford to live well - will drop. 2 figures, 2 tables.

  10. The containment and an absorbent evaluation for a package for a liquid radioactive isotope

    Energy Technology Data Exchange (ETDEWEB)

    Bang, K. S.; Lee, J. C.; Kim, D. H.; Hwang, C. S.; Kim, H. J.; Seo, K. S

    2005-03-01

    Radioactive isotopes must be safely transported from the production centre to the point of use. The shipping package to safely transport radioactive isotopes should be able to withstand the conditions prescribed by law. A type a package, which is used to transport liquid radioactive materials, should have a containment system comprising a primary inner and a secondary outer containment or it should be provided with a sufficiently absorbent material to absorb twice the volume of the liquid contents. Accordingly, an absorbent material for use in a Type A package to transport a liquid radioactive isotope was estimated. To estimate the integrity of containment, the leakage tests for a containment system for a Type A package for domestic and abroad expert were conducted.

  11. Feasibility study for the processing of Hanford Site cesium and strontium isotopic sources in the Hanford Waste Vitrification Plant

    International Nuclear Information System (INIS)

    Anantatmula, R.P.; Watrous, R.A.; Nelson, J.L.; Perez, J.M.; Peters, R.D.; Peterson, M.E.

    1991-09-01

    The final environmental impact statement for the disposal of defense-related wastes at the Hanford Site (Final Environmental Impact Statement: Disposal of Hanford Defense High-Level, Transuranic and Tank Wastes [HDW-EIS] [DOE 1987]) states that the preferred alternative for disposal of cesium and strontium wastes at the Hanford Site will be to package and ship these wastes to the commercial high-level waste repository. The Record of Decision for this EIS states that before shipment to a geologic repository, these wastes will be packaged in accordance with repository waste acceptance criteria. However, the high cost per canister for repository disposal and uncertainty about the acceptability of overpacked capsules by the repository suggest that additional alternative means of disposal be considered. Vitrification of the cesium and strontium salts in the Hanford Waste Vitrification Plant (HWVP) has been identified as a possible alternative to overpacking. Subsequently, Westinghouse Hanford Company's (Westinghouse Hanford) Projects Technical Support Office undertook a feasibility study to determine if any significant technical issues preclude the vitrification of the cesium and strontium salts. Based on the information presented in this report, it is considered technically feasible to blend the cesium chloride and strontium fluoride salts with neutralized current acid waste (NCAW) and/or complexant concentrate (CC) waste feedstreams, or to blend the salts with fresh frit and process the waste through the HWVP

  12. The cobalt radioactive isotopes in environment; Les isotopes radioactifs du cobalt dans l'environnement

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    For the year 1993 the total activity released in cobalt is 69 GBq for the whole of nuclear power plants. The part of activity in cobalt for La Hague in 1993 is 8 GBq of {sup 58}Co and 2 GBq of {sup 60}Co. The radioactive isotopes released by nuclear power plants or the reprocessing plant of La Hague under liquid effluents are shared by half between {sup 58}Co and {sup 60}Co. The exposure to sealed sources is the most important risk for the cobalt. The risk of acute exposure can associate a local irradiation of several decades of grays inducing a radiological burns, deep burn to treat in surgery by resection or graft even amputation. A global irradiation of organism for several grays induces an acute irradiation syndrome, often serious. At long term the stochastic effects are represented by leukemia and radio-induced cancers. The increase of probability of their occurrence is 1% by sievert. We must remind that the natural spontaneous probability is 25%. (N.C.)

  13. Long lived isotopes in the Chernobyl radioactive cloud at Cracow

    International Nuclear Information System (INIS)

    Mietelski, J.W.; Broda, R.; Sieniawski, J.

    1988-01-01

    The analysis of the residual gamma radioactivity in the air filters exposed during the passage of the Chernobyl radioactive cloud over Cracow area gave data on variation in time of the relative contribution of long lived radioisotopes. Conclusions on transport properties of some elements are deduced from the obtained results. 10 refs., 5 figs. (author)

  14. Application of radioactive isotopes in the field of investigations of the means of transportation wear

    International Nuclear Information System (INIS)

    Gromann, Kh-D.

    1979-01-01

    The Station for governing of isotope technique ensures application of radioactive isotopes in the transport of the GDR. The main directions of the isotope application are investigations of wear and leaks. It is reported about the wear investigations performed on models and real structural elements at laboratory testing stands as well as on the real structural elements in the exploitation conditions. Special attention should be paid to the numerous measurements of wear of engines, rails and so on. Data and valuable results have been obtained about the problem of the short-term wear measurement. Measurements of leaks by means of radioactive isotopes application is used for investigations of the hermeticy of the refrigerator tronsport means, heating systems and clymatizing installations of the carriges as well as stationary installations. Then, measurements have been done of leaks in pipelines as well as determinations of their lacalization and intensity. General and specific advantages of separate methods are discussed [ru

  15. Uses of Radioactive Isotopes in Industry; Aplicacion es de los isotopos radiactivos en la industria

    Energy Technology Data Exchange (ETDEWEB)

    Plata, A; Val Cob, M del; Gamboa, J M

    1962-07-01

    The present report contains a list of some of the most important problems in industry that have been approached so far by the use of radioactive isotopes. The list has been compiled trough the experience gained by the authors in revising for several years the most important scientific journal and other sources of information on this subject. The classification of industries has been done in an arbitrary way, choosing those isotope uses that have reached a higher degree of development. (Author)

  16. An absorbent for an application to a package for a liquid radioactive isotope for medical usage

    International Nuclear Information System (INIS)

    Bang, K.S.; Lim, S.P.; Lee, J.C.; Seo, K.S.; Han, H.S.

    2004-01-01

    A radioactive isotope has to be safely transport from the producing center to the consuming center. The shipping package to safely transport the radioactive isotope should be able to withstand the prescribed conditions by law. In the field of nuclear medicine, the radioactive isotope is used in a liquid or capsule form. A Type A package, which is to transport liquid radioactive materials, shall be provided with a containment system composed of primary inner and secondary outer containment components or shall be provided with sufficient absorbent material to absorb twice the volume of the liquid contents. Hospitals prefer to use not only convenient but also re-usable packages. To apply an absorbent material to the Type A package, that is to transport liquid radioactive isotope, the free absorbency of the absorbents was estimated. In the case of a liquid with NaOH 0.4%, the free absorbency of the melanine form was the most superior at 91 g/g. In the case of a liquid with Na 0.9%, the free absorbency of the melanine form was the most excellent at 88 g/g also

  17. Production of medical radioactive isotopes using KIPT electron driven subcritical facility

    International Nuclear Information System (INIS)

    Talamo, Alberto; Gohar, Yousry

    2008-01-01

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, γ), (n, 2n), (n, p), and (γ, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope

  18. Production of medical radioactive isotopes using KIPT electron driven subcritical facility

    Energy Technology Data Exchange (ETDEWEB)

    Talamo, Alberto [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)], E-mail: alby@anl.gov; Gohar, Yousry [Nuclear Engineering Division, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL 60439 (United States)

    2008-05-15

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, {gamma}), (n, 2n), (n, p), and ({gamma}, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope.

  19. Production of medical radioactive isotopes using KIPT electron driven subcritical facility.

    Science.gov (United States)

    Talamo, Alberto; Gohar, Yousry

    2008-05-01

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine in collaboration with Argonne National Laboratory (ANL) has a plan to construct an electron accelerator driven subcritical assembly. One of the facility objectives is the production of medical radioactive isotopes. This paper presents the ANL collaborative work performed for characterizing the facility performance for producing medical radioactive isotopes. First, a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Then, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes have been considered and all transmutation channels are used including (n, gamma), (n, 2n), (n, p), and (gamma, n). In the second part, the parent isotopes with high reaction rate were explicitly modeled in the calculations. Four irradiation locations were considered in the analyses to study the medical isotope production rate. The results show the self-shielding effect not only reduces the specific activity but it also changes the irradiation location that maximizes the specific activity. The axial and radial distributions of the parent capture rates have been examined to define the irradiation sample size of each parent isotope.

  20. Novel methods for estimating 3D distributions of radioactive isotopes in materials

    Energy Technology Data Exchange (ETDEWEB)

    Iwamoto, Y., E-mail: y.iwamoto0805@ruri.waseda.jp [Research Institute for Science and Engineering, Waseda University, Shinjuku, Tokyo 169-8555 (Japan); Kataoka, J.; Kishimoto, A.; Nishiyama, T.; Taya, T.; Okochi, H.; Ogata, H. [Research Institute for Science and Engineering, Waseda University, Shinjuku, Tokyo 169-8555 (Japan); Yamamoto, S. [Nagoya University Graduate School of Medicine, 1-1-20, Daikominami, Higashi-ku, Nagoya-shi, Aichi 461-8673 (Japan)

    2016-09-21

    In recent years, various gamma-ray visualization techniques, or gamma cameras, have been proposed. These techniques are extremely effective for identifying “hot spots” or regions where radioactive isotopes are accumulated. Examples of such would be nuclear-disaster-affected areas such as Fukushima or the vicinity of nuclear reactors. However, the images acquired with a gamma camera do not include distance information between radioactive isotopes and the camera, and hence are “degenerated” in the direction of the isotopes. Moreover, depth information in the images is lost when the isotopes are embedded in materials, such as water, sand, and concrete. Here, we propose two methods of obtaining depth information of radioactive isotopes embedded in materials by comparing (1) their spectra and (2) images of incident gamma rays scattered by the materials and direct gamma rays. In the first method, the spectra of radioactive isotopes and the ratios of scattered to direct gamma rays are obtained. We verify experimentally that the ratio increases with increasing depth, as predicted by simulations. Although the method using energy spectra has been studied for a long time, an advantage of our method is the use of low-energy (50–150 keV) photons as scattered gamma rays. In the second method, the spatial extent of images obtained for direct and scattered gamma rays is compared. By performing detailed Monte Carlo simulations using Geant4, we verify that the spatial extent of the position where gamma rays are scattered increases with increasing depth. To demonstrate this, we are developing various gamma cameras to compare low-energy (scattered) gamma-ray images with fully photo-absorbed gamma-ray images. We also demonstrate that the 3D reconstruction of isotopes/hotspots is possible with our proposed methods. These methods have potential applications in the medical fields, and in severe environments such as the nuclear-disaster-affected areas in Fukushima.

  1. Novel methods for estimating 3D distributions of radioactive isotopes in materials

    Science.gov (United States)

    Iwamoto, Y.; Kataoka, J.; Kishimoto, A.; Nishiyama, T.; Taya, T.; Okochi, H.; Ogata, H.; Yamamoto, S.

    2016-09-01

    In recent years, various gamma-ray visualization techniques, or gamma cameras, have been proposed. These techniques are extremely effective for identifying "hot spots" or regions where radioactive isotopes are accumulated. Examples of such would be nuclear-disaster-affected areas such as Fukushima or the vicinity of nuclear reactors. However, the images acquired with a gamma camera do not include distance information between radioactive isotopes and the camera, and hence are "degenerated" in the direction of the isotopes. Moreover, depth information in the images is lost when the isotopes are embedded in materials, such as water, sand, and concrete. Here, we propose two methods of obtaining depth information of radioactive isotopes embedded in materials by comparing (1) their spectra and (2) images of incident gamma rays scattered by the materials and direct gamma rays. In the first method, the spectra of radioactive isotopes and the ratios of scattered to direct gamma rays are obtained. We verify experimentally that the ratio increases with increasing depth, as predicted by simulations. Although the method using energy spectra has been studied for a long time, an advantage of our method is the use of low-energy (50-150 keV) photons as scattered gamma rays. In the second method, the spatial extent of images obtained for direct and scattered gamma rays is compared. By performing detailed Monte Carlo simulations using Geant4, we verify that the spatial extent of the position where gamma rays are scattered increases with increasing depth. To demonstrate this, we are developing various gamma cameras to compare low-energy (scattered) gamma-ray images with fully photo-absorbed gamma-ray images. We also demonstrate that the 3D reconstruction of isotopes/hotspots is possible with our proposed methods. These methods have potential applications in the medical fields, and in severe environments such as the nuclear-disaster-affected areas in Fukushima.

  2. Development of an improved ion-exchange process for removing cesium and strontium from high-level radioactive liquid wastes

    International Nuclear Information System (INIS)

    Wallace, R.M.; Ferguson, R.B.

    1980-11-01

    Processes are being developed to solidify and isolate the biologically hazardous radionuclides from approximately 23 million gallons of alkaline high-level waste accumulated at the Savannah River Plant. The waste consists mainly of a liquid supernate, a damp salt cake, and a gelatinous, insoluble sludge. The reference solidification process involves separation of the water soluble fraction (supernate) from the insoluble fraction, removal of cesium and traces of strontium from the supernate, incorporation of the sludge and the radionuclides from the supernate in glass, and incorporation of the residual salt in concrete. A new process, now being developed, involves sorbing cesium on phenolic resins that contain no strongly acidic sulfonate groups. These resins can then be eluted with formic acid which is not possible with Duolite ARC-359. Duolite CS-100, a phenol-carboxylate resin, was chosen for further development because of its greater breakthrough capacity and because it also sorbs strontium to some extent. Strontium sorption by CS-100 was not sufficient to eliminate the need for Amberlite IRC-718. However, the latter resin can also be eluted with formic acid because its functional groups are weakly acidic. Formic acid elution permits several options to be considered. The preferred option consists simply of mixing the eluate with sludge prior to calcination. Sodium formate, which is formed when the resins in the sodium form are eluted, decomposes rapidly between 450 0 C and 500 0 C and will be destroyed in either the calciner or the melter. The resulting sodium oxide would be incorporated into glass. The principal advantage of the new process is the elimination of a number of process steps

  3. Mass measurements on radioactive isotopes using the ISOLTRAP spectrometer

    CERN Document Server

    Dilling, J; Kluge, H J; Kohl, A; Lamour, E; Marx, G; Schwarz, S C; Bollen, G; Kellerbauer, A G; Moore, R B; Henry, S

    2000-01-01

    ISOLTRAP is a Penning trap mass spectrometer installed at the on line isotope separator ISOLDE at CERN. Direct measurements of the masses of short lived radio isotopes are performed using the existing triple trap system. This consists of three electromagnetic traps in tandem: a Paul trap to accumulate and bunch the 60 keV dc beam, a Penning trap for cooling and isobar separation, and a precision Penning trap for the determination of the masses by cyclotron resonance. Measurements of masses of unknown mercury isotopes and in the vicinity of doubly magic /sup 208/Pb are presented, all with an accuracy of delta m/m approximately=1*10/sup -7/. Developments to replace the Paul trap by a radiofrequency quadrupole ion guide system to increase the collection efficiency are presently under way and the status is presented. (10 refs).

  4. Spatial distribution sampling and Monte Carlo simulation of radioactive isotopes

    CERN Document Server

    Krainer, Alexander Michael

    2015-01-01

    This work focuses on the implementation of a program for random sampling of uniformly spatially distributed isotopes for Monte Carlo particle simulations and in specific FLUKA. With FLUKA it is possible to calculate the radio nuclide production in high energy fields. The decay of these nuclide, and therefore the resulting radiation field, however can only be simulated in the same geometry. This works gives the tool to simulate the decay of the produced nuclide in other geometries. With that the radiation field from an irradiated object can be simulated in arbitrary environments. The sampling of isotope mixtures was tested by simulating a 50/50 mixture of $Cs^{137}$ and $Co^{60}$. These isotopes are both well known and provide therefore a first reliable benchmark in that respect. The sampling of uniformly distributed coordinates was tested using the histogram test for various spatial distributions. The advantages and disadvantages of the program compared to standard methods are demonstrated in the real life ca...

  5. Nuclear charge radius measurements of radioactive beryllium isotopes

    CERN Multimedia

    2002-01-01

    We propose to measure the nuclear charge radii of the beryllium isotopes $^{7,9,10}$Be and the one-neutron halo isotope $^{11}$Be using laser spectroscopy of trapped ions. Ions produced at ISOLDE and ionized with the laser ion source will be cooled and bunched in the radio-frequency buncher of the ISOLTRAP experiment and then transferred into a specially designed Paul trap. Here, they will be cooled to temperatures in the mK range employing sympathetic and direct laser cooling. Precision laser spectroscopy of the isotope shift on the cooled ensemble in combination with accurate atomic structure calculations will provide nuclear charge radii with a precision of better than 3%. This will be the first model-independent determination of a one-neutron halo nuclear charge radius.

  6. Significance of iodine radioactive isotopes in the problem of radiation safety of nuclear fuel cycle

    International Nuclear Information System (INIS)

    Malenchenko, A.F.; Mironov, V.P.

    1979-01-01

    The data on actual wastes of nuclear-power plants, environmental distribution and biological effects of iodine radioactive isotopes have been analyzed. Dose-response relationship is estimated as well as its significance for struma maligna development under ionizing radiation and the contribution of iodine radionuclides resulted from nuclear power engineering to this process

  7. Cesium in the nutrient cycle

    International Nuclear Information System (INIS)

    Rantavaara, A.

    1992-01-01

    Most radioactive cesium in forests is deposited in soil, from which it passes into berries and mushrooms, and further to game. The cesium contents of Finnish berries and mushrooms vary depending on the intensity of Chernobyl fallout. Northern Haeme, Pirkanmaa and parts of central Finland received the most fallout. Weather conditions and the environmental factors, and other circumstances during the growth period, also affect the contents. However, consumption of wild berries, mushrooms and game need not be restricted because of radioactivity anywhere in Finland

  8. Cesium in the nutrient cycle. Cesium metsaen ravinnekierrossa marjojen ja sienten cesium ei vaehene

    Energy Technology Data Exchange (ETDEWEB)

    Rantavaara, A

    1992-01-01

    Most radioactive cesium in forests is deposited in soil, from which it passes into berries and mushrooms, and further to game. The cesium contents of Finnish berries and mushrooms vary depending on the intensity of Chernobyl fallout. Northern Haeme, Pirkanmaa and parts of central Finland received the most fallout. Weather conditions and the environmental factors, and other circumstances during the growth period, also affect the contents. However, consumption of wild berries, mushrooms and game need not be restricted because of radioactivity anywhere in Finland.

  9. Detection of the actinides and cesium from environmental samples

    Science.gov (United States)

    Snow, Mathew Spencer

    Detection of the actinides and cesium in the environment is important for a variety of applications ranging from environmental remediation to safeguards and nuclear forensics. The utilization of multiple different elemental concentrations and isotopic ratios together can significantly improve the ability to attribute contamination to a unique source term and/or generation process; however, the utilization of multiple elemental "signatures" together from environmental samples requires knowledge of the impact of chemical fractionation for various elements under a variety of environmental conditions (including predominantly aqueous versus arid conditions). The research reported in this dissertation focuses on three major areas: 1. Improving the understanding of actinide-mineral interactions at ultra-low concentrations. Chapter 2 reports a batch sorption and modeling study of Np(V) sorption to the mineral goethite from attomolar to micromolar concentrations. 2. Improving the detection capabilities for Thermal Ionization Mass Spectrometry (TIMS) analyses of ultra-trace cesium from environmental samples. Chapter 4 reports a new method which significantly improves the chemical yields, purification, sample processing time, and ultimately, the detection limits for TIMS analyses of femtogram quantities of cesium from a variety of environmental sample matrices. 3. Demonstrating how actinide and cesium concentrations and isotopic ratios from environmental samples can be utilized together to determine a wealth of information including environmental transport mechanisms (e.g. aqueous versus arid transport) and information on the processes which generated the original material. Chapters1, 3 and 5 demonstrate these principles using Pu, Am, Np, and Cs concentrations and isotopic ratios from contaminated soils taken near the Subsurface Disposal Area (SDA) of Idaho National Laboratory (INL) (a low level radioactive waste disposal site in southeastern Idaho).

  10. Cesium glass irradiation sources

    International Nuclear Information System (INIS)

    Plodinec, M.J.

    1982-01-01

    The precipitation process for the decontamination of soluble SRP wastes produces a material whose radioactivity is dominated by 137 Cs. Potentially, this material could be vitrified to produce irradiation sources similar to the Hanford CsCl sources. In this report, process steps necessary for the production of cesium glass irradiation sources (CGS), and the nature of the sources produced, are examined. Three options are considered in detail: direct vitrification of precipitation process waste; direct vitrification of this waste after organic destruction; and vitrification of cesium separated from the precipitation process waste. Direct vitrification is compatible with DWPF equipment, but process rates may be limited by high levels of combustible materials in the off-gas. Organic destruction would allow more rapid processing. In both cases, the source produced has a dose rate of 2 x 10 4 rads/hr at the surface. Cesium separation produces a source with a dose rate of 4 x 10 5 at the surface, which is nearer that of the Hanford sources (2 x 10 6 rads/hr). Additional processing steps would be required, as well as R and D to demonstrate that DWPF equipment is compatible with this intensely radioactive material

  11. Process for disposal of aqueous solutions containing radioactive isotopes

    Science.gov (United States)

    Colombo, Peter; Neilson, Jr., Robert M.; Becker, Walter W.

    1979-01-01

    A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99.degree. C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump.

  12. Process for disposal of aqueous solutions containing radioactive isotopes

    International Nuclear Information System (INIS)

    Colombo, P.; Neilson, R.M. Jr.; Becker, W.W.

    1979-01-01

    A process for disposing of radioactive aqueous waste solutions whereby the waste solution is utilized as the water of hydration to hydrate densified powdered portland cement in a leakproof container; said waste solution being dispersed without mechanical inter-mixing in situ in said bulk cement, thereafter the hydrated cement body is impregnated with a mixture of a monomer and polymerization catalyst to form polymer throughout the cement body. The entire process being carried out while maintaining the temperature of the components during the process at a temperature below 99 0 C. The container containing the solid polymer-impregnated body is thereafter stored at a radioactive waste storage dump such as an underground storage dump

  13. Separation of cesium-137 from uranium fission products via a NeoflonR column supporting tetraphenylboron

    International Nuclear Information System (INIS)

    Whitney, C.D.; Landsberger, S.

    2009-01-01

    Cesium is a member of the Group I alkali metals, very reactive earth metals that react vigorously with both air and water. The chemistry of cesium is much like the chemistry of neighboring elements on the periodic table, potassium and rubidium. This close relation creates many problems in plant-life exposed to cesium because it is so easily confused for potassium, an essential nutrient to plants. Radioactive 134 Cs and 137 Cs are also chemically akin to potassium and stable cesium. Uptake of these radioactive isotopes from groundwater by plant-life destroys the plant-life and can potentially expose humans to the radioactive affects of 134 Cs and 137 Cs. Much experimental work has been focused on the separation of 137 Cs from uranium fission products. In previous experimental work performed a column consisting of Kel-F supporting tetraphenylboron (TPB) was utilized to separate 137 Cs from uranium fission products. It is of interest at this time to attempt the separation of 134 Cs from 0.01M EDTA using the same method and Neoflon in the place of Kel-F as the inert support. The results of this experiment give a separation efficiency of 88% and show a linear relationship between the column bed length and the separation efficiency obtained. (author)

  14. A new class of medicament: radioactivity isotopes (1962); Une nouvelle classe de medicaments: les isotopes radioactifs (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Very many radioelement are used in medicine, either for diagnosis or as therapeutics. The development of medicine has entailed an increase in the number of application of radioactive isotopes. Firstly used in the form of simple inorganic molecules for diagnosis or as anticancer therapeutics, radioelements are now used for labelling organic molecules, allowing functional specific studies of any kind of nature. Their production is made difficult by their radio-active properties. Their pharmaceutical properties, determined by tests and controls, depend either from radiochemistry and from medicine. The author reminds, in this report, the methods for the preparation and analysis, and set out the medical application. (author) [French] De tres nombreux radioelements trouvent une application en medecine humaine, soit dans le diagnostic, soit en therapeutique. L'evolution de la medecine entraine un accroissement du champ d'application des isotopes radioactifs. D'abord utilises sous forme de molecules minerales simples, pour les diagnostics ou des therapeutiques anticancereuses, les radioelements sont maintenant introduits dans des molecules organiques qui permettent des etudes fonctionnelles specifiques de toute nature. Leur fabrication est compliquee par leurs proprietes radioactives. Leurs caracteristiques pharmaceutiques determinees par des essais et controles, sont liees d'une part a la radiochimie, d'autre part a la medecine. L'auteur rappelle, dans cet expose, les methodes de preparation et d'analyse et aborde les applications medicales. (auteur)

  15. A new class of medicament: radioactivity isotopes (1962); Une nouvelle classe de medicaments: les isotopes radioactifs (1962)

    Energy Technology Data Exchange (ETDEWEB)

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

    1962-07-01

    Very many radioelement are used in medicine, either for diagnosis or as therapeutics. The development of medicine has entailed an increase in the number of application of radioactive isotopes. Firstly used in the form of simple inorganic molecules for diagnosis or as anticancer therapeutics, radioelements are now used for labelling organic molecules, allowing functional specific studies of any kind of nature. Their production is made difficult by their radio-active properties. Their pharmaceutical properties, determined by tests and controls, depend either from radiochemistry and from medicine. The author reminds, in this report, the methods for the preparation and analysis, and set out the medical application. (author) [French] De tres nombreux radioelements trouvent une application en medecine humaine, soit dans le diagnostic, soit en therapeutique. L'evolution de la medecine entraine un accroissement du champ d'application des isotopes radioactifs. D'abord utilises sous forme de molecules minerales simples, pour les diagnostics ou des therapeutiques anticancereuses, les radioelements sont maintenant introduits dans des molecules organiques qui permettent des etudes fonctionnelles specifiques de toute nature. Leur fabrication est compliquee par leurs proprietes radioactives. Leurs caracteristiques pharmaceutiques determinees par des essais et controles, sont liees d'une part a la radiochimie, d'autre part a la medecine. L'auteur rappelle, dans cet expose, les methodes de preparation et d'analyse et aborde les applications medicales. (auteur)

  16. Laser fluorescence on radio-active isotopes produced in very low yield

    International Nuclear Information System (INIS)

    Dancy, D.E.; Billowes, J.; Grant, I.S.; Evans, D.E.; Griffith, J.A.R.; Wells, S.A.; Eastham, D.A.; Groves, J.; Smith, J.R.H.; Tolfree, D.W.L.; Walker, P.M.

    1990-01-01

    Fast particle-photon coincidence techniques, developed at Daresbury with strontium isotopes, allow ultra-sensitive laser fluorescence spectroscopy of beams of radio-active isotopes which can only be produced in very low yields. The technique has now been applied to neutron-deficient barium isotopes down to 120 Ba. From measured hyperfine splitting and isotope shifts, nuclear moments and changes in mean square radii have been determined. The work has revealed an abrupt increase in the mean square radius for 121 Ba large enough to disrupt the systematic staggering of nuclear size seen for the series. In a recent experiment an isomeric state of 127 Ba with a half-life of about 2 seconds has been produced in a very low yield; nevertheless we have succeeded in obtaining a fluorescence spectrum. (orig.)

  17. Process for improving the separation efficiency in the isolation of radioactive isotopes in elementary or chemically bonded form from liquids and gases

    International Nuclear Information System (INIS)

    Schmidberger, R.; Kirch, R.; Kock, W.

    1986-01-01

    In the process for the improvement of the separation efficiency in the isolation of radioactive isotopes in elementary or chemically bonded form from liquids or gases by ion exchange and adsorption, non-radioactive isotopes of the element to be isolated are added to the fluid before the isolation, whereas at the same time a large surplus of the non-radioactive isotopes to the radioactive isotopes is achieved by addition of only small quantities of compounds of the non-radioactive isotopes. (orig./RB) [de

  18. Disposal method of radioactive wastes

    International Nuclear Information System (INIS)

    Uetake, Naoto; Fukazawa, Tetsuo.

    1986-01-01

    Purpose: To improve the safety of underground disposal of radioactive wastes for a long period of time by surrounding the periphery of the radioactive wastes with materials that can inhibit the migration of radioactive nuclides and are physically and chemically stable. Method: Hardening products prepared from a water-hardenable calcium silicate compound and an aqueous solution of alkali silicate have compression strength as comparable with that of concretes, high water tightness and adsorbing property to radioactive isotopes such as cobalt similar to that of concretes and they also show adsorption to cesium which is not adsorbed to concretes. Further, the kneaded slurry thereof is excellent in the workability and can be poured even into narrow gaps. Accordingly, by alternately charging granular radioactive wastes and this slurry before hardening into the ground, the radioactive wastes can be put to underground disposal stably with simple procedures. (Kamimura, M.)

  19. Radioactive Emissions from Fission-Based Medical Isotope Production and Their Effect on Global Nuclear Explosion Detection

    International Nuclear Information System (INIS)

    Bowyer, T.; Saey, P.

    2015-01-01

    The use of medical isotopes, such as Tc-99m, is widespread with over 30 million procedures being performed every year, but the fission-based production of isotopes used for medical procedures causes emissions into the environment. This paper will show that gaseous radioactive isotopes of xenon, such as Xe-133, are released in high quantities, because they have a high fission cross section and they are difficult to scrub from the processes used to produce the medical isotopes due to their largely unreactive nature. Unfortunately, the reasons that large amounts of radioactive xenon isotopes are emitted from isotope production are the same as those that make these isotopes the most useful isotopes for the detection of underground nuclear explosions. Relatively recently, the nuclear explosion monitoring community has established a provisional monitoring network for the Comprehensive Nuclear-Test-Ban Treaty (CTBT) that includes radioactive xenon monitoring as a major component. This community has discovered that emissions from medical isotope production present a more serious problem to nuclear explosion monitoring than thought when the network was first conceived. To address the growing problem, a group of scientists in both the monitoring and the isotope production communities have come together to attempt to find scientific and pragmatic ways to address the emissions problems, recognizing that medical isotope production should not be adversely affected, while monitoring for nuclear explosions should remain effective as isotope production grows, changes, and spreads globally. (author)

  20. Trophic position and metabolic rate predict the long-term decay process of radioactive cesium in fish: a meta-analysis.

    Directory of Open Access Journals (Sweden)

    Hideyuki Doi

    Full Text Available Understanding the long-term behavior of radionuclides in organisms is important for estimating possible associated risks to human beings and ecosystems. As radioactive cesium (¹³⁷Cs can be accumulated in organisms and has a long physical half-life, it is very important to understand its long-term decay in organisms; however, the underlying mechanisms determining the decay process are little known. We performed a meta-analysis to collect published data on the long-term ¹³⁷Cs decay process in fish species to estimate biological (metabolic rate and ecological (trophic position, habitat, and diet type influences on this process. From the linear mixed models, we found that 1 trophic position could predict the day of maximum ¹³⁷Cs activity concentration in fish; and 2 the metabolic rate of the fish species and environmental water temperature could predict ecological half-lives and decay rates for fish species. These findings revealed that ecological and biological traits are important to predict the long-term decay process of ¹³⁷Cs activity concentration in fish.

  1. Artificial neural network application in isotopic characterization of radioactive waste drums

    International Nuclear Information System (INIS)

    Potiens Junior, Ademar Jose

    2005-01-01

    One of the most important aspects to the development of the nuclear technology is the safe management of the radioactive waste arising from several stages of the nuclear fuel cycles, as well as from production and use of radioisotope in the medicine, industry and research centers. The accurate characterization of this waste is not a simple task, given to its diversity in isotopic composition and non homogeneity in the space distribution and mass density. In this work it was developed a methodology for quantification and localization of radionuclides not non homogeneously distributed in a 200 liters drum based in the Monte Carlo Method and Artificial Neural Network (RNA), for application in the isotopic characterization of the stored radioactive waste at IPEN. Theoretical arrangements had been constructed involving the division of the radioactive waste drum in some units or cells and some possible configurations of source intensities. Beyond the determination of the detection positions, the respective detection efficiencies for each position in function of each cell of the drum had been obtained. After the construction and the training of the RNA's for each developed theoretical arrangement, the validation of the method were carried out for the two arrangements that had presented the best performance. The results obtained show that the methodology developed in this study could be an effective tool for isotopic characterization of radioactive wastes contained in many kind of packages. (author)

  2. Fabrication, characterization and radiation damage stability of hollandite based ceramics devoted to radioactive immobilisation; Synthese, caracterisation et etude du comportement sous irradiation electronique de matrices de type hollandite destinees au confinement du cesium radioactif

    Energy Technology Data Exchange (ETDEWEB)

    Aubin-Chevaldonnet, V. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DETCD/SCDV), Dept. d' Etudes du Traitement et du Conditionnement des Dechets, Service de Conditionnement des Dechets et Vitrification, 30 - Marcoule (France)

    2004-11-01

    Research on treating specifically the long-lived and high level nuclear wastes, notably cesium, is currently carried out in France. Cesium immobilization in host matrices of high chemical durability constitutes the favoured option. Hollandite matrix is a good candidate because of its high cesium incorporation ability and its excellent chemical stability. During this study, different compositions of hollandite ceramics Ba{sub x}Cs{sub y}C{sub z}Ti{sub 8-z}O{sub 16} (C = Al{sup 3+}, Cr{sup 3+}, Ga{sup 3+}, Fe{sup 3+}, Mg{sup 2+}, Sc{sup 3+}), synthesized by oxide route, were characterized in terms of structure, microstructure and physical and chemical properties. Iron ions seems to be the most suitable of the studied C cations to get high-performance hollandites. The stability of these ceramics under external electron irradiation, simulating the {beta} particles emitted by radioactive cesium, were also estimated, at the macroscopic and atomic scale. The point defects creation and their thermal stability were followed by electron paramagnetic resonance. (author)

  3. Radioactive isotope and radiation applications in the German Democratic Republic

    International Nuclear Information System (INIS)

    Leonhardt, J.W.; Wetzel, K.G.

    1988-01-01

    The state of the art of radioisotope and radiation applications in the GDR is reviewed. New results are discussed and the following examples of application are presented: radiometric coal ash monitors, radiotracer optimization of power stations, irradiation of waste cellulose, isotope ratios in natural gas prospection, radiographic imaging of impurities on wafer surfaces, food irradiation, tracer techniques by 15 N, radiation induced chlorination of PVC, radiotracer optimization of a caprolactame plant, ionization detectors for pollutants in the air, X-ray analyzer of pollutants in the wafer, radiation treatment of parquet in the palace of Sanssouci, and characterization of porcelain. 27 refs. (author)

  4. Alpha radioactivity for proton-rich even Pb isotopes

    Indian Academy of Sciences (India)

    Alpha radioactivity; proton-rich nuclei; half-life. PACS Nos 23.60.+e; 23.90. ... Z/N ∼= 0.65 to the region close to proton drip line with Z/N ∼= 0.82. The existing ... In the present work we have studied the systematic for alpha emission ..... 80. 0.200. 0.402. 0.497. 8.0. 320.51. 0.333. 0.754. 0.441. 16.0. 1300.72. 0.414. 0.927.

  5. Small zeolite column tests for removal of cesium from high radioactive contaminated water in Fukushima Daiichi Nuclear Power Station

    International Nuclear Information System (INIS)

    Hijikata, Takatoshi; Uozumi, Koichi; Tukada, Takeshi; Koyama, Tadafumi; Ishikawa, Keiji; Ono, Shoichi; Suzuki, Shunichi; Denton, Mark; Raymont, John

    2011-01-01

    After the earthquake on March 11th 2011, a large amount (more than 0.12 million m 3 ) of highly radioactive contaminated water had pooled in Fukushima Daiichi nuclear power station. As an urgent issue, highly radioactive nuclides should be removed from this contaminated water to reduce radioactivity in the turbine buildings and nuclear reactor buildings. Removal of Cs from this contaminated water is a key issue, because 134 Cs and 137 Cs are highly radioactive γ-emitting nuclides. The zeolite column system was used for Cs and Sr removal from the radioactive water of Three-Mile Island Unit 2, and modified columns were then developed as a Cs removal method for high-level radioactive water in US national laboratories (WRSC, ORNL, PNNL, Hanford, etc.). In order to treat Fukushima's highly contaminated water with a similar system, it was necessary to understand the properties of zeolite to remove Cs from sea salt as well as the applicability of the column system to a high throughput of around 1200 m 3 /d. The kinetic characteristics of the column were another property to be understood before actual operation. Hence, a functional small-scale zeolite column system was installed in CRIEPI for conducting the experiments to understand decontamination behaviors. Each column has a 2- or 3-cm inner diameter and a 12-cm height, and 12 g of zeolite-type media was packed into the column. The column experiments were carried out with Kurion-zeolite, Herschelite, at different feed rates of simulated water with different concentrations of Cs and sea salt. As for the water with 4 ppm Cs and 0 ppm sea salt, only a 10% Cs concentration was observed in the effluent after 20,000 bed volumes were fed at a rate of 33 cm/min, which corresponds to the actual system. On the other hand, a 40% Cs concentration was observed in the effluent after only 50 bed volumes were passed for water with 2 ppm Cs and 3.4 wt.% sea salt at a feed rate of 34 cm/min. As the absorption of Cs is hampered by the

  6. Solvent-free synthesis and application of nano-Fe/Ca/CaO/[PO{sub 4}] composite for dual separation and immobilization of stable and radioactive cesium in contaminated soils

    Energy Technology Data Exchange (ETDEWEB)

    Mallampati, Srinivasa Reddy, E-mail: srireddys@ulsan.ac.kr [Department of Civil and Environmental Engineering, University of Ulsan, Daehak-ro 93, Nam-gu, Ulsan 680-749 (Korea, Republic of); Mitoma, Yoshiharu, E-mail: mitomay@pu-hiroshima.ac.jp [Department of Environmental Sciences, Faculty of Life and Environmental Sciences, Prefectural University of Hiroshima, 562 Nanatsuka-Cho Shobara City, Hiroshima 727-0023 (Japan); Okuda, Tetsuji [Environmental Research and Management Center, Hiroshima University, 1-5-3 Kagamiyama, Higashi-Hiroshima, Hiroshima 739-8513 (Japan); Simion, Cristian [Politehnica University of Bucharest, Department of Organic Chemistry, Bucharest 060042 (Romania); Lee, Byeong Kyu [Department of Civil and Environmental Engineering, University of Ulsan, Daehak-ro 93, Nam-gu, Ulsan 680-749 (Korea, Republic of)

    2015-10-30

    Graphical abstract: A possible pathway for immobilization with the nano-Fe/Ca/CaO/[PO{sub 4}] treatment (a) {sup 133}Cs is adsorbed onto the soil particles, (b) Cs encapsulation through the formation of immobile salts, and (c) solid (small/finer or larger/aggregate) soil fraction separation. - Highlights: • Nano-Fe/Ca/CaO/[PO{sub 4}] composite for Cs immobilization in soil was developed. • Enhanced cesium separation and immobilization was done in dry condition. • By SEM analysis the amount of cesium detectable on soil particle surface decreases. • Leachable cesium concentrations reduced, lower than the standard regulatory limit. • Nano-Fe/Ca/CaO/[PO{sub 4}] a highly potential amendment for the remediation of Cs. - Abstract: This study assessed the synthesis and application of nano-Fe/Ca/CaO-based composite material for use as a separation and immobilizing treatment of dry soil contaminated by stable ({sup 133}Cs) and radioactive cesium species ({sup 134}Cs and {sup 137}Cs). After grinding with nano-Fe/CaO, nano-Fe/Ca/CaO, and nano-Fe/Ca/CaO/[PO{sub 4}], approximately 31, 25, and 22 wt% of magnetic fraction soil was separated. Their resultant {sup 133}Cs immobilization values were about 78, 81, and 100%, respectively. When real radioactive cesium contaminated soil obtained from Fukushima was treated with nano-Fe/Ca/CaO/[PO{sub 4}], approximately 27.3 wt% of magnetic and 72.75% of non-magnetic soil fractions were separated. The highest amount of entrapped {sup 134}Cs and {sup 137}Cs was found in the lowest weight of the magnetically separated soil fraction (i.e., 80% in 27.3% of treated soil). Results show that {sup 134}Cs and {sup 137}Cs either in the magnetic or non-magnetic soil fractions was 100% immobilized. The morphology and mineral phases of the nano-Fe/Ca/CaO/[PO{sub 4}] treated soil were characterized using SEM–EDS, EPMA, and XRD analysis. The EPMA and XRD patterns indicate that the main fraction of enclosed/bound materials on treated soil

  7. Electrochemical Removal of Radioactive Cesium from Nuclear Waste Using the Dendritic Copper Hexacyanoferrate/Carbon Nanotube Hybrids

    International Nuclear Information System (INIS)

    Zheng, Yuanyuan; Qiao, Junhua; Yuan, Junhua; Shen, Jianfeng; Wang, Ai-jun; Niu, Li

    2017-01-01

    Highlights: •Copper hexacyanoferrate was uniformly covered on carbon nanotubes. •Cs + ion can be exchanged using this hybrid by controlling the electrode potential. •The maximum of Cs + adsorption capacity is 310 mg·g −1 in 50 μM Cs + solution. •The distribution coefficient of Cs + in this hybrid reaches up to 568 L·g −1 ,. •This hybrid can be regenerated with high stability for Cs + exchange. -- Abstract: A novel electrochemical separation system was developed based on copper hexacyanoferrate/multiwalled carbon nanotube (CuHCF/MWCNT) hybrids for selectively removing cesium from wastewater. These CuHCF/MWCNT hybrids were prepared by co-precipitation strategy. The as-prepared CuHCF nanoparticles were uniformly covered on MWCNTs to form a dendritic core-shell structure. This novel structure can improve CuHCFs conductivity, making CuHCFs more accessible for ion exchange. The uptake and release of alkali ion in CuHCF/MWCNT hybrids can be shifted mutually by switching the applied potentials between the anode and cathode. This ion exchange is a fast and reversible process associated with electron transfer in CuHCFs. The potential response depends on the radius of alkali ion. Using this electrochemical adsorption system (EAS), the maximum adsorption capacity (Q max ) of Cs + ion for CuHCFs/MWCNT hybrids reaches up to 310 mg·g −1 in 50 μM Cs + solution with a distribution coefficient K d of 568 L·g −1 , superior to the Cs + removal performance by the conventional adsorption system (Q max 230 mg·g −1 , Kd 389 L·g −1 ). Besides, CuHCF/MWCNT hybrids can be regenerated electrochemically. In addition to the advantages in Cs + removal performance and electrochemical regenerability, they can maintain considerable stability with uptake capacity retention of 85% after 100 cycles of adsorption and regeneration.

  8. Individual radiation doses due to atmospheric diffusion of cesium-137 in connection with land transport of radioactive material

    International Nuclear Information System (INIS)

    Wilkens, A.-B.

    1979-02-01

    The radiological consequences of a discharge of Cs-137 into the air in connection with the tranportation on land of radioactive material. The accident is supposed to take place during the vegetation period. Possible exposure ways are mapped out and radiation doses are calculated for acute and chromic phases, respectively. The highest doses were obtained by the consumption of food which has been produced on contaminated areas during the year of discharge. (E.R.)

  9. Transmutation of stable isotopes and deactivation of radioactive waste in growing biological systems

    International Nuclear Information System (INIS)

    Vysotskii, Vladimir I.; Kornilova, Alla A.

    2013-01-01

    Highlights: ► The phenomena of isotope transmutation in growing microbiological cultures were investigated. ► Transmutation in microbiological associations is 20 times more effective than in pure cultures. ► Transmutation of radioactive nuclei to stable isotopes in such associations was investigated. ► The most accelerated rate of Cs 137 to stable Ba 138 isotope transmutation was 310 days. ► “Microbiological deactivation” may be used for deactivation of Chernobyl and Fukushima areas. - Abstract: The report presents the results of qualifying examinations of stable and radioactive isotopes transmutation processes in growing microbiological cultures. It is shown that transmutation of stable isotopes during the process of growth of microbiological cultures, at optimal conditions in microbiological associations, is 20 times more effective than the same transmutation process in the form of “one-line” (pure) microbiological cultures. In the work, the process of direct, controlled decontamination of highly active intermediate lifetime and long-lived reactor isotopes (reactor waste) through the process of growing microbiological associations has been studied. In the control experiment (flask with active water but without microbiological associations), the “usual” law of nuclear decay applies, and the life-time of Cs 137 isotope was about 30 years. The most rapidly increasing decay rate, which occurred with a lifetime τ * ≈ 310 days (involving an increase in rate, and decrease in lifetime by a factor of 35 times) was observed in the presence of Ca salt in closed flask with active water contained Cs 137 solution and optimal microbiological association

  10. Radioactivity of neutron rich oxygen, fluorine and neon isotopes

    International Nuclear Information System (INIS)

    Reed, A.T.; Page, R.D.; Tarasov, O.

    1999-01-01

    The γ-radiation and neutrons emitted following the β-decays of 24 O, 25-27 F and 28-30 Ne have been measured. The nuclides were produced in the quasi-fragmentation of a 78 MeV/A 36 S beam, separated in-flight and identified through time-of-flight and energy loss measurements. The ions were stopped in a silicon detector system, which was used to detect the β-particles emitted in their subsequent radioactive decay. The coincident γ-rays were measured using four large Ge detectors mounted close to the implantation point and the neutrons were detected using forty-two 3 He proportional counters. The measured γ-ray energy spectra are compared with shell model calculations and, where available, the level energies are deduced from transfer reactions

  11. Studies of colossal magnetoresistive oxides with radioactive isotopes

    CERN Document Server

    CERN. Geneva. ISOLDE and Neutron Time-of-Flight Experiments Committee; Amaral, V S; Araújo, J P; Butz, T; Correia, J G; Dubourdieu, C; Habermeier, H U; Lourenço, A A; Marques, J G; Da Silva, M F A; Senateur, J P; Soares, J C; Sousa, J B; Suryan, R; Tokura, Y; Tavares, P B; Tomioka, Y; Tröger, W; Vantomme, A; Vieira, J M; Wahl, U; Weiss, F P; INTC

    2000-01-01

    We propose to study Colossal Magnetoresistive (CMR) oxides with several nuclear techniques, which use radioactive elements at ISOLDE. Our aim is to provide local and element selective information on some of the doping mechanisms that rule electronic interactions and magnetoresistance, in a complementary way to the use of conventional characterisation techniques. Three main topics are proposed: \\\\ \\\\ a) Studies of local [charge and] structural modifications in antiferromagnetic LaMnO$_{3+ \\delta}$ and La$_{1-x}$R$_{x}$MnO$_{3}$ with R=Ca and Cd, doped ferromagnetic systems with competing interactions: - research on the lattice site and electronic characterisation of the doping element. \\\\ \\\\ b) Studies of self doped La$_{x}$R$_{1-x}$MnO$_{3+\\delta}$ systems, with oxygen and cation non-stoichiometry: -learning the role of defects in the optimisation of magnetoresistive properties. \\\\ \\\\ c) Probing the disorder and quenched random field effects in the vicinity of the charge or orbital Ordered/Ferromagnetic phase...

  12. Studies of Colossal Magnetoresistive Oxides with Radioactive Isotopes

    CERN Multimedia

    2002-01-01

    We propose to study Colossal Magnetoresistive (CMR) oxides with several nuclear techniques, which use radioactive elements at ISOLDE. Our aim is to provide local and element selective information on some of the doping mechanisms that rule electronic interactions and magneto- resistance, in a complementary way to the use of conventional characterisation techniques. Three main topics are proposed: \\\\ \\\\ a) Studies of local [charge and] structural modifications in antiferromagnetic LaMnO$_{3+\\delta}$ and La$_{1-x}$R$_{x}$MnO$_{3}$ with R=Ca and Cd, doped ferromagnetic systems with competing interactions: - research on the lattice site and electronic characterisation of the doping element. \\\\ \\\\ b) Studies of self doped La$_{x}$R$_{1-x}$MnO$_{3+\\delta}$ systems, with oxygen and cation non- stoichiometry: - learning the role of defects in the optimisation of magnetoresestive properties. \\\\ \\\\ c) Probing the disorder and quenched random field effects in the vicinity of the charge or orbital Ordered/Ferromagnetic p...

  13. Estimation of burnup with cesium isotopes based on gamma-scanning of a instrumented fuel capsule(02F-11K) in hot-cell

    International Nuclear Information System (INIS)

    Song, Ung Sup; Kim, Hee Moon; Park, Dae Gyu; Paik, Seung Je; Lee, Hong Gi; Choo, Yong Sun; Hong Kwon Pyo

    2004-01-01

    Many experimental inspection have been performed to obtain the burnup of fuel. In the case, chemical analysis were popular with high reliability. High radioactivity of fuel was severe problem during destructive procedure. Afterward, many researchers have studied calculation of burnup using gamma detector as the non-destructive method. methodologies of gamma-scanning test have been developed as well as higher accuracy of detector. Generally, Cs-137 and Cs-134 are standard isotopes for long-term cooling spent fuel to estimate burnup, because atomic ratio of them follows the linearity with burnup

  14. A novel hydrothermal method to convert incineration ash into pollucite for the immobilization of a simulant radioactive cesium

    Energy Technology Data Exchange (ETDEWEB)

    Jing, Zhenzi, E-mail: zzjing@tongji.edu.cn [Key Laboratory of Advanced Civil Engineering Materials, Ministry of Education, Tongji University, 4800 Cao’an Road, Shanghai 201804 (China); Hao, Wenbo; He, Xiaojun; Fan, Junjie; Zhang, Yi; Miao, Jiajun [Key Laboratory of Advanced Civil Engineering Materials, Ministry of Education, Tongji University, 4800 Cao’an Road, Shanghai 201804 (China); Jin, Fangming [School of Environmental Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai 200240 (China)

    2016-04-05

    Highlights: • Incineration ash could be converted hydrothermally to pollucite to immobilize Cs. • Pollucite could be synthesized readily with a wide range of Cs/Si ratios. • With Ca(OH){sub 2} added, a tough pollucite could be used to solidify Cs-polluted RHA. • Leaching results showed that the amount of Cs leached from specimen was very low. - Abstract: The Fukushima nuclear accident in Japan on March 11, 2011 produced huge amounts of Cs-polluted incineration ashes; conventional solidification methods seem unsuitable for the treatment of large amounts of Cs-polluted ashes. A novel hydrothermal method was developed to directly convert Cs-polluted incineration ash (rice husk ash) into pollucite to immobilize Cs in its crystal structure in situ. Results revealed that pollucite could be synthesized readily over a wide range of added Cs (Cs/Si = 0.2–0.6); the addition of more Cs (Cs/Si ≥ 0.5) caused the formation of a small amount of cesium aluminosilicate (CsAlSiO{sub 4}), which exhibits poor immobilization behavior for Cs. Pollucite could be formed even for a short curing time (1 h) or at a low curing temperature (150 °C). However, a high curing temperature or a long curing time favored the formation of a pure pollucite. With the added calcium hydroxide, a tough specimen with a flexural strength of approximately 22 MPa could be obtained, which suggested that this technology may be applied directly to the solidification of Cs-polluted incineration ashes. Hydrogarnet and tobermorite formations enhanced the strength of the solidified specimens, and meanwhile the formed pollucite was present in a matrix steadily. Leaching test demonstrated that the amount of Cs that leached from the synthesized specimens was very low (0.49 × 10{sup −5}–2.31 × 10{sup −5}) and even lower than that from the reference hollandite-rich synroc (2.0 × 10{sup −2}), although a higher content of Cs was found in the synthesized pollucite specimens (6.0–31.7%) than in the

  15. Survey of literature on the use of radioactive isotopes in agriculture published between 1973 and 1980

    International Nuclear Information System (INIS)

    Van der Westhuizen, M.; Van der Bank, D.J.; Van der Berg, G.W.J.; Uys, A.

    1980-04-01

    The literature on the use of radioactive isotopes in agriculture appears in reports and magazines which are spread over a wide spectrum of disciplines, e.g. nuclear science and agriculture science. For this reason it will be of assistance to practicing scientists to have in one volume a compilation of literature covering this field. The first part of this report consists of a list of books on this subject published by the International Atomic Energy Agency in Vienna. Most of the books are proceedings of symposia and seminars but the report also includes manuals on specialised subjects, useful for scientists starting in this field. The second part of this report consists of titles of reports and magazine articles. These were obtained form 'INIS Atomindex' for the years 1973-1980. It is hoped that the items presented in this report will be useful to scientists interested in the application of radioactive isotopes to agricultural research

  16. TRI mu P - a radioactive isotope trapping facility under construction at KVI

    CERN Document Server

    Berg, G P; Dermois, O; Harakeh, M N; Hoekstra, R; Jungmann, Klaus; Kopecky, S; Morgenstern, R; Rogachevskiy, A; Timmermans, R; Willmann, L; Wilschut, H W

    2003-01-01

    At the Kernfysisch Versneller Instituut a new facility (TRI mu P) is under development which aims to investigate fundamental interactions using radioactive ions. A spectrum of radioactive isotopes will be produced in inverse-kinematics and fragmentation reactions using heavy-ion beams from the superconducting cyclotron AGOR. The reaction products will be separated from the primary beam in a dual-mode recoil and fragment separator. The beam of isotopes of interest will be transformed into a low-energy, high-quality, bunched beam and, after neutralization, stored in an atom trap. The emphasis will be put on studying the origin of parity violation via beta-nu angular correlations and the search for permanent electric dipole moments of atoms and nuclei. The facility will be open to outside users; suggestions for collaborations to extend the scientific program are encouraged.

  17. Dating of oilfield contamination by Natural Occurring Radioactive Materials (NORM) using isotopic ratios

    International Nuclear Information System (INIS)

    Al-Masri, M. S.; Othman, I.; Aba, A.

    2008-05-01

    In the present work, the possibility of using radium isotope ratios (226, 224, 228) for dating of NORM contaminated sites in the oilfields due to uncontrolled disposal of produced water into the environmental NORM contaminated soil sample were collected from different locations in Syrian Oilfields and radioactivity analysed. In addition, production water samples were collected and analysed to determine the isotopes ratios of the naturally occurring radioactive materials. The results have shown that the 228 Ra/ 226 Ra can be successfully used to date contaminated soil provided that this ratio is determined in production water. Moreover, the 210 Pb/ 226 Ra activity ratios was used for the first time for dating of contaminated soil where all factors affecting the method application have been evaluated. Furthermore, the obtained results for dating using the three methods were compared with the actual contamination dates provided by the oil companies. (Authors)

  18. Uranium isotopes as radioactive pollutants in groundwaters of the Morro do Ferro thorium deposit, Brazil

    International Nuclear Information System (INIS)

    Bonotto, D.M.

    1991-01-01

    Groundwater and surface water samples were collected at Morro do Ferro, a thorium and rare earth deposit located on the Pocos de Caldas Plateau, Minas Gerais State, Brazil, to evaluate if the mechanisms related to the migration of 238 U and 234 U isotopes can generate concentrations greater than the gross-alpha activity contaminant limit. The 238 U content range was 0.003-0.24 pCi/1 and the 234 U content range was 0.004-0.25 pCi/1, showing that the studied hydrologic environment doesn't indicate pollution by radioactivity due to these nuclides. However, 226 Ra and 228 Ra isotopes can be considered as radioactive pollutants in groundwaters but not in surface waters of the Morro do Ferro. (author)

  19. Use of Eichornia crassipes for treatment of low level liquid radioactive waste

    Energy Technology Data Exchange (ETDEWEB)

    Hafez, N.; Ramadan, Y.S.; Hassanin, R.A.; Gafez, M.B. (Atomic Energy Authority, Hot Lab. Center, Cairo (Egypt))

    1993-01-01

    Radioactive and non-radioactive isotopes of cobalt, cerium and cesium were found to be accumulated inside Eichornia crassipes (the water hyacinth). The rate and extent of accumulation were dependent upon environmental parameters such as pH, temperature and interference by certain anions and cations. The accumulation rate of radioactive isotopes inside Eichornia crassipes, were more rapid than non-active ions. The results showed that accumulation of such metals inside the plant could be used successfully in the treatment of low-level liquid radioactive wastes. (author) 4 figs., 2 tabs., 15 refs.

  20. Use of Eichornia crassipes for treatment of low level liquid radioactive waste

    International Nuclear Information System (INIS)

    Hafez, N.; Ramadan, Y.S.; Hassanin, R.A.; Gafez, M.B.

    1993-01-01

    Radioactive and non-radioactive isotopes of cobalt, cerium and cesium were found to be accumulated inside Eichornia crassipes (the water hyacinth). The rate and extent of accumulation were dependent upon environmental parameters such as pH, temperature and interference by certain anions and cations. The accumulation rate of radioactive isotopes inside Eichornia crassipes, were more rapid than non-active ions. The results showed that accumulation of such metals inside the plant could be used successfully in the treatment of low-level liquid radioactive wastes. (author) 4 figs., 2 tabs., 15 refs

  1. Memory Effects Study of Measuring Radioactive Xenon Isotopes With β-γ Coincidence Method

    International Nuclear Information System (INIS)

    Jia Huaimao; Wang Shilian; Wang Jun; Li Qi; Zhao Yungang; Fan Yuanqing; Zhang Xinjun

    2010-01-01

    The β-γ coincidence technique is a kind of the key important method to detect radioactive xenon isotopes for the Comprehensive Nuclear-Test-Ban Treaty (CTBT). This paper describes noble gases memory effects of β-γ coincidence detector. Xenon memory effects were measured and its influence on detector's minimum detectable activity (MDA) was evaluated. The methods of reducing xenon memory effects were studied. In conclusion, aluminium coated plastic scintillator and YAP scintillator can remarkably decrease xenon memory effects. (authors)

  2. The MOON-1 detector construction and the study of backgrounds from radioactive isotopes

    International Nuclear Information System (INIS)

    Ogama, T; Nakamura, H; Ejiri, H; Fushimi, K; Ichihara, K; Matsuoka, K; Nomachi, M; Hazama, R; Umehara, S; Yoshida, S; Sakiuchi, T; Hai, V H; Sugaya, Y

    2006-01-01

    MOON is a multilayer system of plastic scintillators and 100 Mo films for 100 Mo 0νββ decays. A prototype detector MOON-1 was built with 6 layers of plastic scintillators and 142g of 100Mo films for background (BG), energy and position resolution studies of the MOON detector. No serious BG from natural radioactive isotopes (RI) for 0νββ detection was found

  3. Hyperfine spectra of the radioactive isotopes 81Kr and 85Kr

    International Nuclear Information System (INIS)

    Cannon, B.D.

    1993-01-01

    Isotope shifts and hyperfine constants are reported for the radioactive isotopes 81 Kr and 85 Kr and the stable isotope 83 Kr. The previously unreported nuclear moments of 81 Kr were determined to be μ I =-0.909(4) nuclear magneton and Q=+0.630(13) b from the hyperfine constants. This work increases the number of transitions for which 85 Kr hyperfine constants and isotope shifts have been measured from 1 to 4. The hyperfine anomaly for krypton reported in the previous measurement of 85 Kr hyperfine constants [H. Gerhardt et al., Hyperfine Interact. 9, 175 (1981)] is not supported by this work. The isotope shifts and hyperfine constants of 83 Kr measured in this work are in excellent agreement with previous work. Saturation spectroscopy was used to study transitions from krypton's metastable 1s 5 state to the 2p 9 , 2p 7 , and 2p 6 states. In saturation spectra, different line shapes were observed for the even- and odd-mass krypton isotopes. This even- versus odd-line-mass shape difference can be explained using the large cross section that has been reported for collisional transfer of the 1s 5 state excitation between krypton atoms. Two-color two-photon laser-induced fluorescence was used to measure the hyperfine spectra of the 1s 5- 4d 4 ' transition using the 2p 9 state as the intermediate state. This technique proved to be more sensitive than saturation spectroscopy

  4. Development of equipment for migration control of radioactive cesium absorbed in suspended solid in the river water

    International Nuclear Information System (INIS)

    Ohyama, Takuya; Ishikawa, Hiroyasu

    2015-01-01

    To prevent inflow of radiocesium with suspended solids (SS) into farmland and increase in dose rate of the river bank in the midstream and downstream, it is important to reduce SS in the river water; therefore we newly developed the test equipment using non-woven fabrics as a trapping material to capture and reduce the SS in running small river water. Authors installed this equipment into the small river which is located in mountainous area surrounded by forests where radionuclides released from the Fukushima Daiichi Nuclear Power Plant were deposited. Two turbidity gauges are installed in inflow and outflow point of this equipment and the turbidity has been continuously measured. From the result of a comparison of turbidity between inflow point and outflow point, a turbidity of inflow point is always higher than outflow point during ordinary water-level; this equipment can capture and reduce the SS in the river water. Through the analysis of particle size distribution, identification of minerals and measurement of concentration of radioactive Cs of the captured SS in the non-woven fabric should be carried out, to clarify the effectiveness of this equipment and non-woven fabrics for reducing the radioactive Cs in small rivers in the future. (author)

  5. Cesium distribution and phases in proxy experiments on the incineration of radioactively contaminated waste from the Fukushima area.

    Science.gov (United States)

    Saffarzadeh, Amirhomayoun; Shimaoka, Takayuki; Kakuta, Yoshitada; Kawano, Takashi

    2014-10-01

    After the March 11, 2011 Tohoku earthquake and Fukushima I Nuclear Power Plant accident, incineration was initially adopted as an effective technique for the treatment of post-disaster wastes. Accordingly, considerable amounts of radioactively contaminated residues were immediately generated through incineration. The level of radioactivity associated with radiocesium in the incineration ash residues (bottom ash and fly ash) became significantly high (several thousand to 100,000 Bq/kg) as a result of this treatment. In order to understand the modes of occurrence of radiocesium, bottom ash products were synthesized through combusting of refuse-derived fuel (RDF) with stable Cs salts in a pilot incinerator. Microscopic and microanalytical (SEM-EDX) techniques were applied and the following Cs categories were identified: low and high concentrations in the matrix glass, low-level partitioning into some newly-formed silicate minerals, partitioning into metal-sulfide compounds, and occurring in newly-formed Cs-rich minerals. These categories that are essentially silicate-bound are the most dominant forms in large and medium size bottom ash particles. It is expected that these achievements provide solutions to the immobilization of radiocesium in the incineration ash products contaminated by Fukushima nuclear accident. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. Use of environmental radioactive isotopes in geothermal prospecting

    International Nuclear Information System (INIS)

    Balcazar, M.; Lopez M, A.; Huerta, M.; Flores R, J. H.; Pena, P.

    2010-10-01

    Oil resources decrease and environmental impact of burning fossil fuels support the use of alternative energies around the world. By far nuclear energy is the alternative which can supply huge amount of clean energy. Mexico has two nuclear units and has also explored and exploited the use of other complementary renewal energies, as wind and geothermal. Mexico is the third geothermal-energy producer in the world with an installed capacity of 960 MW and is planning the installation of 146 MW for the period 2010-2011, according to information of the Mexican Federal Electricity Board. This paper presents a study case, whose goal is to look for areas where the heat source can be located in geothermal energy fields under prospecting. The method consist in detecting a natural radioactive tracer, which is transported to the earth surface by geo-gases, generated close to the heat source, revealing areas of high permeability properties and open active fractures. Those areas are cross correlated to other resistivity, gravimetric and magnetic geophysical parameters in the geothermal filed to better define the heat source in the field. (Author)

  7. Expeditious syntheses of stable and radioactive isotope-labeled anticonvulsant agent, JNJ-26990990, and its metabolites.

    Science.gov (United States)

    Lin, Ronghui; Weaner, Larry E; Hoerr, David C; Salter, Rhys; Gong, Yong

    2013-01-01

    Syntheses of stable and radioactive isotope-labeled anticonvulsant agent, JNJ-26990990, that is, N-(benzo[b]thien-3-ylmethyl)-sulfamide and its metabolites are described. [(13)C(15)N]Benzo[b]thiophene-3-carbonitrile was first prepared by coupling of 3-bromo-benzo[b]thiophene with [(13)C(15)N]-copper cyanide. The resultant [(13)C(15)N]benzo[b]thiophene-3-carbonitrile was reduced with lithium aluminum deuteride to give [(13)CD2(15)N]benzo[b]thiophen-3-yl-methylamine; which was then coupled with sulfamide to afford [(13)CD2(15)N]-N-(benzo[b]thien-3-ylmethyl)-sulfamide, the stable isotope-labeled compound with four stable isotope atoms. Direct oxidation of [(13)CD2(15)N]-N-(benzo[b]thien-3-ylmethyl)-sulfamide with hydrogen peroxide and peracetic acid gave the stable isotope-labeled sulfoxide and sulfone metabolites. On the other hand, radioactive (14)C-labeled N-(benzo[b]thien-3-ylmethyl)-sulfamide was prepared conveniently by sequential coupling of 3-bromo-benzo[b]thiophene with [(14)C]-copper cyanide, reduction of the carbonitrile to carboxaldehyde, and reductive amination with sulfamide. Copyright © 2013 John Wiley & Sons, Ltd.

  8. Simultaneous determination of radioactive halogen isotopes and 99Tc

    International Nuclear Information System (INIS)

    Kabai, E.; Vajda, N.; Gaca, P.

    2003-01-01

    The purpose of this study was to develop a simplified method for simultaneous determination of radiologically important halogen isotopes and 99 Tc from different types of samples like environmental, biological and waste samples. Due to their long half-lives (longer than 10 5 years) they play important role in the nuclear cycle, especially in environmental monitoring and protection. For a rapid response in the evaluation of 129 I, 36 Cl and 99 Tc contamination levels of these samples it is advantageous to combine the existing individual methods. According to the present procedure, iodine, chlorine and technetium are separated selectively from the same sample aliquot followed by the β spectrometry of the purified fractions. Increased sensitivities can be achieved by neutron activation (NA) especially in the case of 129 I. Our work intends to solve the problem by combining the well-known hot acidic distillation method for iodine separation with the organic extraction process characteristic for technetium separation. The major objective of the work was to separate the disturbing halides from iodine. For this purpose a selective oxidant was applied. For the sample destruction and fractionated distillation an air flow-through installation was used with hot concentrated sulphuric and nitric acids. The trap for iodine contained 3 M NaOH solution. After iodine separation the trap was exchanged for a new one containing the same solution for trapping chlorine or bromine with an addition of 0.01 M KMnO 4 solution as an oxidative agent. As expected, the main part of technetium was contained in the acidic residue after distillation. Tc purification was performed by organic extraction with TBP and TEVA column. (author)

  9. Re-suspension of Cesium-134/137 into the Canadian Environment and the Contribution Stemming from the Fukushima-Daiichi Nuclear Incident

    Science.gov (United States)

    Mercier, Jean-Francois; Zhang, Weihua; Loignon-Houle, Francis; Cooke, Michael W.; Ungar, Kurt R.; Pellerin, Eric R.

    2013-04-01

    Cesium-137 (t1/2 = 30 yr) and cesium-134 (t1/2 = 2yr) constitute major fission by-products observed as the result of a nuclear incident. Such radioisotopes become integrated into the soil and biomass, and can therefore undergo re-suspension into the environment via activities such as forest fires. The Canadian Radiological Monitoring Network (CRMN), which consists of 26 environmental monitoring stations spread across the country, commonly observes cesium-137 in air filters due to re-suspension of material originating from long-past weapons testing. Cesium-134 is not observed owing to its relatively short half-life. The Fukushima-Daiichi nuclear power plant incident of March 2011 caused a major release of radioactive materials into the environment. In Canada, small quantities of both cesium-137 and cesium-134 fallout were detected with great frequency in the weeks which followed, falling off rapidly beginning in July 2011. Since September 2011, the CRMN has detected both cesium-137 and cesium-134 from air filters collected at Yellowknife, Resolute, and Quebec City locations. Using the known initial cesium-134/cesium-137 ratio stemming from this incident, along with a statistical assessment of the normality of the data distribution, we herein present evidence that strongly suggests that these activity spikes are due to re-suspended hot particles originating from the Fukushima-Daiichi nuclear power plant incident. Moreover, we have evidence to suggest that this re-suspension is localized in nature. This study provided empirical insight into the transport and uptake of radionuclides over vast distances, and it demonstrates that the CRMN was able to detect evidence of a re-suspension of Fukushima-Daiichi related isotopes.

  10. Investigation of radioactive cesium transportation from forest canopy to floor by litterfall, stemflow and throughfall in northern Fukushima

    Science.gov (United States)

    Endo, I.; Ohte, N.; Iseda, K.; Tanoi, K.; Hirose, A.; Kobayashi, N. I.; Murakami, M.; Tokuchi, N.; Ohashi, M.

    2015-12-01

    After the Fukushima Daiichi nuclear power plant accident due to Great East Japan Earthquake in March 11th 2011, large areas of forest have been highly contaminated by the radioactive nuclides. Most of the deposited radioactive material to the canopy is then washed out with rainfall or leaf fall due to the tree phenology. There have been studies showing that the amount of 137Cs transportation differs among litter components and water pathways, and was affected by seasonal variations. Thus, to evaluate the amount of 137Cs flux from canopy to forest floor, continuous monitoring of each component (litterfall, throughfall and stemflow) is required. We investigated the annual transfer of 137Cs from the forest canopy to the floor by litterfall, throughfall and stemflow at two different forest types in northern Fukushima after two years from the accident. Seasonal variations in 137Cs transportation and differences between forests types were also determined. Forest sites were set in the upstream part of Kami-Oguni River catchment at Date city, which locates approximately 50km northwest from the Fukushima Dai-ichi Nuclear Power Plant. The study sites consisted of two deciduous (Mixed deciduous-1, Mixed deciduous-2) and one cedar (Cedar plantation) stands. The cumulative 137Cs transportation from the forest canopy to the floor was 6.6 kBq m-2 year-1 for the Mixed deciduous-1, 3.9 kBq m-2 year-1 for the Mixed deciduous-2 and 11.0 kBq m-2 year-1 for the Cedar plantation. 137Cs transportation with litterfall increased in the defoliation period which correlated with the increased amount of litterfall. 137Cs transportation with throughfall and stemflow increased in the rainy season. 137Cs flux by litterfall was higher in Cedar plantation compared with that of mixed deciduous forests, while the opposite result was obtained for stemflow. The ratio of annual 137Cs flux and the estimated 137Cs amount deposited in the forests will be discussed.

  11. Copper Ferrocyanide Functionalized Core-Shell Magnetic Silica Composites for the Selective Removal of Cesium Ions from Radioactive Liquid Waste.

    Science.gov (United States)

    Lee, Hyun Kyu; Yang, Da Som; Oh, Wonzin; Choi, Sang-June

    2016-06-01

    The copper ferrocyanide functionalized core-shell magnetic silica composite (mag@silica-CuFC) was prepared and was found to be easily separated from aqueous solutions by using magnetic field. The synthesized mag@silica-CuFC composite has a high sorption ability of Cs owing to its strong affinity for Cs as well as the high surface area of the supports. Cs sorption on the mag@silica-CuFC composite quickly reached the sorption equilibrium after 2 h of contact time. The effect of the presence of salts with a high concentration of up to 3.5 wt% on the efficiency of Cs sorption onto the composites was also studied. The maximum sorption ability was found to be maintained in the presence of up to 3.5 wt% of NaCl in the solution. Considering these results, the mag@silica-CuFC composite has great potential for use as an effective sorbent for the selective removal of radioactive Cs ions.

  12. Optimization and validation of a chemical process for uranium, mercury and cesium leaching from cemented radioactive wastes

    Energy Technology Data Exchange (ETDEWEB)

    Reynier, N.; Lastra, R.; Laviolette, C.; Bouzoubaa, N., E-mail: nicolas.reynier@canada.ca [Natural Resources Canada, CanmetMINING, Ottawa, Ontario (Canada); Chapman, M. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

    2015-12-15

    Canadian Nuclear Laboratories (CNL) is developing a treatment and long-term management strategy for a legacy cemented radioactive waste that contains uranium, mercury, and fission products. Extracting the uranium would be advantageous for decreasing the waste classification and reducing the cost of long-term management. The chemical leachability of 3 key elements (U, Hg, and Cs) from a surrogate cemented waste (SCW) was studied with several lixiviants. The results showed that the most promising approach to leach and recover U, Hg, and Cs is the direct leaching of the SCW with H{sub 2}SO{sub 4} in strong saline media. Operating parameters such as particle size, temperature, pulp density, leaching time, acid and salt concentrations, number of leaching/washing steps, etc. were optimized to improve key elements solubilization. Sulfuric leaching in saline media of a SCW (U5) containing 1182 ppm of U, 1598 ppm of Hg, and 7.9 ppm of Cs in the optimized conditions allows key elements solubilisation of 98.5 ± 0.4%, 96.6 ± 0.1%, and 93.8 ± 1.1% of U, Hg, and Cs, respectively. This solubilization process was then applied in triplicate to 7 other SCWs prepared with different cements, liquid ratios, and at different aging times and temperatures. Concentrated sulfuric acid is added to the slurry until the pH is about 2, which causes the complete degradation of cement and the formation of CaSO{sub 4}. Sulfuric acid is particularly useful because it produces a leachate that is amenable to conventional ion exchange technology for the separation and recovery of uranium. (author)

  13. Chemical Studies on the treatment and Conditioning of Radioactive Liquid Waste Using Combined Processes

    International Nuclear Information System (INIS)

    El-Masry, E.H.

    2004-01-01

    Natural inorganic exchanges were used to remove radioactive isotopes cesium, Cobalt and europium using coagulant zinc sulfate as coagulant from low level liquid radioactive waste. the highest percent of removal was obtained in the order asswanlly (85.5%), bentonite (82.2%) and sandstone (65.4%) for the removal of cesium . the same order of removal percent was detected for the removal of cobalt (92.5,91.2,90.6%) and europium (90.6,90.8,90.2%) for asswanlly, bentonite and sandstone respectively

  14. Investigations of Baltic See radioactivity within 1976-1980

    International Nuclear Information System (INIS)

    Weiss, D.; Lyonnig, M.; Tille, J.; Gzhibovska, D.; Tomchak, Ya.; Gedeonov, L.I.; Gusev, D.I.; Ivanova, L.M.; Pavlovskij, O.A.; Stepanova, V.D.

    1983-01-01

    The report presents summary of data on the Baltic Sea radioactive contamination obtained in DDR, PPR and the USSR within 1976-1980. The seawater, sediments and aquatic plants and animals were investigated. The distribution of strontium-90 and cesium-137 isotopes is given both for the open sea and its gulfs. Tendency towards strontium-90 concentration decrease is noted though cesium-137 concentration rise was observed in 1980 due to radioactive and polluted water ingress from the Northern Sea. In a number of points, except western regions in the vicinity of the Northern Sea, uniform distributions of strontium-90 and cesium-137 concentations versus depth were established. The radionuclide contents in water, sediments and aquatic organisms of Greifswald and Finland gulfs where Nuclear Power Plants are located on the seashore were found to be the same as in the open sea. The dependence of strontium-90 and especially cesium-137 sorption on the sediments composition has been noticed. In 1980 DDR presented data on tritium content in both near-surface and deep waters. Poland has carried out the first investigations of plutonium-239 and 240 content in the sediments. The dynamic behaviour of strontium-90 and cesium-137 concentrations in the Baltic Sea water within 1959-1980 has been reviewed. Data on strontium-90 and cesium-137 content in fishes and plants are given. On this basis the dose commitmments for population were estimated. 19 refs.; 27 tabs.; 6 figs

  15. Cesium levels in foodstuffs fall slowly

    International Nuclear Information System (INIS)

    Rantavaara, A.

    1994-01-01

    Since spring 1986, radioactive decay has reduced the total amount of radioactive cesium 137 in the Finnish environment, originating in Chernobyl, by 17 per cent. The cesium content in fish keeps falling at a diminishing rate, depending on the species of fish and environmental factors. The use of fish from lakes need not be restricted anymore. The cesium contents of game, mushrooms and wild berries have remained steady for some years now. The same is true for agricultural produce. The contents in milk and meat still keep falling slowly. Most of the cesium ingested by finns comes from fish, then from game, reindeer and gathered foods; the lowest amounts are received from agricultural products. (orig.)

  16. Extraction of cesium from acid solutions

    International Nuclear Information System (INIS)

    Katykhin, G.S.; Simonov, A.S.

    1983-01-01

    The extraction of cesium from acidic solutions is studied. Halogen-substituted carboxylic acids were chosen for the aqueous phase and nitrobenzene the diluent. The distribution coefficients are determined by the use of radioactive tracers 134 Cs and 137 Cs. It is believed that large singly charged anions of strong acids are necessary for the extraction of cesium. Metal halide acids are selected for supplying the anions

  17. Study of soil erosion dynamics on the arable lands of Lublin Upland using isotope techniques (137Cs)

    International Nuclear Information System (INIS)

    Zglobicki, W.; Reszka, M.

    2002-01-01

    One of the consequences of agricultural activity are changes of significant element of the environment, that is terrain relief. Since sixties the radioactive isotope of cesium, 137 Cs, is applied in the examination of the dynamics of the erosion processes. This method is based on the idea that the circulation of this isotope in the environment accompanies to physical transport of soil. Studies proved that cesium is firmly bond by adsorption complex of the soil. Chemical and biochemical processes have limited influence on the transportation of the cesium. By the examination of the horizontal changes of the total cesium activity one can determine a type and intensity of the processes responsible for its migration and thus the migration of the soil particles

  18. Simulation Studies of Diffusion-Release and Effusive-Flow of Short-Lived Radioactive Isotopes

    CERN Document Server

    Zhang, Yan; Kawai, Yoko

    2005-01-01

    Delay times associated with diffusion release from targets and effusive-flow transport of radioactive isotopes to ion sources are principal intensity limiters at ISOL-based radioactive ion beam facilities, and simulation studies with computer models are cost effective methods for designing targets and vapor transport systems with minimum delay times to avoid excessive decay losses of short lived ion species. A finite difference code, Diffuse II, was recently developed at the Oak Ridge National Laboratory to study diffusion-release of short-lived species from three principal target geometries. Simulation results are in close agreement with analytical solutions to Fick’s second equation. Complementary to the development of Diffuse II, the Monte-Carlo code, Effusion, was developed to address issues related to the design of fast vapor transport systems. Results, derived by using Effusion, are also found to closely agree with experimental measurements. In this presentation, the codes will be used in conc...

  19. Process for recovering cesium from cesium alum

    International Nuclear Information System (INIS)

    Mein, P.G.

    1984-01-01

    Cesium is recovered from cesium alum, CsAl(SO 4 ) 2 , by a two-reaction sequence in which the cesium alum is first dissolved in an aqueous hydroxide solution to form cesium alum hydroxide, CsAl(OH) 3 , and potassium sulfate, K 2 SO 4 . Part of the K 2 SO 4 precipitates and is separated from the supernatant solution. In the second reaction, a water-soluble permanganate, such as potassium permanganate, KMnO 4 , is added to the supernatant. This reaction forms a precipitate of cesium permanganate, CsMnO 4 . This precipitate may be separated from the residual solution to obtain cesium permanganate of high purity, which can be sold as a product or converted into other cesium compounds

  20. Sorption of cesium on titanium and zirconium phosphates

    International Nuclear Information System (INIS)

    Lebedev, V.N.; Mel'nik, N.A.; Rudenko, A.V.

    2003-01-01

    Titanium and zirconium phosphates were prepared from mineral raw materials of the Kola Peninsula. Their capability to recover cesium cations from the model solutions and liquid radioactive waste (LRW) was studied. Titanium phosphate prepared from solutions formed by titanite breakdown demonstrates greater distribution coefficients of cesium as compared to zirconium phosphate. Titanium phosphate as a cheaper agent featuring greater sorption capacity was recommended for treatment of LRW to remove cesium [ru

  1. Cesium-137

    International Nuclear Information System (INIS)

    Ammerich, Marc; Frot, Patricia; Gambini, Denis-Jean; Gauron, Christine; Moureaux, Patrick; Herbelet, Gilbert; Lahaye, Thierry; Pihet, Pascal; Rannou, Alain

    2014-06-01

    This sheet belongs to a collection which relates to the use of radionuclides essentially in unsealed sources. Its goal is to gather on a single document the most relevant information as well as the best prevention practices to be implemented. These sheets are made for the persons in charge of radiation protection: users, radioprotection-skill persons, labor physicians. Each sheet treats of: 1 - the radio-physical and biological properties; 2 - the main uses; 3 - the dosimetric parameters; 4 - the measurement; 5 - the protection means; 6 - the areas delimitation and monitoring; 7 - the personnel classification, training and monitoring; 8 - the effluents and wastes; 9 - the authorization and declaration administrative procedures; 10 - the transport; and 11 - the right conduct to adopt in case of incident or accident. This sheet deals specifically with Cesium-137

  2. Study of the Production of Radioactive Isotopes through Cosmic Muon Spallation in KamLAND

    Energy Technology Data Exchange (ETDEWEB)

    KamLAND Collaboration; Abe, S.; Enomoto, S.; Furuno, K.; Gando, Y.; Ikeda, H.; Inoue, K.; Kibe, Y.; Kishimoto, Y.; Koga, M.; Minekawa, Y.; Mitsui, T.; Nakajima, K.; Nakajima, K.; Nakamura, K.; Nakamura, M.; Shimizu, I.; Shimizu, Y.; Shirai, J.; Suekane, F.; Suzuki, A.; Takemoto, Y.; Tamae, K.; Terashima, A.; Watanabe, H.; Yonezawa, E.; Yoshida, S.; Kozlov, A.; Murayama, H.; Busenitz, J.; Classen, T.; Grant, C.; Keefer, G.; Leonard, D. S.; McKee, D.; Piepke, A.; Banks, T. I.; Bloxham, T.; Detwiler, J. A.; Freedman, S. J.; Fujikawa, B. K.; Gray, F.; Guardincerri, E.; Hsu, L.; Ichimura, K.; Kadel, R.; Lendvai, C.; Luk, K.-B.; O' Donnell, T.; Steiner, H. M.; Winslow, L. A.; Dwyer, D. A.; Jillings, C.; Mauger, C.; McKeown, R. D.; Vogel, P.; Zhang, C.; Berger, B. E.; Lane, C. E.; Maricic, J.; Miletic, T.; Batygov, M.; Learned, J. G.; Matsuno, S.; Pakvasa, S.; Foster, J.; Horton-Smith, G. A.; Tang, A.; Dazeley, S.; Downum, K. E.; Gratta, G.; Tolich, K.; Bugg, W.; Efremenko, Y.; Kamyshkov, Y.; Perevozchikov, O.; Karwowski, H. J.; Markoff, D. M.; Tornow, W.; Heeger, K. M.; Piquemal, F.; Ricol, J.-S.; Decowski, M. P.

    2009-06-30

    Radioactive isotopes produced through cosmic muon spallation are a background for rare event detection in {nu} detectors, double-beta-decay experiments, and dark-matter searches. Understanding the nature of cosmogenic backgrounds is particularly important for future experiments aiming to determine the pep and CNO solar neutrino fluxes, for which the background is dominated by the spallation production of {sup 11}C. Data from the Kamioka Liquid scintillator Anti-Neutrino Detector (KamLAND) provides valuable information for better understanding these backgrounds, especially in liquid scintillator, and for checking estimates from current simulations based upon MUSIC, FLUKA, and Geant4. Using the time correlation between detected muons and neutron captures, the neutron production yield in the KamLAND liquid scintillator is measured to be (2.8 {+-} 0.3) x 10{sup -4} n/({mu} {center_dot} (g/cm{sup 2})). For other isotopes, the production yield is determined from the observed time correlation related to known isotope lifetimes. We find some yields are inconsistent with extrapolations based on an accelerator muon beam experiment.

  3. Review of Cyclotrons for the Production of Radioactive Isotopes for Medical and Industrial Applications

    Science.gov (United States)

    Schmor, Paul

    2011-02-01

    Radioactive isotopes are used in a wide range of medical, biological, environmental and industrial applications. Cyclotrons are the primary tool for producing the shorter-lived, proton-rich radioisotopes currently used in a variety of medical applications. Although the primary use of the cyclotron-produced short-lived radioisotopes is in PET/CT (positron emission tomography/computed tomography) and SPECT (single photon emission computed tomography) diagnostic medical procedures, cyclotrons are also producing longer-lived isotopes for therapeutic procedures as well as for other industrial and applied science applications. Commercial suppliers of cyclotrons are responding by providing a range of cyclotrons in the energy range of 3-70MeV for the differing needs of the various applications. These cyclotrons generally have multiple beams servicing multiple targets. This review article presents some of the applications of the radioisotopes and provides a comparison of some of the capabilities of the various current cyclotrons. The use of nuclear medicine and the number of cyclotrons supplying the needed isotopes are increasing. It is expected that there will soon be a new generation of small "tabletop" cyclotrons providing patient doses on demand.

  4. Design of a positional tracking and radiological alarm system for transportation of radioactive isotopes

    International Nuclear Information System (INIS)

    Saindane, Shashank; Pujari, R.N.; Narsaiah, M.V.R.; Chaudhury, Probal; Pradeepkumar, K.S.

    2016-01-01

    The safety aspects during the transport of radioactive material have to ensure that even in event of accident the potential of radiation exposure to public is extremely small. Continuous monitoring and online data transfer to emergency control room will strengthen the emergency preparedness to response to any such accident during transport of radioactive material. The paper presents the combined application of Geographical Information Systems (GIS), Global Positioning System (GPS), General Packet Radio Service (GPRS) and the Internet for tracking the shipment vehicle transporting radioactive isotopes for use in the medical industry. The key features of the prototype system designed are realtime radiological status update along with photo snap of the shipping flask at predefined interval along with positional coordinates, GIS platform and a web-based user interface. The system consists of a GM based radiation monitoring device (RMD) along with a LAN camera, GPS for tracking the shipment vehicle, a communications server, a web-server, a database server, and a map server. The RMD and tracking device mounted in the shipment vehicle collects location and radiological information on real-time via the GPS. This information is transferred continuously through GPRS to a central database. The users will be able to view the current location of the vehicle via a web-based application

  5. Study on Method of Asphalt Density Measurement Using Low Level Radioactive Isotope

    International Nuclear Information System (INIS)

    Chung, Jin-young; Kim, Jung-hoon; Whang, Joo-ho

    2008-01-01

    The fundamental cause of damage to road pavement is insufficient management of asphalt density during construction. Currently, asphalt density in Korea is measured in a laboratory by extracting a core sample after construction. This method delays the overall time of measurement and therefore it is difficult to achieve real-time density management. Using a radioactive isotope for measuring asphalt density during construction reduces measuring time thus enabling realtime measurement. Also, it is provided reliable density measurement to achieve effective density management at work sites. However, existing radiological equipment has not been widely used because of management restrictions and regulations due to the high radiation dose. In this study, we employed a non-destructive method for density measurement. Density is measured by using a portable gamma-ray backscatter device having a radioactivity emission of 100 μCi or less (notice No. 2002-23, Ministry of Science and Technology, standards on radiation protection, etc.), a sealed radioactive source subject to declaration

  6. Ion beam production and study of radioactive isotopes with the laser ion source at ISOLDE

    Science.gov (United States)

    Fedosseev, Valentin; Chrysalidis, Katerina; Day Goodacre, Thomas; Marsh, Bruce; Rothe, Sebastian; Seiffert, Christoph; Wendt, Klaus

    2017-08-01

    At ISOLDE the majority of radioactive ion beams are produced using the resonance ionization laser ion source (RILIS). This ion source is based on resonant excitation of atomic transitions by wavelength tunable laser radiation. Since its installation at the ISOLDE facility in 1994, the RILIS laser setup has been developed into a versatile remotely operated laser system comprising state-of-the-art solid state and dye lasers capable of generating multiple high quality laser beams at any wavelength in the range of 210-950 nm. A continuous programme of atomic ionization scheme development at CERN and at other laboratories has gradually increased the number of RILIS-ionized elements. At present, isotopes of 40 different elements have been selectively laser-ionized by the ISOLDE RILIS. Studies related to the optimization of the laser-atom interaction environment have yielded new laser ion source types: the laser ion source and trap and the versatile arc discharge and laser ion source. Depending on the specific experimental requirements for beam purity or versatility to switch between different ionization mechanisms, these may offer a favourable alternative to the standard hot metal cavity configuration. In addition to its main purpose of ion beam production, the RILIS is used for laser spectroscopy of radioisotopes. In an ongoing experimental campaign the isotope shifts and hyperfine structure of long isotopic chains have been measured by the extremely sensitive in-source laser spectroscopy method. The studies performed in the lead region were focused on nuclear deformation and shape coexistence effects around the closed proton shell Z = 82. The paper describes the functional principles of the RILIS, the current status of the laser system and demonstrated capabilities for the production of different ion beams including the high-resolution studies of short-lived isotopes and other applications of RILIS lasers for ISOLDE experiments. This article belongs to the Focus on

  7. Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center, Khartoum

    International Nuclear Information System (INIS)

    Ahmed, Amel Bushra Abaker

    2001-01-01

    Evaluation of management of radioactive waste in nuclear medicine department of radiation and isotopes center in Khartoum, Sudan, was conducted using radiation survey meter. The purpose of this study is to provide protection of workers, patients, co patients, an the environment by introducing good practice in management of radioactive waste generated in this lab. In this work measurement of radiation effective dose at different locations in the department were carried out. These locations were selected around the radioactive liquid and solid waste disposal position. It was found that the effective doses per year from radioactive wastes obtained through this work using the survey meter RDS-120 at these locations, are 1.47 mSv/y at the neighbouring patients room, 5.47 mSv/y at the hot lab., 0.09 mSv/y at the neighbouring toilet, 0.321 mSv/y at the water closet, and 1.4 mSv/y at the place down water closet. The results obtained shows that the dose levels waste at the location not exceed the recommended dose limits for workers 20 mSv/y, that set by basic safety standards (Bss 115) which published by the international atomic energy agency. Also it s comply with the national regulation, regulation on basic radiation protection requirement and dose limits 1996, issued by sudan atomic energy commission act 1996. The annual dose calculated for the patients and co-patients at rooms around the nuclear medicine department, the results shows that dose are fairly high. Measure should taken to improve the waste management in the department for better protection of workers, patients and co patients. (Author)

  8. Cesium-137 global fallout into the Ob river basin and its influence on the Kara sea contamination - Weapons fallout cesium-137 in the Ob' catchment landscapes and its influence on radioactive contamination of the Kara sea: Western Siberia, Russia

    Energy Technology Data Exchange (ETDEWEB)

    Semenkov, Ivan N.; Miroshnikov, Alexey Yu. [The Organization of Russian Academy of Sciences Institute of geology of ore deposits, petrography, mineralogy and geochemistry Russian Academy of Sciences (Russian Federation)

    2014-07-01

    There are several high level {sup 137}Cs anomaly zones detected in the deposits of the SW part of the Kara Sea. These anomaly zones were formed in the Ob' and the Enisey river estuaries due to the geochemical 'river-sea' boarder barrier. Level of radiocaesium specific activity reaches 120 Bq*kg{sup -1} in the deposits from these zones. Radiochemical enterprises occur in the both river basins. Their activity results in caesium-137 transfer into the river net. Vast area is contaminated by {sup 137}Cs after nuclear weapons in Semipalatinsk test-site and Kyshtym disaster in the Ob' river basin. Moreover, caesium comes to the Ob' and the Enisey river basins with global atmospheric fallout. The inflow of global fallout caesium-137 to the catchments is 660 kCi (320 kCi including radioactive decay) that is 4 times higher than {sup 137}Cs emission due to Fukushima disaster. Therefore, these river basins as any other huge catchment are an important sources of radioactive contamination of the Arctic Ocean. The aim of our research is to study behavior of global fallout caesium-137 in the landscapes of the Ob and the Enisey river basins. We studied caesium-137 behavior on the example of first order catchments in taiga, wetland, forest-steppe, steppe, and semi-arid landscapes. Geographic information system (GIS) was made. The tenth-order catchments (n=154, Horton coding system) shape 20-groups due to topsoil properties controlling cesium mobility. Eleven first-order basins, characterized 7 groups of tenth order catchments, were studied. And 700 bulk-core soil samples were collected in 2011-2013. Cesium runoff is calculated for 3 first-order river basins in taiga and forest-steppe landscapes. Storage of global fallout caesium-137 declines from undisturbing taiga first-order river basin (90% of cumulative fallout including radioactive decay)> arable steppe and fores-steppe (70 - 75%)> undisturbing wetland (60%). Caesium-137 transfer is high in arable lands

  9. Process for recovering cesium from cesium alum

    International Nuclear Information System (INIS)

    Mein, P.G.

    1984-01-01

    Cesium is recovered from cesium alum, CsAl(SO 4 ) 2 , by an aqueous conversion and precipitation reaction using a critical stoichiometric excess of a water-soluble permanganate to form solid cesium permanganate (CsMnO 4 ) free from cesium alum. The other metal salts remain in solution, providing the final pH does not cause hydroxides of aluminium or iron to form. The precipitate is separated from the residual solution to obtain CsMnO 4 of high purity

  10. Environmental radioactivity in Canada 1987

    International Nuclear Information System (INIS)

    1988-01-01

    The radiological surveillance program of the Department of National Health and Welfare is conducted for the purpose of determining levels of environmental radioactivity in Canada and assessing the resulting population exposures. A study was initiated to evaluate the contamination by cesium-137, of caribou, a major source of food in northern communities. Work on development of methods proceeded for the determination of radon, carbon-14, polonium-210, radium-228 and isotopic uranium in samples. Monitoring continued of fallout contamination from Chernobyl of imported foods. All measurements made during 1987 are below the limits recommended by the International Commission on Radiological Protection

  11. New Applications of Cosmogenic Radioactive Isotopes to Study Water Travel Times

    Science.gov (United States)

    Visser, A.; Thaw, M.; Deinhart, A.; Bibby, R. K.; Esser, B.

    2017-12-01

    The travel time of water moving through a landscape influences nutrient dynamics and biogeochemical cycles. Constraining water travel times helps to understand the functioning of the critical zone. Water travel times cannot be observed directly but can be constrained by measurements of cosmogenic radioactive isotopes. We studied a small (4.6 km2) subalpine (1660-2117 m) catchment in a Mediterranean climate (8 °C, 1200 mm/yr) in the California Sierra Nevada to assess subsurface water storage dynamics and investigate flow paths and flow velocities. We analyzed a combination of three cosmogenic radioactive isotopes with half-lives varying from 87 days (sulfur-35), 2.6 years (sodium-22) to 12.3 years (tritium) in precipitation and stream samples. Water stable isotopes and solute chemistry aided the interpretation of the cosmogenic isotopes. Tritium samples (1L) are analyzed by noble gas mass spectrometry after helium-3 accumulation. Samples for sulfur-35 and sodium-22 are collected by processing 20-1000 L of water through an anion and cation exchange column in-situ. Sulfur-35 is analyzed by liquid scintillation counting after chemical purification and precipitation. Sodium-22 is analyzed by gamma counting after eluting the cations into a 4L Marinelli beaker. Monthly collected precipitation samples show variability of deposition rate for tritium and sulfur-35. Sodium-22 levels in cumulative yearly precipitation samples are consistent with recent studies in the US and Japan. The observed variability of deposition rates complicates direct use as decaying age tracers. The level and variability of tritium in monthly stream samples indicate a mean residence time on the order of 10 years and only small contributions of younger water during high flow conditions. Sulfur-35 and sodium-22 concentrations were critically interpreted considering possible uptake by vegetation and cation exchange. Detections of sodium-22 confirm a small fraction of younger (water. Low concentrations

  12. Decorporation of cesium-137; Decorporation du cesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Le Fleche, Ph; Destombe, C; Grasseau, A; Mathieu, J; Chancerelle, Y; Mestries, J C [GMR, Direction des Recherches, Etudes et Techniques, 94 - Arcueil (France)

    1998-12-31

    Cesium radio-isotopes, especially cesium-137 ({sup 137}Cs) are among the radionuclides of main importance produced by a fission reaction in reactor or a nuclear weapon explosion. In the environment, {sup 137}Cs is a major contaminant which can cause severe {beta}, {gamma}irradiations and contaminations. {sup 137}Cs is distributed widely and relatively uniformly throughout the body with the highest concentration in skeletal muscles. A treatment becomes difficult afterwards. The purposes of this report are Firstly to compare the Prussian blue verses cobalt and potassium ferrocyanide (D.I. blue) efficiency for the {sup 137}Cs decorporation and secondly to assess a chronological treatment with D.I. blue. (author)

  13. Decorporation of cesium-137; Decorporation du cesium-137

    Energy Technology Data Exchange (ETDEWEB)

    Le Fleche, Ph.; Destombe, C.; Grasseau, A.; Mathieu, J.; Chancerelle, Y.; Mestries, J.C. [GMR, Direction des Recherches, Etudes et Techniques, 94 - Arcueil (France)

    1997-12-31

    Cesium radio-isotopes, especially cesium-137 ({sup 137}Cs) are among the radionuclides of main importance produced by a fission reaction in reactor or a nuclear weapon explosion. In the environment, {sup 137}Cs is a major contaminant which can cause severe {beta}, {gamma}irradiations and contaminations. {sup 137}Cs is distributed widely and relatively uniformly throughout the body with the highest concentration in skeletal muscles. A treatment becomes difficult afterwards. The purposes of this report are Firstly to compare the Prussian blue verses cobalt and potassium ferrocyanide (D.I. blue) efficiency for the {sup 137}Cs decorporation and secondly to assess a chronological treatment with D.I. blue. (author)

  14. Removal of cesium radioisotopes from solutions using granulated zeolites

    International Nuclear Information System (INIS)

    Bronic, J.; Subotic, B.

    1991-01-01

    The influence of type of zeolite and the flow rate of solution through the column on the removal efficiency of radioactive cesium ions from solution has been investigated. The analysis of the change in the concentration of cesium ions in the solutions and distribution of cesium ions in the column fillings (granulated zeolites), after passing the solutions through the columns filled with various granulated zeolites (zeolite 4A, zeolite 13X, synthetic mordenite) was performed. On the basis of the results of this study, the conditions for the most efficient removal of cesium ions from solutions have been discussed. (author) 35 refs.; 9 figs.; 1 tab

  15. Total cross section measurement of radioactive isotopes with a thin beam neutron spectrometer

    International Nuclear Information System (INIS)

    Razbudej, V.F.; Vertebnyj, V.P.; Padun, G.S.; Muravitskij, A.V.

    1975-01-01

    The method for measuring the neutron total cross sections of radioactive isotopes by a time-of-flight spectrometer with a narrow (0.17 mm in diameter) beam of thermal neutrons is described. The distinguishing feature of this method is the use of capillary samples with a small amount of substance (0.05-1.0 mg). The energy range is 0.01-0.3 eV. The total cross sections of irradiated samples of sub(153)Eu and sub(151)Eu are measured. From them are obtained the cross sections of sub(152)Eu (Tsub(1/2)=12.4 g) and of sub(154)E (Tsub(1/2)=8.6 yr); they equal 11400+-1400 and 1530+-190 barn at E=0.0253 eV. The cross section of the sub(152)Eu absorption for the thermal spectrum (T=333 K) is determined by the activation method; it is 8900+-1200 barn

  16. The future of the accelerator mass spectrometry of rare long-lived radioactive isotopes

    International Nuclear Information System (INIS)

    Litherland, A.E.

    1990-01-01

    Accelerators, originally designed for nuclear physics, can be added to mass spectrometric apparatus to increase the sensitivity so that isotope ratios in the range 10 -12 to 10 -15 can be measured routinely. This significant improvement of high-sensitivity mass spectrometry has been called Accelerator Mass Spectrometry. The present article addresses the basic principles of accelerator mass spectrometry and some recent applications which show its versatility. In particular, it is noted that accelerator mass spectrometry could play an increasing role in the measurement of the levels of long lived radioactivities in the environment, including the actinides, which result from human activities such as the use of nuclear power. To fulfill this promise, continued research and development is necessary to provide ion sources, various types of heavy ion accelerators and peripheral magnetic and electric analysers. (N.K.)

  17. The beam diagnostic instruments in Beijing radioactive ion-beam facilities isotope separator on-line

    International Nuclear Information System (INIS)

    Ma, Y.; Cui, B.; Ma, R.; Tang, B.; Chen, L.; Huang, Q.; Jiang, W.

    2014-01-01

    The beam diagnostic instruments for Beijing Radioactive Ion-beam Facilities Isotope Separator On-Line are introduced [B. Q. Cui, Z. H. Peng, Y. J. Ma, R. G. Ma, B. Tang, T. Zhang, and W. S. Jiang, Nucl. Instrum. Methods 266, 4113 (2008); T. J. Zhang, X. L. Guan, and B. Q. Cui, in Proceedings of APAC 2004, Gyeongju, Korea, 2004, http://www.jacow.org , p. 267]. For low intensity ion beam [30–300 keV/1 pA–10 μA], the beam profile monitor, the emittance measurement unit, and the analyzing slit will be installed. For the primary proton beam [100 MeV/200 μA], the beam profile scanner will be installed. For identification of the nuclide, a beam identification unit will be installed. The details of prototype of the beam diagnostic units and some experiment results will be described in this article

  18. Method for determination of radioactive iodine isotopes in environmental objects and biologic materials

    International Nuclear Information System (INIS)

    Dubynin, O.D.; Pogodin, R.I.

    1981-01-01

    The method proposed for determination of radioactive iodine isotopes content in environmental objects and biologic materials is based on the extraction of iodine with carbon tetrachloride and subsequent precipitation of bismuthyl iodine (BiOI) in perchloric medium. Sample preparation for analysis is carried out using conventional alkaline ashing methods. Quantitative iodine separation is hampered if macroquantities of Cl - , Br - , SO 4 2 - , SO 8 2 - , Cr 2 O 7 2 - and other ions are present in the solution. Iodine extraction is carried out before its precipitation. Separated iodine preparation activity is measured using scintillation (NaI) Tl gamma spectrometer. The method's sensitivity when measuring iodine-131 preparations makes up 0.07 Bq per 1 sample with the error +-25 %

  19. A new method for the labelling of proteins with radioactive arsenic isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Jennewein, M. [Institute of Nuclear Chemistry, Johannes Gutenberg University of Mainz, Fritz-Strassmann-Weg 2, 55128 Mainz (Germany); Hermanne, A. [VUB Cyclotron, University of Brussels, Laarbeeklaan 103, 1090 Brussels (Belgium); Mason, R.P. [Department of Radiology, Advanced Radiological Sciences, University of Texas Southwestern Medical Center at Dallas, Dallas, Texas (United States); Thorpe, P.E. [Department of Pharmacology and Simmons and Hamon Cancer Centers, University of Texas Southwestern Medical Center at Dallas, Dallas, TX (United States); Roesch, F. [Institute of Nuclear Chemistry, Johannes Gutenberg University of Mainz, Fritz-Strassmann-Weg 2, 55128 Mainz (Germany)]. E-mail: frank.roesch@uni-mainz.de

    2006-12-20

    Radioarsenic labelled radiopharmaceuticals could be a valuable asset to positron emission tomography. In particular, the long half-lives of {sup 72}As (T{sub 1/2}=26h) and {sup 74}As (T{sub 1/2}=17.8d) allow to investigate slow physiological or metabolical processes, like the enrichment and distribution of monoclonal antibodies (mab) in tumour tissue. In this work, a new method for the labelling of proteins with various radioactive arsenic isotopes was developed. For this purpose, two proteins, namely a chimeric IgG{sub 3} monoclonal antibody, ch3G4, directed against anionic phospholipids, and Rituxan (Rituximab), were labelled as a proof of principle with no-carrier-added radioarsenic isotopes ({sup 74}As and {sup 77}As). The developed labelling chemistry gives high yields (>99.9%), is reliable and could easily be transferred to automated labelling systems in a clinical environment. At least for the mab used in this work, this route of radioarsenic labelling does not affect the immunoreactivity of the product. The arsenic label stays stable for up to 72h at the molecular mass of the monoclonal antibody, which is in particular relevant to follow the pharmacology and pharmacokinetics of the labelled mab for several days.

  20. Determination of stable and radioactive isotopes in rain water in Sahel in 1975 and 1976

    International Nuclear Information System (INIS)

    Baudet, J.; Abi, B.

    1979-01-01

    The problem of desertification in Africa incites to materialize the circuit of the water vapour between its main source, the Gulf of Guinea, and its precipitation site. Some rainwater samples have been collected in Ouagadougou in 1975 and 1976 during the rainy season. The dosage of the stable isotopes D and O 18 and radioactive isotope T shows that in 1975, a year with a general rain deficit, the rain was formed in a continental air mass. On the contrary, in 1976, a year with excess rain, the rain was formed in a maritime air mass. A study of the wind flows at 600, 900, 1500 and 2100 m shows that in 1975 the monsoon penetration is limited to the bottom of the Gulf of Guinea facing Cameroons, while in 1976 it entered the African Continent through the whole Gulf Coast, from Senegal to Cameroons. In 1976, the monsoon went up in latitude 3 0 to 5 0 more to the north than in 1975 [fr

  1. Isotope hydrogeological study of the underground repository for radioactive wastes at Morsleben

    International Nuclear Information System (INIS)

    Gellermann, R.; Hebert, D.

    1991-01-01

    As a contribution of safety assessment of the underground repository for radioactive wastes (ERA) in Morsleben isotope investigations in the hydrosphere has been carried out. The measured tritium concentrations of brines infiltrating into the mine cannot be interpreted in a conventional way due to contamination of mine air with tritium. However, modelling the isotope exchange allows conclusions regarding the water balance of the dripping brines. A complex interpretation which includes hydrogeochemical data results in a qualitative assessment of the infiltrating brines in regard to their hazard potential. An acute danger cannot be derived from the data available up to the present. The natural input of cosmogenic radionuclides (tritium, radiocarbon) into the aquifers above the salt level permits to study radionuclide migration at the ERA site. Tritium from the nuclear weapon tests is detectable up to a depth of 50 m below groundwater level with a maximum in about 20 m. From these data infiltration velocities of 1.6 m/a at maximum and 0.9 m/a in average are derived. The 14 C measurements of samples from more than 100 m depth yield model ages in the order of 10 4 years. This indicates a significantly reduced groundwater dynamic in the deeper horizons. (orig.) [de

  2. Techniques and problems in studying intestinal absorption with radioactive isotopes in children

    International Nuclear Information System (INIS)

    James, W.P.T.; Waterlow, J.C.

    1976-01-01

    Radioactive isotopes give substantial promise for assisting the study of gastrointestinal absorption in children in that they allow reduction or elimination of the collection of blood, urine and faeces specimens. These operations are particularly difficult and unreliable in infants, on whom greatest interest in paediatric gastroenterology is centred in the tropics. Here intestinal malabsorption is most commonly associated with malnutrition, lactose intolerance, gastroenteritis, parasitic infestation and iron-deficiency anaemia. Two general techniques that have been employed are whole-body counting and analyses of 14 CO 2 exhaled in the breath after the feeding of 14 C-labelled nutrients. The former is advantageous if radionuclides suitable for the test at hand exist; the latter may be hard to interpret because of problems in the distribution and metabolism of the nutrient and intermediary products. Proper selection and understanding of the tests is particularly important in paediatric work, where the use of radioactive tracer techniques is unacceptable merely for the convenience of the investigator. (author)

  3. Travel Times of Water Derived from Three Naturally Occurring Cosmogenic Radioactive Isotopes

    Science.gov (United States)

    Visser, Ate; Thaw, Melissa; Deinhart, Amanda; Bibby, Richard; Esser, Brad

    2017-04-01

    Hydrological travel times are studied on scales that span six orders of magnitude, from daily event water in stream flow to pre-Holocene groundwater in wells. Groundwater vulnerability to contamination, groundwater surface water interactions and catchment response are often focused on "modern" water that recharged after the introduction of anthropogenic tritium in precipitation in 1953. Shorter residence times are expected in smaller catchments, resulting in immediate vulnerability to contamination. We studied a small (4.6 km2) alpine (1660-2117 m) catchment in a Mediterranean climate (8 ˚ C, 1200 mm/yr) in the California Sierra Nevada to assess subsurface storage and investigate the response to the recent California drought. We analyzed a combination of three cosmogenic radioactive isotopes with half-lives varying from 87 days (sulfur-35), 2.6 years (sodium-22) to 12.3 years (tritium) in precipitation and stream samples. Tritium samples (1 L) are analyzed by noble gas mass spectrometry after helium-3 accumulation. Samples for sulfur-35 and sodium-22 are collected by processing 20-1000 L of water through an anion and cation exchange column in-situ. Sulfur-35 is analyzed by liquid scintillation counting after chemical purification and precipitation. Sodium-22 is analyzed by gamma counting after eluting the cations into a 4L Marinelli beaker. Monthly collected precipitation samples show variability of deposition rate for tritium and sulfur-35. Sodium-22 levels in cumulative yearly precipitation samples are consistent with recent studies in the US and Japan. The observed variability of deposition rates complicates direct estimation of stream water age fractions. The level and variability of tritium in monthly stream samples indicate a mean residence time on the order of 10 years and only small contributions of younger water during high flow conditions. Estimates of subsurface storage are in agreement with estimates from geophysical studies. Detections of sodium-22

  4. Environmental isotopes assist in the site assessment of Vaalputs radioactive waste disposal facility

    International Nuclear Information System (INIS)

    Verhagen, B.T.; Levin, M.

    1986-01-01

    The first South African nuclear waste disposal facility is to be sited in an arid environment with an average annual rainfall of about 78mm. The ground water might therefore be virtually stationary, making the geohydrology of the area crucial in the assessment of radionuclide dispersal difficult to study with standard hydraulic methods. Environmental isotopes, which label the water itself and some of its dissolved constituents are able to give synoptic information about the ground water; from this, some projections about future mobility can be made. Tritium profiles in the unsaturated zone show the limited extent of rain water infiltration, which generally extends down to 3-4 metres, with sporadic evidence of deeper penetration through cracks and rootholes in the thick clay cover. Soil moisture therefore seems to occur in tightly bound and more mobile components. This is confirmed by occasionally measurable tritium observed in the saturated zone. Radiocarbon in the ground water cannot be simply interpreted on account of the nature of the granite aquifer. Although suggesting ages of several thousands of years, radiocarbon proves that the water is not 'fossil' or derived from the last pluvial period, postulated to have occurred some 12 000 years ago. Recharge appears to be more ongoing and to occur periodically and locally as a result of outliers within the present climatological regime. Regional movement of ground water is however very limited, as spatial variations seen in the radiocarbon data of the ground water are non-systematic. These conclusions are supported by the distribution of the non-radioactive isotopes, such as oxygen-18

  5. Cesium-134 and cesium-137 in honey bees and cheese samples collected in the U. S. after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Ford, B C; Jester, W A; Griffith, S M; Morse, R A; Zall, R R; Lisk, D J; Burgett, D M; Bodyfelt, F W

    1988-01-01

    As a result of the Chernobyl accident on April 25, 1986, possible radioactive contamination of honey bees and cheese sampled in several areas of the United States were measured. Of bees collected in May and June of 1986 in both Oregon and New York, only those from Oregon showed detectable levels of cesium-134 (T1/2 = 2.05 years), a radionuclide which would have originated from the Chernobyl incident. Cheese produced in Oregon and New York before the accident showed only cesium-137 (T1/2 = 30.23 years) but cheese produced afterwards (May and September, 1986) in Oregon contained cesium-134. Cheese produced in Ohio and California at the time of the accident and thereafter contained only cesium-137. In general, the levels of radioactivity were higher in the West coast samples as compared to those taken in the East. The levels of radioactivity detected were considered to be toxicologically of no consequence.

  6. A hydrochemical and isotopic case study around a near surface radioactive waste disposal

    International Nuclear Information System (INIS)

    Szanto, Zs.; Svingor, E.; Futo, I.; Palcsu, L.; Molnar, M.; Rinyu, L.

    2007-01-01

    As part of the site characterisation program for the near surface radioactive waste treatment and disposal facility (RWTDF) at Puespoekszilagy, Hungary, water quality and environmental isotope investigations have been carried out. Water samples for major ion chemistry, tritium, 14 C and stable isotope ratio measurements (δ 18 O, δD, δ 34 S, δ 13 C) were taken quarterly from the observation wells, the streams and the precipitation during the period 1999-2001. The chemical composition of groundwaters presented a continuous transition from waters situated on one side to waters on the top and on the other slope of the disposal suggesting the mixing of the three hydrochemical ''endmembers''. Most of δD and δ 18 O data were situated between GMWL and LMWL (δD = 7.2 x δ 18 O - 1 permille) with Oligocene aquifer presenting recharge of Pleistocene origin and water on the top and the gentle slope of the hill presenting recharge of Holocene origin. δ 34 S values of dissolved sulphates varied in a wide range (-14.2 permille to +5.4 permille). The tritium in precipitation varied between 4.4 and 18.1 TU with an annual weighted average of 10 ± 0.3 TU. The streams showed larger fluctuations than the wells, but the changes of δ 18 O, δD and T were small compared to those in precipitation (showing seasonal variation). Stable isotope, tritium and radiocarbon data proved that the replenishment of groundwater is slow on the steeper side and the direction of water movement is toward the gentle slope of the hill. It was judged that this path is the one that is most likely to give rise to high doses and, therefore, was used in the hydrological modelling of the safety assessment that followed the present work. The possibility that there may also be transport through the unsaturated zone and systems of perched water tables in layers 1 and 2 to both the Szilagyi and Nemedi streams cannot be excluded; the transport along these pathways is likely to be intermittent. (orig.)

  7. A kinematic model to estimate the effective dose of radioactive isotopes in the human body for radiological protection

    Science.gov (United States)

    Sasaki, S.; Yamada, T.

    2013-12-01

    The great earthquake attacked the north-east area in Japan in March 11, 2011. The system of electrical facilities to control Fukushima Daiichi nuclear power station was completely destroyed by the following tsunamis. From the damaged reactor containment vessels, an amount of radioactive substances had leaked and been diffused in the vicinity of this station. Radiological internal exposure becomes a serious social issue both in Japan and all over the world. The present study provides an easily understandable, kinematic-based model to estimate the effective dose of radioactive substances in a human body by simplified the complicated mechanism of metabolism. International Commission on Radiological Protection (ICRP) has developed an exact model, which is well-known as a standard method to calculate the effective dose for radiological protection. However, owing to that the above method accord too much with the actual mechanism of metabolism in human bodies, it becomes rather difficult for non-professional people of radiology to gasp the whole images of the movement and the influences of radioactive substances in a human body. Therefore, in the present paper we propose a newly-derived and easily-understandable model to estimate the effective dose. The present method is very similar with the traditional and conventional hydrological tank model. Ingestion flux of radioactive substances corresponds to rain intensity and the storage of radioactive substances to the water storage in a basin in runoff analysis. The key of this method is to estimate the energy radiated from the radioactive nuclear disintegration of an atom by using classical theory of E. Fermi of beta decay and special relativity for various kinds of radioactive atoms. The parameters used in this study are only physical half-time and biological half-time, and there are no intentional and operational parameters of coefficients to adjust our theoretical runoff to observation of ICRP. Figure.1 compares time

  8. Secondary ion mass spectrometry and environment. SIMS as applied to the detection of stable and radioactive isotopes in marine organisms

    International Nuclear Information System (INIS)

    Chassard-Bouchaud, C.; Escaig, F.; Hallegot, P.

    1984-01-01

    Several marine species of economical interest, Crustacea (crabs and prawns) and Molluscs (common mussels and oysters) were collected from coastal waters of France: English Channel, Atlantic Ocean and Mediterranean Sea and of Japan. Microanalyses which were performed at the tissue and cell levels, using Secondary Ion Mass Spectrometry, revealed many contaminants; stable isotopes as well as radioactive actinids such as uranium were detected. Uptake, storage and excretion target organs were identified [fr

  9. The use of natural radioactive Isotopes in the determination of pollution sources of AL-Kabir AL-Shimali river

    International Nuclear Information System (INIS)

    Al-Masri, M. S.; Shwiekani, R.; Mamish, S.

    2012-01-01

    In the present research, variations of concentration levels of some natural radioactive isotopes (226 Ra, 210 Po,210 Pb, U and Th isotopes) and some trace elements (Cu, Zn, Pb, Cd) in water and sediments of AL-Kabir AL-Shimali river during the period of 2009-2010 have been studied. The samples were collected along the river from the asphalt factory to the end of the mouth of the river in the Mediterranean Sea. Results showed that concentrations of natural radioactive isotopes have been increased slightly in water and sediments of the river after the asphalt factory and after the factories area, while the concentrations of Rn in the river's water were low along the river except the waters of October 16, Lake Dam that reached a value of 341 mBq/l. These high concentrations in water and sediments of the AL-Kabir AL-Shimali River were due to discharges from the asphalt factory and other factories known to contain natural radioactive isotopes, indicating the possibility of using these isotopes in the determination of pollution sources of AL-Kabir AL-Shimali River. However, the measured concentrations are relatively low compared to the values reported in the world due to river water flow that dilute concentrations of these elements. On the other hand, measurements of trace elements (Cu,Zn,Pb,Cd) showed low concentrations in the waters of the river, with some increases in the concentrations in river sediments after the asphalt factory and the factories area , indicating the contribution of the factories outlets in this increase. The results were compared with the results of previous studies conducted on the Euphrates and the Orontes, where the comparison showed lower values in the AL-Kabir AL-Shimali river environment. (author)

  10. The use of natural radioactive isotopes in the determination of pollution sources of Al-Kabir Al-Shimali river

    International Nuclear Information System (INIS)

    ALmasri, M.; Shweikani, R.; Mamish, S.; Al-Haleem, M.A.; Al-Shamali, K.; Jerby, B.

    2010-10-01

    In the present research, variations of concentration levels of some natural radioactive isotopes ( 226 Ra, 210 Po, 210 Pb, U and Th isotopes) and some trace elements (Cu, Zn, Pb, Cd) in water and sediments of Al-Kabir Al-Shimali river during the period of 2009-2010 have been studied. The samples were collected along the river from the asphalt factory to the end of the mouth of the river in the Mediterranean Sea. Results showed that concentrations of natural radioactive isotopes have been increased slightly in water and sediments of the river after the asphalt factory and after the factories area, while the concentrations of Rn in the river's water were low along the river except the waters of October 16, Lake Dam that reached a value of 341mBq/l. These high concentrations in water and sediments of the Al-Kabir Al-Shimali River were due to discharges from the asphalt factory and other factories known to contain natural radioactive isotopes, indicating the possibility of using these isotopes in the determination of pollution sources of Al-Kabir Al-Shimali River. However, the measured concentrations are relatively low compared to the values reported in the world due to river water flow that dilute concentrations of these elements. On the other hand, measurements of trace elements (Cu,Zn,Pb,Cd) showed low concentrations in the waters of the river, with some increases in the concentrations in river sediments after the asphalt factory and the factories area , indicating the contribution of the factories outlets in this increase. The results were compared with the results of previous studies conducted on the Euphrates and the Orontes, where the comparison showed lower values in the Al-Kabir Al-Shimali river environment.(author)

  11. Cold valleys in the radioactive decay of 248-254Cf isotopes

    International Nuclear Information System (INIS)

    Biju, R.K.; Sahadevan, Sabina; Santhosh, K.P.; Joseph, Antony

    2008-01-01

    Based on the concept of cold valley in cold fission and fusion, we have investigated the cluster decay process in 248-254 Cf isotopes. In addition to alpha particle minima, other deep minima occur for S, Ar and Ca clusters. It is found that inclusion of proximity potential does not change the position of minima but minima become deeper. Taking Coulomb and proximity potential as interacting barrier for post-scission region, we computed half-lives and other characteristics for various clusters from these parents. Our study reveals that these parents are stable against light clusters and unstable against heavy clusters. Computed half-lives for alpha decay agree with experimental values within two orders of magnitude. The most probable clusters from these parents are predicted to be 46 Ar, 48,50 Ca which indicate the role of doubly or near doubly magic clusters in cluster radioactivity. Odd A clusters are found to be favorable for emission from odd A parents. Cluster decay model is extended to symmetric region and it is found that symmetric fission is also probable which stresses the role of doubly or near doubly magic 132 Sn nuclei. Geiger-Nuttal plots were studied for various clusters and are found to be linear with varying slopes and intercepts. (author)

  12. Possibility of wine dating using the natural Pb-210 radioactive isotope

    International Nuclear Information System (INIS)

    Hubert, Ph.; Pravikoff, M.S.; Gaye, J.

    2015-01-01

    To control the authenticity of an old wine without opening the bottle, we developed a few years ago a method based on the measurement of the 137 Cs activity. However, for recent vintages, the 137 Cs activity drops to far too low values (most of the time less than 10 mBq/L for a 10-year-old wine) for this method to perform correctly. In this paper we examine the possibility to date wines using the natural radio-element 210 Pb which has a 22-year period. This new method we propose implies the opening of the bottle and the follow-on destruction of the wine itself, which means that it can only be used for investigating non-expensive bottles or wine lots where there are multiple bottles of the same provenance. Uncertainties on the resulting 210 Pb radioactivity values are large, up to more than 50%, mainly due to local atmospheric variations, which prevents us to carry out precise dating. However it can be used to discriminate between an old wine (pre-1952) and a young wine (past-1990), an information that cannot be obtained with the other techniques based on other isotopes ( 137 Cs, 14 C or tritium). - Highlights: • We correlate the measured 210 Pb activity in wine to the vintage year. • A precise dating with 210 Pb is still difficult. • The method is complementary to the 137 Cs technique we previously developed

  13. Resonant ionization by laser beams: application to ions sources and to study the nuclear structure of radioactive tellurium isotopes

    International Nuclear Information System (INIS)

    Sifi, R.

    2007-07-01

    The radioactive ion beams that are produced through current isotope separators are well separated according to the A mass but not according to the Z parameter. The resonant ionization through laser beams applied to ion sources allows the production of radioactive ion beam in a very selective and efficient way by eliminating the isobaric contamination. The first chapter is dedicated to the resonant ionization by laser beams, we describe the principle, the experimental setting, the lasers used, the ionization schemes and the domain of application. The second chapter deals with the application of resonant ionization to laser ion sources for the production of radioactive ion beams. We present experimental tests performed for getting copper ion beams. Resonant ionization through laser is also used in the spectroscopy experiments performed at the Isolde (isotope separation on-line device) installation in CERN where more than 20 elements are ionized very efficiently. The technique is based on a frequency scanning around the excitation transition of the atoms in order to probe the hyperfine structure. Laser spectroscopy allows the determination of the hyperfine structure as well as the isotopic shift of atoms. In the third chapter the method is applied to the spectroscopy of tellurium atoms. First, we define the 2 parameters on which the extraction is based: charge radius and nuclear moments, then we present several theoretical models that we have used to assess our experimental results. (A.C.)

  14. Behaviour of radioactive and stable isotopes of calcium in the soil-solution-plant system at different soil humidity

    International Nuclear Information System (INIS)

    Karavaeva, E.N.; Molchanova, I.V.

    1976-01-01

    The results of experiments performed to study the behaviour of radioactive and stable isotopes of Ca in soil - solution - plant system at different soil moistening are given. The experiments have been conducted in culture pans with two soils: soddy-meadow and soddy-podzolic differing in a number of physico-chemical properties. The solution of radioactive Ca( 45 CaCl 2 ) has been applied to soddy-meadow soil at the rate of 0.2 μcurie/kg, and to soddy-podzolic soil - at the rate of 0.1 μcurie/kg. The distribution and accumulation coefficients are estimated by the ratio to the total content of stable Ca and 45 Ca in soil. A direct relationship between distribution coefficients and the rate of soil moistening is observed. It has been established that 45 Ca and the natural stable isotopes of Ca applied to the soil differ in the type of distribution in soil - soil solution system and in accumulation by plants. However, a great similarity has been observed in behaviour of radioactive and stable isotopes of Ca depending on soil moistening

  15. Decontamination of radioactively polluted game by means of pickling

    International Nuclear Information System (INIS)

    Hecht, H.

    1987-01-01

    The effect of pickling on the decontamination of game polluted by radioactive cesium isotopes has been investigated in the study reported. The best decontamination degree has been achieved with a vinegar marinade, the ratio between game and marinade being 1:3, pickling temperature being maintained at 12 0 C for a period of 4 days. By this procedure, 90 p.c. of the cesium isotopes have been taken up by the marinade. Buttermilk marinade also is a successful means of decontamination, but with clearly lower effects, and at the same temperature of 12 0 C does not remain microbiologically stable. Spices added to the marinade have shown to reduce the decontamination effet. Also, the ratio between game and marinade has been found to be decisive, the best ratio being 1:3. (orig./MG) [de

  16. Titanium carbide-carbon porous nanocomposite materials for radioactive ion beam production: processing, sintering and isotope release properties

    CERN Document Server

    AUTHOR|(CDS)2081922; Stora, Thierry

    2017-01-26

    The Isotope Separator OnLine (ISOL) technique is used at the ISOLDE - Isotope Separator OnLine DEvice facility at CERN, to produce radioactive ion beams for physics research. At CERN protons are accelerated to 1.4 GeV and made to collide with one of two targets located at ISOLDE facility. When the protons collide with the target material, nuclear reactions produce isotopes which are thermalized in the bulk of the target material grains. During irradiation the target is kept at high temperatures (up to 2300 °C) to promote diffusion and effusion of the produced isotopes into an ion source, to produce a radioactive ion beam. Ti-foils targets are currently used at ISOLDE to deliver beams of K, Ca and Sc, however they are operated at temperatures close to their melting point which brings target degradation, through sintering and/or melting which reduces the beam intensities over time. For the past 10 years, nanostructured target materials have been developed and have shown improved release rates of the produced i...

  17. Utilization of small-amount of radioactive isotope. Report of Technical Committee for Using Minor Radioactive Sources, Section of Physical Science and Industry, JRIAS. (1)

    International Nuclear Information System (INIS)

    1999-01-01

    The report of this series is a summary of considerations made by the committee which was founded in January, 1991, for stimulating the utilization of small-amount radioactive isotopes. The present report (1) is composed of three chapters concerning the purpose above mentioned and achievement of the committee, and reasonable regulation for the sealed isotopes. For the purpose, analysis was made for the present states of small-amount radioisotope utilization and of legal regulation and proposals were done by the committee. In the past, the first (1/1, 1991-5/31, 1992) and second (6/1, 1992 5/31, 1994) terms of the committee investigated the present states of utilization and safety handling in Japan and foreign countries, methods for stimulation, education and re-evaluation of the past trials for technology of those sub-legal isotopes together with translation of IAEA SAFETY SERIES No. 104 into Japanese, which was published in the journal Radioisotopes vol.44 (1995), for reference of the present states in Japan and foreign countries. In the chapter of proposal for the reasonable regulation for the sealed isotopes, the present committee investigated the present states of utilization of the industrial instruments and daily necessities which are equipped with small-amount radioisotopes, their legal and safety problems involved and the basis of calculation of exemption level, and made proposals for reasonable regulation. (K.H.)

  18. Study of Cesium and Strontium sorption in Brazilian clays for their use as a barrier in repositories of radioactive wastes; Estudo de sorcao de cesio e estroncio em argilas nacionais para sua utilizacao como barreira em repositorios de rejeitos radioativos

    Energy Technology Data Exchange (ETDEWEB)

    Freire, Carolina Braccini

    2007-07-01

    Wastes in general should be properly treated and stored. Then the radioactive wastes also require suitable and safe management beginning in their generation until the storage in repository. The main purpose of the radioactive waste management is to preserve the human beings and the environment. The objective of this research was to characterize some Brazilian clays in order to evaluate the viability of their use in the backfill layer, one of the radioactive waste repository barriers. The main function of this barrier is to contribute in the delay of the radionuclides movement, and to prevent their release into the environment. Four clays provided by national suppliers were selected for the research: Ca-Montmorillonite (Dol 01), Na-Montmorillonite (Dol 02), Kaolinite (Ind 01) and Vermiculite (Ubm 04). Their physical, chemical and mineralogical characteristics were determined, and also their sorption potential of Cesium and Strontium cations. It was confirmed through these results a direct relationship among their specific surface (SS), the capacity of cationic exchange (CCE) and pH. The CCE results followed this increasing order: Ind 01, Dol 01, and Dol 02. In accordance with the models of Freundlich (KJ) and Langmuir (M), the clays Dol 01 and Dol 02 were the best sorbers of Sr{sup 2+}. The Ind 01 and Ubm 04 were the best ones in the case of Cs{sup +}. The Gibbs free energy change ({delta}G deg) was calculated for the sorption reactions between the clays and the cations, and it was negative for all clays, confirming the sorption reaction spontaneity. (author)

  19. Development and application of RP-HPLC methods for the analysis of transition metals and their radioactive isotops in radioactive waste

    International Nuclear Information System (INIS)

    Seekamp, S.

    1999-07-01

    A major criterion in the final disposal of nuclear waste is to keep possible changes in the geosphere due to the introduction of radioactive waste as small as possible and to prevent any escape into the biosphere in the long term. The Federal Office for Radiation Protection (BfS) has therefore established limit values for a number of nuclides. Verifying these limits has to date involved laborious wet chemical analysis. In order to accelerate quantification there is a need to develop rapid multielement methods. HPLC methods represent a starting point for this development. Chemical separation is necessary to quantify β-emitters via their radioactive radiation since they are characterized by a continuous energy spectrum. A method for quantifying transition metals and their radioactive isotopes from radioactive waste has been created by using a chelating agent to select the analytes and RP-HPLC to separate the complexes formed. In addition to separating the matrix, complexation on a precolumn has the advantage of enriching the analytes. The subject of this thesis is the development and application of the method including studies of the mobile and stationary phase, as well as the optimization of all parameters, such as pH value, sample volume etc., which influence separation, enrichment or detection. The method developed was successfully tested using cement samples. It was also used for investigations of ion exchange resins and for trace analysis in calcium fluoride. Furthermore, the transferability of the method to actinides was examined by using a different complexing agent. (orig.) [de

  20. METHOD FOR THE RECOVERY OF CESIUM VALUES

    Science.gov (United States)

    Rimshaw, S.J.

    1960-02-16

    A method is given for recovering Cs/sup 137/ from radioactive waste solutions together with extraneous impurities. Ammonium alum is precipitated in the waste solution. The alum, which carries the cesium, is separated from the supernatant liquid and then dissolved in water. The resulting aqueous solution is then provided with a source of hydroxyl ions, which precipitates aluminum as the hydroxide, and the aluminum hydroxide is separated from the resulting liquid. This liquid, which contains anionic impurities together with ammonium and cesium, is passed through an anion exchange resin bed which removes the anionic impurities. The ammonium in the effluent is removed by destructive distiilation, leaving a substantiaily pure cesium salt in the effluent.

  1. Equilibrium sorption of cobalt, cesium, and strontium on Bandelier Tuff: analysis of alternative mathematical modeling

    International Nuclear Information System (INIS)

    Polzer, W.L.; Fuentes, H.R.; Essington, E.H.; Roensch, F.R.

    1985-01-01

    Sorption isotherms are derived from batch equilibrium data for cobalt, cesium and strontium on Bandelier Tuff. Experiments were conducted at an average temperature of 23 0 C and equilibrium was defined at 48 hours. The solute concentrations ranged from 0 to 500 mg/L. The radioactive isotopes 60 Co, 137 Cs, and 85 Sr were used to trace the sorption of the stable solutes. The Linear, Langmuir, Freundlich and a Modified Freundlich isotherm equations are evaluated. The Modified Freundlich isotherm equation is validated as a preferred general mathematical tool for representing the sorption of the three solutes. The empirical constants derived from the Modified Freundlich isotherm equation indicate that under dynamic flow conditions strontium will move most rapidly and cobalt least rapidly. On the other hand, chemical dispersion will be greatest for cesium and least for strontium. Hill Plots of the sorption data suggest that in the region of low saturation sorption of all three solutes is impeded by interactions among sorption sites; cobalt exhibits the greatest effect of interactions and strontium shows only a minimal effect. In the saturation region of 50% or more, sorption of cobalt is enhanced slightly by interactions among sorption sites whereas sorption of cesium and strontium appears to be independent of site interactions. 9 references, 4 figures, 2 tables

  2. Stationary point of the radiometric control of cesium contamination of agricultural animals

    International Nuclear Information System (INIS)

    1997-01-01

    Stationary point of the radiometric control of cesium contamination of an agricultural animals. Is intended for vital measurements of the contents of radiocesium in muscular tissue of a cattle. Can be used on cattle-breeding farms, providing points, in meat factories and personal facilities. As a base means for accommodation of the control point the motor-car is used. Design of the car allows to automate operations on deployment of the control point on a place and translation of one to a transport mode. Limits of measured specific activity of cesium contamination of a cattle is up 5*10 -9 to 5*10 -6 Ci/kg. The basic error on the bottom limit of measurement at confidence coefficient 0,95 is no more than 30%. Measurement time for the bottom limit of determined specific activity is no more than 30 s. There is automatic measurement mode. Type of a power is 220 V, 50 Hz. Range of working temperatures is up -15 to +35 centigrade. Relative humidity is no more than 98% at 25 centigrade. External gamma background is till 0.035 mR/h. Time of installation and dismantle of stationary control point is no more than 1,5 hours. The direct radiometric control in divo allows to fulfil and to use biotechnological process of removing of cesium isotopes from body of animals for decrease of levels of radioactive contamination

  3. A laboratory study of washing of SRS high-level waste radioactive sludge-evidence for insoluble sodium and cesium-137

    International Nuclear Information System (INIS)

    Hay, M.S.; Bibler, N.E.

    1994-01-01

    Experiments in the Shielded Cells at the Savannah River Technology Center were undertaken to simulate the full-scale sludge washing process and thereby identify potential problems, wash water requirements, sludge settling rates and the fate of various radioactive and non-radioactive species present in the sludge. The laboratory sludge washing experiments were conducted on a radioactive sludge sample taken from one of three processing tanks in Extended Sludge Processing. The sample of Tank 42H sludge was extensively characterized for both soluble and insoluble species (radioactive and non-radioactive) before beginning the washing study. The results of the washing experiments using inhibited water (0.01 M NaOH) indicate there is essentially no dissolution of species from the insoluble phase of the sludge during the washing. The addition of wash water to the sludge merely dilutes the salt dissolved in the interstitial supernate of the sludge. Another result from the experiments is that approximately 30% of the sodium and 86% of the Cs-137 in the original unwashed sludge is present in an insoluble form and does not wash out of the sludge

  4. Cesium 137 in oils and plants from Guatemala

    International Nuclear Information System (INIS)

    Ayala, R.E.; Perez, J.F.

    1993-01-01

    Since 1990 the project of radioactive and environmental contamination started in Guatemala. Studies about the radioactive contamination levels are made within the framework of this project. Cesium-137 has been an interest radionuclide, because it is a fission product released to the environment by the use of nuclear weapons and nuclear power plants accidents. The sampling consisted in collection of soil and grass in 20 provinces of Guatemala, one point by province, and it was made in 1990. The cesium-137 concentration in the samples, was determined by gamma spectrometry, using an hyper pure germanium detector. The results show the presence of radioactive contamination in soil and grass due to cesium-137, at levels that might be considered as normal. The levels found are not harmful for human health, and its importance is the fact that can be used as reference levels for the environmental radioactivity monitoring in Guatemala

  5. Adsorption of cesium on cement mortar from aqueous solutions

    Energy Technology Data Exchange (ETDEWEB)

    Volchek, Konstantin, E-mail: konstantin.volchek@ec.gc.ca [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Miah, Muhammed Yusuf [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Department of Applied Chemistry and Chemical Technology, Noakhali Science and Technology University (Bangladesh); Kuang, Wenxing; DeMaleki, Zack [Emergencies Science and Technology Section, Environment Canada, 335 River Road, Ottawa, Ontario, Canada K1A 0H3 (Canada); Tezel, F. Handan [Department of Chemical and Biological Engineering, University of Ottawa, 161 Louis-Pasteur, Ottawa, Ontario, Canada K1N 6N5 (Canada)

    2011-10-30

    Highlights: {yields} The adsorption of cesium on cement mortar was investigated in a range of temperatures and cesium concentrations. {yields} The pseudo-second order kinetic model produced a good fit with the experimental kinetic data. {yields} Equilibrium test results correlated well with the Freundlich isotherm adsorption model. {yields} The interaction between cesium ions and cement mortar was dominated by chemical adsorption. - Abstract: The adsorption of cesium on cement mortar from aqueous solutions was studied in series of bench-scale tests. The effects of cesium concentration, temperature and contact time on process kinetics and equilibrium were evaluated. Experiments were carried out in a range of initial cesium concentrations from 0.0103 to 10.88 mg L{sup -1} and temperatures from 278 to 313 K using coupons of cement mortar immersed in the solutions. Non-radioactive cesium chloride was used as a surrogate of the radioactive {sup 137}Cs. Solution samples were taken after set periods of time and analyzed by inductively coupled plasma mass spectroscopy. Depending on the initial cesium concentration, its equilibrium concentration in solution ranged from 0.0069 to 8.837 mg L{sup -1} while the respective surface concentration on coupons varied from 0.0395 to 22.34 {mu}g cm{sup -2}. Equilibrium test results correlated well with the Freundlich isotherm model for the entire test duration. Test results revealed that an increase in temperature resulted in an increase in adsorption rate and a decrease in equilibrium cesium surface concentration. Among several kinetic models considered, the pseudo-second order reaction model was found to be the best to describe the kinetic test results in the studied range of concentrations. The adsorption activation energy determined from Arrhenius equation was found to be approximately 55.9 kJ mol{sup -1} suggesting that chemisorption was the prevalent mechanism of interaction between cesium ions and cement mortar.

  6. Radioactive contamination of environment and food in Poland in 1998

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.

    1999-01-01

    The analysis of the level of radioactive contamination in environmental and food samples was carried out in Poland in 1998. The results were compared to the data from the period 1985-1997. Since the Chernobyl accident gradual decrease of contamination level has been observed. The gamma dose rate and the contamination of air, fallout, tape and surface water were at the level of 1985. The only contamination enhanced in relation to pre-Chernobyl period was the content of cesium isotopes in soil and as a consequence food contamination was higher particularly milk and meat. At present, the source of additional dose is ingestion of artificial isotopes with food as a result of food contamination. No significant regional differences in the distribution of the level of cesium in food over the territory of Poland has been registered. Milk can be assumed as the main contributor of cesium to the diet, its share is about 33% of annual intake of cesium. The average effective dose, resulting from the contaminated food consumption, was estimated to be at the level of 13 μSv per capita of the Polish population in 1998. (author)

  7. Radioactive contamination of environment and food in Poland in 1997

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.; Wilgos, J.

    1998-01-01

    The analysis of the level of radioactive contamination in environmental and food samples was carried out in Poland in 1997. The results were compared to the data from the period 1985-1996. Since the Chernobyl accident gradual decrease of contamination level has been observed. The gamma dose rate and the contamination of air, fallout, tape and surface water were at the level of 1985. The only contamination enhanced in relation to pre-Chernobyl period was the content of cesium isotopes in soil and as a consequence food contamination was higher particularly milk and meat. At present, the source of additional dose is ingestion of artificial isotopes with food as a result of food contamination. No significant regional differences in the distribution of the level of cesium in food over the territory of Poland has been registered. Milk can be assumed as the main contributor of cesium to the diet, its share is about 35% of annual intake of cesium. The average effective dose equivalent, resulting from the contaminated food consumption, was estimated to be at the level of 13 μSv per capita of the Polish population in 1997. (author)

  8. Radioactive contamination of environment and food in Poland in 1996

    International Nuclear Information System (INIS)

    Grabowski, D.; Kurowski, W.; Muszynski, W.; Rubel, B.; Smagala, G.; Swietochowska, J.; Wilgos, J.

    1997-01-01

    The analysis of the level of radioactive contamination in environmental and food samples was carried out in Poland in 1996. The results were compared to the data from the period 1985-1995. Since the Chernobyl accident gradual decrease of contamination level has been observed. The gamma dose rate and the contamination of air, fallout, tape and surface water were at the level of 1985. The only contamination enhanced in relation to pre-Chernobyl period was the content of cesium isotopes in soil and as a consequence food contamination was higher particularly milk and meat. At present, the source of additional dose is ingestion of artificial isotopes with food as a result of food contamination. No significant regional differences in the distribution of the level of cesium in food over the territory of Poland has been registered. Milk can be assumed as the main contributor of cesium to the diet, its share is about 40% of annual intake of cesium. The average effective dose equivalent, resulting from the contaminated food consumption, was estimated to be at the level of 14 μSv per capita of the Polish population in 1996. (author)

  9. Prognostication of the radioactive contamination with iodine 131, strontium 90 and cesium 137 of the air and soil after commissioning the ''Kozloduj'' nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Khristova, M; Paskalev, Z [Nauchno-Izsledovatelski Inst. po Radiologiya i Radiatsionna Khigiena, Sofia (Bulgaria)

    1975-01-01

    The content of iodine 131, strontium 90 and cesium 137 in the air (curie/l) and soil (curie/m/sup 2/ sec) in the area of the Kozloduj atomic power station (at a distance from 3 to 75 km from the chimney-stack of the power station) was determined. The concentrations of these radionuclides are determined under different meteorologic conditions: air temperature from -20/sup 0/C to +20/sup 0/C and a wind speed from 2 m/sec to 30 m/sec. The data show that at -20/sup 0/C radionuclide concentrations in the air decrease with increasing distance from the chimney-stack, regardless of the speed of the wind. At +20/sup 0/C radionuclide concentrations in the air increase with the distance from the chimney-stack, peak at a definite distance and then decrease. At 2 m/sec and speed this maximum is at a distance of 50 km from station. As the speed of the air increases, the peak moves nearer and remains about 30 km from the power station. Results on ground surface concentrations show that a trend is observed toward persistent decrease with distance from the power station. In rainy weather they are almost four times higher than in dry weather. The radionuclide concentrations on the ground surface will be comparable to their global deposits.

  10. Functions and requirements for a cesium demonstration unit

    International Nuclear Information System (INIS)

    Howden, G.F.

    1994-04-01

    Westinghouse Hanford Company is investigating alternative means to pretreat the wastes in the Hanford radioactive waste storage tanks. Alternatives include (but are not limited to) in-tank pretreatment, use of above ground transportable compact processing units (CPU) located adjacent to a tank farm, and fixed processing facilities. This document provides the functions and requirements for a CPU to remove cesium from tank waste as a demonstration of the CPU concept. It is therefore identified as the Cesium Demonstration Unit CDU

  11. Use of radioanalytical methods for determination of uranium, neptunium, plutonium, americium and curium isotopes in radioactive wastes

    International Nuclear Information System (INIS)

    Geraldo, Bianca

    2012-01-01

    Activated charcoal is a common type of radioactive waste that contains high concentrations of fission and activation products. The management of this waste includes its characterization aiming the determination and quantification of the specific radionuclides including those known as Difficult-to-Measure Radionuclides (RDM). The analysis of the RDM's generally involves complex radiochemical analysis for purification and separation of the radionuclides, which are expensive and time-consuming. The objective of this work was to define a methodology for sequential analysis of the isotopes of uranium, neptunium, plutonium, americium and curium present in a type of radioactive waste, evaluating chemical yield, analysis of time spent, amount of secondary waste generated and cost. Three methodologies were compared and validated that employ ion exchange (TI + EC), extraction chromatography (EC) and extraction with polymers (ECP). The waste chosen was the activated charcoal from the purification system of primary circuit water cooling the reactor IEA-R1. The charcoal samples were dissolved by acid digestion followed by purification and separation of isotopes with ion exchange resins, extraction and chromatographic extraction polymers. Isotopes were analyzed on an alpha spectrometer, equipped with surface barrier detectors. The chemical yields were satisfactory for the methods TI + EC and EC. ECP method was comparable with those methods only for uranium. Statistical analysis as well the analysis of time spent, amount of secondary waste generated and cost revealed that EC method is the most effective for identifying and quantifying U, Np, Pu, Am and Cm present in charcoal. (author)

  12. Global searches for microalgae and aquatic plants that can eliminate radioactive cesium, iodine and strontium from the radio-polluted aquatic environment: a bioremediation strategy.

    Science.gov (United States)

    Fukuda, Shin-Ya; Iwamoto, Koji; Atsumi, Mika; Yokoyama, Akiko; Nakayama, Takeshi; Ishida, Ken-Ichiro; Inouye, Isao; Shiraiwa, Yoshihiro

    2014-01-01

    The Fukushima 1 Nuclear Power Plant accident in March 2011 released an enormously high level of radionuclides into the environment, a total estimation of 6.3 × 10¹⁷ Bq represented by mainly radioactive Cs, Sr, and I. Because these radionuclides are biophilic, an urgent risk has arisen due to biological intake and subsequent food web contamination in the ecosystem. Thus, urgent elimination of radionuclides from the environment is necessary to prevent substantial radiopollution of organisms. In this study, we selected microalgae and aquatic plants that can efficiently eliminate these radionuclides from the environment. The ability of aquatic plants and algae was assessed by determining the elimination rate of radioactive Cs, Sr and I from culture medium and the accumulation capacity of radionuclides into single cells or whole bodies. Among 188 strains examined from microalgae, aquatic plants and unidentified algal species, we identified six, three and eight strains that can accumulate high levels of radioactive Cs, Sr and I from the medium, respectively. Notably, a novel eustigmatophycean unicellular algal strain, nak 9, showed the highest ability to eliminate radioactive Cs from the medium by cellular accumulation. Our results provide an important strategy for decreasing radiopollution in Fukushima area.

  13. Indian radioactive waste management programme: an overview

    International Nuclear Information System (INIS)

    Raj, Kanwar; Ozarde, P.D.

    2009-01-01

    The salient features of the closed fuel cycle are recovery and recycle of uranium and plutonium for reconversion as fuel. Emphasis is also being given to separation of useful isotopes of cesium and strontium for use in healthcare and in heat source applications and partitioning of minor actinides for transmutation. This finally leaves a very small percentage of material present in the spent fuel as radioactive waste, which needs to be managed. Radioactive waste management practices in India have roots in indigenous research and development in view of the importance accorded to it from the very inception of the country's nuclear energy programme. India's experience in the management of radioactive waste from research and power reactors, fuel reprocessing, and allied facilities is rich and comparable with international practices. (author)

  14. A novel technique for measurement of atomic data of rare and radioactive isotopes: a case study in gadolinium isotopes

    International Nuclear Information System (INIS)

    Marathe, A.P.; Venugopalan, A.; Jagatap, B.N.

    2002-01-01

    A new method of performing high resolution spectroscopy of rare and radioactive elements by devising a new design of a HCDL and using this as an emission source for high resolution spectroscopy on recording Fabry-Pecort optical spectrometer (REFPOS) has been developed

  15. Cesium migration experiments in different media

    International Nuclear Information System (INIS)

    Tello, C.C.O. de

    1992-01-01

    The environmental impact caused by the radioactive waste disposal depends on many factors, mainly on the release pathways of the radionuclides from the waste product to the environment. The migration of the radioelements through the different barriers, which compose the disposal system, is considered the main via for this release. This paper describes the experiments carried out to improve the cemented waste quality, as well to assess the cesium migration in different media. (author)

  16. A two-zone cosmic ray propagation model and its implication of the surviving fraction of radioactive cosmic ray isotopes

    International Nuclear Information System (INIS)

    Simon, M.; Scherzer, R.; Enge, W.

    1977-01-01

    In cosmic ray propagation calculations one can usually assume a homogeneous distribution of interstellar matter. The crucial astrophysical parameters in these models are: The path length distribution, the age of the cosmic ray particles and the interstellar matter density. These values are interrelated. The surviving fraction of radioactive cosmic ray isotopes is often used to determine a mean matter density of that region, where the cosmic ray particles may mainly reside. Using a Monte Carlo Propagation Program we calculated the change in the surviving fraction quantitatively assuming a region around the sources with higher matter density. (author)

  17. High resolution optical spectroscopy in isotopically-pure Si using radioactive isotopes: towards a re-evaluation of deep centres

    CERN Multimedia

    2008-01-01

    Deep centres in silicon have been studied in great detail over the last 50 years and much progress has been made in the understanding and control of impurities in this material. Much of this effort has been focussed on the problems of metallic impurities such as Fe, Ag, Cu and Au. These are impurities that diffuse quickly into the crystal and hamper device performance. Although the understanding of these impurity centres in Si is widely thought to be "solved" recent experiments with isotopically-pure Si are disproving long-held results and are opening up new perspectives on the constitutent nature of deep centres in Si. In particular, there is new evidence to show that the family of Cu, Ag and Au may all show essentially the same behaviour by forming a cluster of $\\textbf{any four atoms}$ of these elements. This has been established for Cu and Ag through the use of different stable isotopes in the preparation of samples, but the case of Au remains unproven since there is only one stable Au isotope. In this pr...

  18. Radioactivity

    International Nuclear Information System (INIS)

    Chelet, Y.

    2006-01-01

    The beginning of this book explains the why and how of the radioactivity, with a presentation of the different modes of disintegration. Are tackled the reports between radioactivity and time before explaining how the mass-energy equivalence appears during disintegrations. Two chapters treat natural radioisotopes and artificial ones. This book makes an important part to the use of radioisotopes in medicine (scintigraphy, radiotherapy), in archaeology and earth sciences (dating) before giving an inventory of radioactive products that form in the nuclear power plants. (N.C.)

  19. Radioactivity

    International Nuclear Information System (INIS)

    2002-01-01

    This pedagogical document presents the origin, effects and uses of radioactivity: where does radioactivity comes from, effects on the body, measurement, protection against radiations, uses in the medical field, in the electric power industry, in the food (ionization, radio-mutagenesis, irradiations) and other industries (radiography, gauges, detectors, irradiations, tracers), and in research activities (dating, preservation of cultural objects). The document ends with some examples of irradiation levels (examples of natural radioactivity, distribution of the various sources of exposure in France). (J.S.)

  20. Radiation from Radioactive Cesium (137 Cs) and Strontium (90Sr) Contaminated soil during the Chernobyl Nuclear Disaster Triggers Rice Immune Response

    International Nuclear Information System (INIS)

    Kimura, S.; Rakwal, R.; Agrawal, G. K.; Tamogami, S.; Kim, Y.H.; Shibato, J.; Sahoo, S. K.; Shiraishi, K.; Los, I. P.; Shevachuk, V. E.; Yonekura, M.; Iwahashi, H.

    2004-01-01

    After the Chernobyl nuclear accident in 1986 that exposed most of the population of the Northern hemisphere to various degrees of radiation, the public's perception of nuclear risk was completely changed. other than the obvious and much studied health impact, the agriculture and environmental impacts still pose a serious problem. Cesium-137, which has a half-life of 30.1 years, is the most important radionuclide left from Chernobyl's catastrophic explosion, and is present at high concentrations (activity, gamma-and beta-emitter) in the 0-5 cm soil layer. Strontium-90 (beta.emitter), which has a half-life of 29.1 years also constitutes a problem for plants. The effect of these radionuclides, and importantly show the radiation released therein affects plants has not been investigated in detail. In this study, we tested the hypothesis that leaves of two-week-old rice (japonica-type c, Nipponbare) seedlings (that constitutes a well-established in-vitro assay system) would respond to radiation (from the contaminated soil from Masany. Belarus, with major radionuclides, 137 Cs and 90 sr) by inducing various biochemical/molecular changes associated with the defense/stress response, including those involving mechanisms affecting the inactivation of damaging reactive oxygen specie. Rice (oryza sativa L.) is an enormously important food and monocot cereal crop research model whose draft genome sequence has recently been released. A molecular (northern analysis which provides a picture of the transcriptional changes of a particular gene), proteomics (two-dimensional electrophoresis (2-DE) is a powerful tool in understanding which proteins are present in particular tissue under given condition), and metabolomic (determining the metabolic profiles of metabolites induced during stress) approach was employed to monitor the changes in defense(stress-related (D/S-.r) genes, proteins (using 2-DE coupled with amino acid sequencing and immunoblotting) and metabolites (in particular

  1. Radioactive waste repository of Cesium of Abadia de Goias. Construction and design; Repositorio de rejeitos radioativos de cesio - Abadia de Goias. Concepcao e projeto

    Energy Technology Data Exchange (ETDEWEB)

    Tranjan Filho, Alfredo [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil); Alves, Antonio Sergio de Martin; Santos, Cicero Durval Pacifici dos; Passos, Erivaldo Mario dos; Coutinho, Fernando Paulo Millen [NUCLEN Engenharia e Servicos S.A., Rio de Janeiro, RJ (Brazil)

    1997-12-31

    The main criteria, the methodology, the solutions and parameters that were utilized in the design of the Intermediate and Low Level Radioactive Waste Repository of Abadia de Goias are shortly described. The various design steps are analysed from the preparation of the Safety Analysis Report to the detailing engineering tasks. The safety analysis for the constructed repository had the goal of verifying the magnitude of radioecological impacts corresponding to idealized activity release scenarios, allowing also the possible effects of human intrusion in the repository. These safety studies are intrinsically connected to computer calculations envisaged to simulate the long term performance of the repository. (author) 18 refs., 7 figs., 7 tabs.

  2. Criminal Protection of the Consumer of Irradiated food and Consumer Protection Against Contaminated Food with Radioactive Isotopes

    International Nuclear Information System (INIS)

    El-Baroudy, M.M.

    2003-01-01

    The widespread peaceful applications of atomic energy in food and agriculture had various positive and negative impacts on the economies of food and its production. Food is positively affected through either its treatment by ionizing radiation to preserve and reduce losses in it or by using mutations treated by ionizing radiation for improving their productivity. On the other hand, negative effects of nuclear energy on food are caused by nuclear explosions in nuclear weapons testing as well as by different nuclear energy applications and the wastes formed as a result of it. These activities can cause different contamination levels of the environment and particularly, the arable land. This in turn leads to the production of contaminated food with radioactive isotopes. Consequently, the present work which is subdivided into two parts, involves a study of both the positive and negative effects of ionizing radiations and radioactive isotopes on food. The first part deals with the legal protection of food treated by ionizing radiations to preserve it, explaining the related different legal and regulatory aspects. Food irradiation processes should be carried out in a framework of the national control regulations and in a way that is consistent with the reference standards adopted internationally for the safety and hygiene of food

  3. The effect of fertilizer application on 137 cesium accumulation in lucerne grown on a leached chernozem

    International Nuclear Information System (INIS)

    Konstantinov, G.; Kovachev, K.; Penchev, D.; Ermolaev, I.; Mirchev, M.

    1974-01-01

    On the basis of pot experiments, carried out in a glass-house the following conclusions on the effect of fertilizer application are made: nitrogen fertilizer application increases the amount of radioactive cesium in lucerne plants. Phosphorus fertilizer introduction, similarly to potassium fertilizer application decreases cesium uptake, resulting in an increase in available phosphorus in the soil. (M.Ts.)

  4. Utilization of cesium-137 environmental contamination from fallout in erosion and sedimentation studies

    International Nuclear Information System (INIS)

    Guimaraes, M.F. da; Pessenda, L.C.R.; Fernandes, E.A.N.; Freire, O.; Nascimento Filho, V.F. do; Ferraz, E.S.B.

    1988-01-01

    The radioactivity of cesium-137 from fallout in different soils profiles for erosion and sedimentation studies are described. The potential of this technique for hydrographic basin in Piracicaba/Sao Paulo is evaluated. Due to the existence of natural radionuclides in soil, with energy near to cesium-137, the soil samples are determined by a high-purity Ge detectors. (author)

  5. Cesium-137: psychological and social consequences of the Goiania's accident

    International Nuclear Information System (INIS)

    Helou, Suzana; Costa Neto, Sebastiao Benicio da

    1995-01-01

    The book care for radioactive accident occurred in 1987 in Goiania - brazilian city. The accident had origin by the hospitable equipment incorrect handling which contained a stainless steel capsule, in which interior there was cesium-137 chloride. The main boarded aspects are: psychological and social aspects verified after the accident; psychological and social analysis of population of Goiania three years after the accident; essay on the pertinence of Luscher's abbreviate test in psychological evaluation of the radioactive accident victims of Goiania; and psychological and mobile evaluation of intra-uterus children exposed to the radiation with cesium-137

  6. First-principles calculation study of mechanism of cation adsorption selectivity of zeolites. A guideline for effective removal of radioactive cesium

    International Nuclear Information System (INIS)

    Nakamura, Hiroki; Okumura, Masahiko; Machida, Masahiko

    2013-01-01

    Zeolites have attracted attention in the reprocessing of radioactive nuclear waste because of their high selective affinity for radioisotopes of Cs. Very recently, their useful properties have been widely utilized in decontamination after the accident at the Fukushima Daiichi Nuclear Power Plants. In this study, we study the high selectivity in the Cs adsorption of zeolites using first-principles calculations and clarify the mechanism of the cation selectivity of zeolites. We obtain energy surfaces on all capture locations for Cs/Na ions inside the micropores of a zeolite, 'mordenite', and find three crucial conditions for the highly ion-selective exchange of Na for Cs: 1) micropores with a radius of ∼3 Å, 2) a moderate Al/Si ratio, and 3) a uniform distribution of Al atoms around each micropore. These insights suggest a guideline for developing zeolites with high Cs selectivity and for enhancing the cation selectivity in more general situations. (author)

  7. Radioactivity Handbook

    International Nuclear Information System (INIS)

    Firestone, R.B.; Browne, E.

    1985-01-01

    The Radioactivity Handbook will be published in 1985. This handbook is intended primarily for applied users of nuclear data. It will contain recommended radiation data for all radioactive isotopes. Pages from the Radioactivity Handbook for A = 221 are shown as examples. These have been produced from the LBL Isotopes Project extended ENDSF data-base. The skeleton schemes have been manually updated from the Table of Isotopes and the tabular data are prepared using UNIX with a phototypesetter. Some of the features of the Radioactivity Handbook are discussed here

  8. Study on preparing the absorbent of potassium nickel hexacyanoferrate (II) loaded zeolite for removal of cesium from radioactive waste solutions and followed method for stable solidification of spent composites

    International Nuclear Information System (INIS)

    Pham Quynh Luong; Nguyen Hoang Lan; Nguyen Van Chinh; Nguyen Thu Trang; Vuong Huu Anh; Le Xuan Huu; Nguyen Thi Xuan; Le Van Duong

    2017-01-01

    The selective adsorption and stable immobilization of radioactive cesium, K-Ni-hexacyanoferrate (II) loaded zeolite (FC-zeolite) prepared by impregnation / precipitation method were studied. The uptake equilibrium of Cs + for composites FC-zeolite was attained within 8 h and estimated to be above 97% in Cs + 100 mg/l solution at pH 4-10. Maximum ion exchange capacity of Cs + ions (Q max ) for FC-zeoliteX was 112.5 and 69.7 mg/g in pure water and sea water, respectively. Those values for FC-zeolite A was 85.7 and 42.7 mg/g. Decontamination factor (DF) of FC-zeolite X for 134 Cs was 149.7 and 107.5 in pure water and sea water respectively. Study on synthesized zeolites (A and X) made of HUST was also conducted in similar manner. The values of Q max were 98.6 and 39.9 mg/g for zeolite A, and 69.5 and 20.8 mg/g for zeolite X in pure water and sea water, respectively. Decontamination factor (DF) of zeolite A and X for 134 Cs showed lower values. The spent CsFC-zeolite was solidificated in optimal experimental conditions: 5% Na 2 B 4 O 7 additives; calcination temperature at 900 o C for 2 h in air. Solid form was determined some of parameters: immobilization of Cs, compressive strength, volume reduction after calcination (%) and leaching rate of Cs + ions in deionization water. (author)

  9. State of radionuclides in seawater. Comparison of natural stable and artificial radioactive isotope s of mercury and zinc in natural waters of the arid zone of the USSR

    International Nuclear Information System (INIS)

    Rakhmatov, U; Khikmatov, K; Kist, A.A.; Kulmatov, R.A.; Teshabaev, S.T.; Volkov, A.A.

    1986-01-01

    This paper studies the state of stable and artificial radioactive isotopes of merury and zinc in natural waters of the arid zone of the USSR by radioactivity and radiochemical methods. Convergent results have been obtained for the dissolved forms of mercury and zinc in natural waters of the arid zone in a comparison of the results of radioactivation analysis and laboratory simulation using the radionuclides mercury-203 and zinc-65

  10. Use of stable and radioactive isotopes in the determination of the recharge rate in Djeffara aquifer system southern Tunisia

    International Nuclear Information System (INIS)

    Trabelisi, R.; Zouari, K.

    2012-12-01

    Southern Tunisia is characterized by the presence of several hydrogeological basins, which extend over Tunisian borders. The Djeffara aquifer is one of the most important aquifer systems n this area and contains several interconnected aquifer levels. Stable (δ 2 H, δ 18 O and δ 13 C) and radioactive isotopes (1 4C , 3 H ) have been used to evaluate recharge mechanisms and groundwater residence time in the Djeffara multi-aquifer. Thesis aquifer presents two compartments, the first one ( west of the Medenine fault system) is unconfined with a well defined isotope fingerprint, the second compartment is deeper and confined multi- tracer results show groundwater of different origins, and ages , and that tectonic features control ground water flows. The unconfined part was mostly recharged during the Holocene. The recharge rates of this aquifer, inferred by 1 4C ages, are variable and could reach 3.5 mm/year. However, stable isotope composition and 1 4 'C content of the confined groundwater indicates carrier recharge during late pelistocene cold periods. (Author)

  11. Source term estimation and the isotopic ratio of radioactive material released from the WIPP repository in New Mexico, USA

    International Nuclear Information System (INIS)

    Thakur, P.

    2016-01-01

    After almost 15 years of operations, the Waste Isolation Pilot Plant (WIPP) had one of its waste drums breach underground as a result of a runaway chemical reaction in the waste it contained. This incident occurred on February 14, 2014. Moderate levels of radioactivity were released into the underground air. A small portion of the contaminated underground air also escaped to the surface through the ventilation system and was detected approximately 1 km away from the facility. According to the source term estimation, the actual amount of radioactivity released from the WIPP site was less than 1.5 mCi. The highest activity detected on the surface was 115.2 μBq/m 3 for 241 Am and 10.2 μBq/m 3 for 239+240 Pu at a sampling station located 91 m away from the underground air exhaust point and 81.4 μBq/m 3 of 241 Am and 5.8 μBq/m 3 of 239+240 Pu at a monitoring station located approximately 1 km northwest of the WIPP facility. The dominant radionuclides released were americium and plutonium, in a ratio that matches the content of the breached drum. Air monitoring across the WIPP site intensified following the first reports of radiation detection underground to determine the extent of impact to WIPP personnel, the public, and the environment. In this paper, the early stage monitoring data collected by an independent monitoring program conducted by the Carlsbad Environmental Monitoring & Research Center (CEMRC) and an oversight monitoring program conducted by the WIPP's management and operating contractor, the Nuclear Waste Partnership (NWP) LLC were utilized to estimate the actual amount of radioactivity released from the WIPP underground. The Am and Pu isotope ratios were measured and used to support the hypothesis that the release came from one drum identified as having breached that represents a specific waste stream with this radionuclide ratio in its inventory. This failed drum underwent a heat and gas producing reaction that overpowered its vent and

  12. Efigie: a computer program for calculating end-isotope accumulation by neutron irradiation and radioactive decay

    International Nuclear Information System (INIS)

    Ropero, M.

    1978-01-01

    Efigie is a program written in Fortran V which can calculate the concentration of radionuclides produced by neutron irradiation of a target made of either a single isotope or several isotopes. The program includes optimization criteria that can be applied when the goal is the production of a single nuclide. The effect of a cooling time before chemical processing of the target is also accounted for.(author) [es

  13. Cesium transport in Four Mile Creek of the Savannah River Plant

    International Nuclear Information System (INIS)

    Kiser, D.L.

    1979-04-01

    The behavior of a large radioactive cesium release to a Savannah River Plant (SRP) stream was examined using a stable cesium release to Four Mile Creek. Measurements following the release show that most of the cesium released was transported downstream; however, sorption and desorption decreased the maximum concentration and increased the travel time and duration, relative to a dye tracer, at sampling stations downstream. The study was made possible by the development of an analytical technique using ammonium molybdophosphate and neutron activation that permitted the measurement of stable cesium concentrations as low as 0.2 μg/L

  14. Seasonal variation of cesium 134 and cesium 137 in semidomestic reindeer in Norway after the Chernobyl accident

    International Nuclear Information System (INIS)

    Eikelmann, I.M.H.; Bye, K.; Sletten, H.D.

    1990-01-01

    The Chernobyl accident had a great impact on the semidomestic reindeer husbandry in central Norway. Seasonal differences in habitat and diet resulted in large variations in observed radiocesium concentrations in reindeer after the Chernobyl accident. In three areas with high values of cesium-134 and cesium-137 in lichens, the main feed for reindeer in winter, reindeer were sampled every second month to monitor the seasonal variation and the decrease rate of the radioactivity. The results are based on measurements of cesium-134 and cesium-137 content in meat and blood and by whole-body monitoring of live animals. In 1987 the increase of radiocesium content in reindeer in Vågå were 4x from August to January. The mean reductions in radiocesium content from the winter 1986/87 to the winter 1987/88 were 32%, 50% and 43% in the areas of Vågå, Østre-Namdal and Lom respectively

  15. Removal of cesium from red deer meat

    International Nuclear Information System (INIS)

    Jandl, J.; Novosad, J.; Francova, J.; Prochazka, H.

    1989-01-01

    The effect was studied of marinading on the reduction of cesium radionuclide activity in red deer meat contaminated by ingestion of feed containing 134 Cs+ 137 Cs from radioactive fallout following the Chernobyl accident. Two types of marinade were studied, viz., a vinegar infusion and a vinegar infusion with an addition of vegetables and spices. The meat was chopped to cubes of about 1.5 cm in size and the marinading process took place at temperatures of 5 and 11 degC. The drop of cesium content in the meat was determined by gamma spectrometry at given time intervals. The replacement of the marinade and the duration of the process were found to maximally affect efficiency. If the solution was not replaced, about 80% of cesium radionuclides were removed after seven hours of marinading. With one replacement of the infusion the drop in 134 Cs+ 137 Cs radioactivity amounted to up to 90% after seven hours of marinading. No effects were shown of vegetable additions to the vinegar infusion and of the change in temperature from 5 to 11 degC on the efficiency of the process. (author). 3 tabs., 6 refs

  16. Radioactivity. Centenary of radioactivity discovery

    International Nuclear Information System (INIS)

    Charpak, G.; Tubiana, M.; Bimbot, R.

    1997-01-01

    This small booklet was edited for the occasion of the exhibitions of the celebration of the centenary of radioactivity discovery which took place in various locations in France from 1996 to 1998. It recalls some basic knowledge concerning radioactivity and its applications: history of discovery, atoms and isotopes, radiations, measurement of ionizing radiations, natural and artificial radioactivity, isotope dating and labelling, radiotherapy, nuclear power and reactors, fission and fusion, nuclear wastes, dosimetry, effects and radioprotection. (J.S.)

  17. Isotopic and Radioactivity Fingerprinting of Groundwater in the United Arab Emirates (UAE)

    Energy Technology Data Exchange (ETDEWEB)

    Murad, A.; Hussein, S. [Department of Geology, United Arab Emirates University, Al Ain (United Arab Emirates); Aldahan, A. [Department of Geology, United Arab Emirates University, Al Ain (United Arab Emirates); Department of Earth Sciences, Uppsala University, Uppsala (Sweden); Hou, X. L. [Riso National Laboratory for Sustainable Energy, Technical University of Denmark, Roskilde (Denmark); Possnert, G. [Tandem Laboratory, Uppsala University, Uppsala (Sweden)

    2013-07-15

    A pilot investigation using radioactivity together with chemical features was conducted to characterize groundwater sampled from wells drilled in fractured Paleogen-Neogen carbonate rocks along the foothill of about 1200 m absl high mountain and wells drilled in Quaternary clastic sediments from a nearby alluvial plain in the southeastern part of the UAE. These two water modes are relatively easily separated by their chloride and EC (salt content) contents and provide an ideal case for testing radioactivity fingerprints. The groundwater of the alluvial plain, which is expected to reflect a short distance precipitation recharge source, indicates a concentration of {sup 222}Rn and {sup 226}Ra 2-3 orders of magnitude lower than the groundwater of the carbonate rocks. The range of variability for gross alpha is similar, but the gross beta activity indicates only 1 order of magnitude difference between the two water types. The radioactively richer groundwater of the carbonate aquifers compared to the alluvium plane may reflect the signature of deep basinal fluids. These marked differences in radioactivity of the two water modes clearly suggests that radioactive fingerprinting can provide a potential method for the identification groundwater sources in the UAE. (author)

  18. Natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store

    International Nuclear Information System (INIS)

    Bezak, J.; Daniel, J.; Moravek, J.

    2000-01-01

    The results of monitoring of natural and artificial radioactivity in the area of the Mochovce regional radioactive waste store before commission are presented. The concentrations of uranium, thorium, potassium, and cesium, as well as radon volume activity were measured

  19. Environmental radioactivity in Canada, 1987. Annual publication

    Energy Technology Data Exchange (ETDEWEB)

    1988-01-01

    The radiological surveillance program of the Department of National Health and Welfare is conducted to determine levels of environmental radioactivity in Canada and to assess the resulting population exposures. The report is prepared as a summary of work in progress and as a means of publishing the results of ongoing programs. Special studies reported on included the evaluation of the contamination by cesium-137 of caribou, a major source of food in northern communities; the development of methods for the determination of radon, carbon-14, polonium-210, radium-228 and isotopic uranium in samples; and monitoring of fallout contamination from Chernobyl of imported foods. Environmental monitoring programs conducted included external radiation exposure, tritium in water vapour, gross beta radioactivity, and monitoring of air, drinking water, precipitation and milk. A list of reports and presentations is also included.

  20. Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility.

    Energy Technology Data Exchange (ETDEWEB)

    Talamo, A.; Gohar, Y.; Nuclear Engineering Division

    2007-05-15

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,{gamma}), (n,2n), (n,p), and ({gamma},n). In the second part

  1. The behaviour of radioactive isotopes in liquid metal cooled fast reactors

    International Nuclear Information System (INIS)

    Watson, W.R.; Gwyther, J.R.

    1979-01-01

    A small scale, all AISI 316 stainless steel, pumped loop has been operated with 134 Cs, 137 Cs and 22 Na in the sodium. The loop has a distillation sampler, oxygen meter, two cold traps and a small subsidiary pumped loop initially containing the isotopes adsorbed on uranium oxide. The distribution of the isotopes within the loop has been determined over the temperature range 100 to 300 0 C with 1 to 2 ppm of oxygen in the sodium and a sodium velocity about half the Reynolds number required for the onset of turbulence in the vertical legs. (author)

  2. Radioactive isotope production for medical applications using Kharkov electron driven subcritical assembly facility

    International Nuclear Information System (INIS)

    Talamo, A.; Gohar, Y.

    2007-01-01

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an accelerator driven subcritical assembly. The main functions of the subcritical assembly are the medical isotope production, neutron thereby, and the support of the Ukraine nuclear industry. Reactor physics experiments and material research will be carried out using the capabilities of this facility. The United States of America and Ukraine have started collaboration activity for developing a conceptual design for this facility with low enrichment uranium (LEU) fuel. Different conceptual designs are being developed based on the facility mission and the engineering requirements including nuclear physics, neutronics, heat transfer, thermal hydraulics, structure, and material issues. Different fuel designs with LEU and reflector materials are considered in the design process. Safety, reliability, and environmental considerations are included in the facility conceptual design. The facility is configured to accommodate future design improvements and upgrades. This report is a part of the Argonne National Laboratory Activity within this collaboration for developing and characterizing the subcritical assembly conceptual design. In this study, the medical isotope production function of the Kharkov facility is defined. First, a review was carried out to identify the medical isotopes and its medical use. Then a preliminary assessment was performed without including the self-shielding effect of the irradiated samples. Finally, more detailed investigation was carried out including the self-shielding effect, which defined the sample size and irradiation location for producing each medical isotope. In the first part, the reaction rates were calculated as the multiplication of the cross section with the unperturbed neutron flux of the facility. Over fifty isotopes were considered and all transmutation channels are used including (n,γ), (n,2n), (n,p), and (γ,n). In the second part, the parent

  3. Simultaneous Measurements of Nanoaerosols and Radioactive Aerosols Containing the Short-lived Radon Isotopes.

    Czech Academy of Sciences Publication Activity Database

    Otáhal, P.P.S.; Burian, I.; Ondráček, Jakub; Ždímal, Vladimír; Holub, R.F.

    2017-01-01

    Roč. 175, č. 5 (2017), s. 53-56 ISSN 0144-8420. [Conference on Protection against Radon at Home and at Work / 13th International Workshop on the Geological Aspects of Radon Risk Mapping /8./. Prague, 12.09.2017-16.09.2017] Institutional support: RVO:67985858 Keywords : equilibrium-equivalent concentration * radon * radioactive nenoaerosols Subject RIV: DL - Nuclear Waste, Radioactive Pollution ; Quality OBOR OECD: Environmental sciences (social aspects to be 5.7) Impact factor: 0.917, year: 2016

  4. Determination of Isotopes Types and Activities in Radioactive Waste of Kosovo A Power Plant

    OpenAIRE

    , B Cena; , K Dollani; , G Hodolli

    2013-01-01

    The second nnportant event after the 1nventory of rad10act1ve waste 1n Kosovo, their location and the number of radioactive sources, is the determination of the type of radioisotope and their activities. This activity was conducted entirely in difŞcult terrain and was taken due to the absence in most cases of resource certiŞcates or any other document with the necessary information that will enable the identiŞcation of radioactive sources and their activity. In this way the activity was under...

  5. Radioactive substances

    International Nuclear Information System (INIS)

    Butler, G.C.; Hyslop, C.

    1980-01-01

    The purpose of this chapter is to show how to assess the detriment resulting from the release of radioactive materials to the environment. The minimum information required for the assessments is given for seven radionuclides of interest from the point of view of environmental contamination. The seven radionuclides are tritium, krypton-85, strontium-90, iodine-131, cesium-137, radium-226 and plutonium-239. Information is given on the radiation doses and the radiation effects on man due to these radioisotopes. (AN)

  6. High resolution laser spectroscopy of radioactive isotopes using a RFQ cooler-buncher at CERN-ISOLDE

    CERN Document Server

    Mané, E

    2009-01-01

    At CERN, the European Organization for Nuclear Research, radioactive nuclear beams are produced at the On-Line Isotope Mass Separator facility, ISOLDE. This facility provides a variety of exotic nuclear species for multidisciplinary experiments including nuclear physics. A gas-filled linear Paul trap was commissioned off-line and on-line and now is fully integrated at the focal plane of the high resolution separator magnets of ISOLDE. Ion beams with reduced transverse emitance and energy spread are now available for all experiments located downstream the separator beam line. This device is also able to accumulate the ion beam and release the collected sample in short bunches. Typical accumulation times are 100 ms and the released bunch width is 5-20 $\\mu{s}$. Such bunching capabilities has substantially increased the sensitivity of collinear laser spectroscopy with fluorescence detection by reducing the background from laser scatter by up to four orders of magnitude. The spectroscopic quadrupole moments of $^...

  7. α decay and cluster radioactivity of nuclei of interest to the synthesis of Z =119 , 120 isotopes

    Science.gov (United States)

    Poenaru, D. N.; Gherghescu, R. A.

    2018-04-01

    Super-heavy nuclei of interest for the forthcoming synthesis of the isotopes with Z =119 , 120 are investigated. One of the very interesting latest experiments was performed at the velocity filter SHIP (GSI Darmstadt) trying to produce 299120 in a fusion reaction 248Cm(54Cr,3 n )299120 . We report calculations of α -decay half-lives using four models: AKRA (Akrawy), ASAF (analytical superasymmetric fission), UNIV (universal formula), and semFIS (semi-empirical formula based on fission theory). The released energy, Q , is calculated using the theoretical model of atomic masses, WS4. For Sr,9492 cluster radioactivity of 120,302300 we predict a branching ratio relative to α decay of -0.10 and 0.49, respectively, meaning that it is worth trying to detect such kinds of decay modes in competition with α decay.

  8. Study of isotopic desequilibrium of natural radioactive series in granitic environment: Pluton of El Berrocal (Toledo)

    International Nuclear Information System (INIS)

    Hernandez Benitez, A.

    1994-01-01

    This report summarizes the work funded by European Communities with contract '' The Berrocal project: characterization and validation of natural radionuclide migration processes under real conditions in a fissured granitic environment''. The author takes into account the following aspects in his study: isotope of natural radionuclides, sampling methods, analytic methodology and geological characteristics of the area

  9. Use of radioactive and stable isotopes in hydrologic studies. Some examples of its application in Ecuador

    International Nuclear Information System (INIS)

    Villalba, Fabio

    2001-01-01

    Isotope techniques have been applied in Ecuador in different cases, looking for solutions to specific problems related to the origin and age of ground waters, dam filtrations, characterization of lakes, river/aquifers interrelation, and others. This work presents a short review of these cases showing the applied technique and the results obtained

  10. Preparation of radioactive labelled compounds. Pt. 2. 82Br labelled organic bromine compounds by isotopic exchange

    International Nuclear Information System (INIS)

    Otto, R.

    1988-05-01

    Studies on isotopic exchange between organic bromine compounds and 82 Br labelled dioxane dibromide in the presence of AlCl 3 are described. The results obtained enable to develop a simple and quick preparation method for the labelling with 82 Br [fr

  11. Collinear laser spectroscopy on radioactive neutron-deficient lead and thallium isotopes

    International Nuclear Information System (INIS)

    Menges, R.

    1989-02-01

    The systematic study of the isotope shift in the neighbourhood of the closed shells was extended in this thesis to Z = 82. The elements lead and thallium were measured up to the mass 190 and 188 and the nuclear moments determined together with the change of the mean square charge radius. The accumulating of the recoil nuclei formed by heavy ion reactions in the bunched ion source of the GSI mass separator could be used in order to study the low-spin isomers with I = 2 of the neutron-deficient thallium isotopes up to A = 190. It is a clearly recognizable isomer shift against the I = 7 isomers shown which changes at A = 194 the sign. A phenomenon which also exists in the element mercury, but for which no sufficient explanation exists. The magnetic moments of the thallium isotopes complete the analysis of Ekstroem (1976) and confirm the choice of the sign of the magnetic moments of the I = 2 isomers. The application of the additivity rule to the odd-odd nuclei shows qualitatively good agreement with the experiment and confirms so the assignment of the configuration of the contributing nuclear states. The quadrupole moments show a slight oblate deformation of the 9/2 - intruder states. The moments of the lead isotopes show pronounced one-particle character and by this the nearly spherical shape of nuclei with closed proton shell. The deviation from the linear slope of the mean square radius of the lead isotopes onsetting at A = 194 cannot be explained by the mixing of the 0 1 + ground state with the deformed 0 2 + intruder state. The odd - even staggering and the buckling of the charge radii at the shell closure are very well reproduced by Hartree-Fock calculations which regard the 3- and 4-particle interactions in the nucleus. (orig.) [de

  12. Isotopic and Radioactivity Fingerprinting of Groundwater in the United Arab Emirates

    DEFF Research Database (Denmark)

    Murad, A.; Aldahan, A.; Hou, Xiaolin

    2013-01-01

    A pilot investigation using radioactivity together with chemical features was conducted to characterize groundwater sampled from wells drilled in fractured Paleogen-Neogen carbonate rocks along the foothill of about 1200 m absl high mountain and wells drilled in Quaternary clastic sediments from ...

  13. Methods of producing cesium-131

    Science.gov (United States)

    Meikrantz, David H; Snyder, John R

    2012-09-18

    Methods of producing cesium-131. The method comprises dissolving at least one non-irradiated barium source in water or a nitric acid solution to produce a barium target solution. The barium target solution is irradiated with neutron radiation to produce cesium-131, which is removed from the barium target solution. The cesium-131 is complexed with a calixarene compound to separate the cesium-131 from the barium target solution. A liquid:liquid extraction device or extraction column is used to separate the cesium-131 from the barium target solution.

  14. Strontium-90 and cesium-137 in fresh water

    International Nuclear Information System (INIS)

    1978-01-01

    Japan Chemical Analysis Center has analysed the strontium-90 and Cesium-137 contents in fresh water from 7 prefectures in Japan by the commission of Science and Technology Agency of Japanese Government. The method described in ''Radioactivity Survey Data in Japan No. 43 (NIRS-RSD-43, 1977) was applied to the analysis of these two radionuclides in samples. (author)

  15. Cesium-137: A physiological disruptor?

    International Nuclear Information System (INIS)

    Souidi, Maamar; Grison, Stephane; Dublineau, Isabelle; Aigueperse, Jocelyne; Lestaevel, Philippe

    2013-01-01

    Today, radiation protection is a major issue for the nuclear industry throughout the world, particularly in France. The 2011 disaster of Fukushima Dai-ichi has brought back to public attention questions about the risks associated with nuclear power for civilian purposes. The risk of accidental release of radioactive molecules, including cesium-137 ( 137 Cs), from these facilities cannot be completely eliminated. The non-cancer-related health consequences of chronic exposure to this radionuclide remain poorly understood. After absorption, cesium is distributed throughout the body. The toxicity of 137 Cs is due mainly to its radiological properties. Studies in humans report that 137 Cs impairs the immune system and induces neurological disorders. Children appear more susceptible than adults to its toxic effects. In animals, and most particularly in rodents, low-dose internal contamination disrupts the sleep-wake cycle, but without behavioural disorders. Impairment of the cardiovascular system has also been observed. Physiologic systems such as the metabolism of vitamin D, cholesterol and steroid hormones are altered, although without leading to the emergence of diseases with clinical symptoms. Recently, a metabolomics study based on contamination levels comparable to those around Chernobyl after the accident showed that it is possible to identify individual rats chronically exposed to low doses of 137 Cs, even though the exposure was too low to affect the standard clinical markers. In conclusion, the scientific evidence currently available, particularly that from experimental animal models exposed to chronic contamination, suggests that 137 Cs is likely to affect many physiologic and metabolic functions. Thus, it could contribute, with other artificial substances in the environment, to increasing the risk of developing non-cancer diseases in some regions. (authors)

  16. Radionuclide ratios of cesium and strontium in Tarapur marine environment, west coast of India

    International Nuclear Information System (INIS)

    Baburajan, A.; Rao, D.D.; Chandramouli, S.; Iyer, R.S.; Hegde, A.G.

    1999-01-01

    Marine environment of Tarapur located 100 km north of Mumbai on the west coast, receives low level liquid waste from Tarapur Atomic Power Station (TAPS) and Fuel Reprocessing Plant (FRP). Radionuclide ratios of cesium and strontium were obtained in source term (the quantum of radioactive liquid waste available for discharge) and different marine samples viz, seawater, sediment, seaweed and marine organisms. A constant ratio of 137 Cs: 134 Cs was observed in seawater and source term. But the ratio of 137 Cs: 90 Sr had wide variation due to selective scavenging of 137 Cs by sedimentary particles at the discharge location. Among the other matrices, sediment showed a higher value of 137 Cs: 134 Cs and 137 Cs: 90 Sr reflecting the cumulative effects of releases from TAPS and FRP and higher distribution coefficient of radiocesium from seawater to sediment. Marine algae indicate a discrimination against sorption of 90 Sr due to the isotopic dilution by stable strontium present in seawater (8mg/l). The marine organisms preying on sediment containing microflora and fauna exhibited radionuclide ratios similar to seawater as the sediment sorbed cesium is not available for assimilation due to the mineral nature of the sediment. The matrices other than sediment indicated the equilibrated activity ratio of radionuclides in seawater which is the recipient medium and reflected the influence of continuous discharge. The sedimentary radionuclide ratio is largely dependent on sorption characteristics of radionuclides and their retention. (author)

  17. Behavior of ruthenium, cesium and antimony in high temperature processes for waste conditioning

    International Nuclear Information System (INIS)

    Klein, M.; Weyers, C.; Goossens, W.R.A.

    1985-01-01

    The fission products and the actinides of high level radioactive liquid wastes can be immobilized by incorporation into a glass matrix prior to disposal. The behaviour of so-called semi-volatile products during the vitrification process has been studied by the C.E.N./S.C.K. in Mol since 1979 in the framework of a contract with DWK of Germany in support to the HAW technological program PAMELA. The experiments were performed on laboratory and semi-pilot scale using simulated LEWC solutions tagged with radioisotopes of three suspected volatile fission products, namely ruthenium, cesium and antimony. The releases of these semi-volatile compounds to the off-gases have been investigated for a liquid fed melter as a function of the operational conditions. The study of a wet purification system, comprising in series of a dust scrubber, a condensor, an ejector venturi and an NOsub(x) column, has shown that cesium appears to be the reference isotope for the volatile elements released from the melter. Ruthenium seems not to be a problem from the point of view of gas purification although local radiation problems caused by deposits on metal surfaces cannot be excluded. (Auth.)

  18. Physico-chemical reactions in the underground movement of radioactive isotopes

    International Nuclear Information System (INIS)

    Gailledreau, C.

    The physico-chemical state of the radioelements moving underground can influence considerably their migration velocity. In the case of 90 Sr--held on by monmorillonites, apatites, activated aluminum oxide--the occurrence of electronegative colloids, sorbing selectively 90 Sr results in an immediate break-through of this isotope. This phenomenon has been demonstrated in the case of the calcite phosphate reaction. A high pH is generally favorable to 90 Sr sorption (apatite, aluminum oxide). The occurrence of Ca 2+ ions acts very unfavorably on 90 Sr sorption by minerals specifics of this isotope (apatite, aluminum oxide). The same thing occurs with organic matters 137 Cs sorption, attributed to illitic clays, is little sensitive to the nature of the solution. Ruthenium-106 seems to move underground chiefly as a nitrosylruthenium hydroxide complex. This complex would be weakly sorbed on soil colloids by London--Van der Waals forces

  19. Validation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes

    Energy Technology Data Exchange (ETDEWEB)

    Thanh, Tran Thien; Tran, Le Bao; Ton, Thai Van; Chuong, Huynh Dinh; Tao, Chau Van [VNUHCM-Univ. of Science, Ho Chi Minh City (Viet Nam). Dept. of Nuclear Physics; VNUHCM-Univ. of Science, Ho Chi Minh City (Viet Nam). Nuclear Technique Lab.; Tam, Hoang Duc [Ho Chi Minh City Univ. of Pedagogy (Viet Nam). Faculty of Physics; Quang, Ma Thuy [VNUHCM-Univ. of Science, Ho Chi Minh City (Viet Nam). Dept. of Nuclear Physics

    2017-07-15

    In this work, the angular dependent efficiency recorded by collimated NaI(Tl) detector is determined a quantification of the activity of mono- and multi-energy gamma emitting isotopes positioning in a waste drum. The simulated efficiencies using both MCNP5 and Geant4 are in good agreement with experimental results. Referring to these simulated efficiencies, we recalculated the source activity with the highest deviation of 13%.

  20. Laser-spectroscopic nuclear-structure studies on radioactive silver and indium isotopes

    International Nuclear Information System (INIS)

    Dinger, U.

    1988-05-01

    Neutron-deficient silver and neutron-rich indium isotopes were studied by collinear laser spectroscopy. The neutron-deficient nuclei 101 , 103 , 104 , 105 , 105m , 106m Ag were produced as evaporation-residual nuclei in heavy-ion fusion reactions at the mass separator of the GSI in Darmstadt. The fourteen studied indium isotopes and isomers with even mass number in the range 112-126 In were produced by 600-MeV-proton induced fission of a uranium carbide target at the ISOLDE separator in Geneva. The mass-separated ion beam was subsequently deviated electrostatically, neutralized in a sodium vapor and superposed with a c w dye laser. A photon counting system detected the resonance fluorescence of the induced transitions. The hyperfine structure and the isotope shift of the 4d 9 5s 2 2 D 5/2 → 4d 10 6p 2 P 3/2 transition (λ=547.7 nm) in silver and the 5p 2 P 1/2,3/2 → 6s 2 s 1/2 transition (λ=410 respectively 451 nm) in indium were measured. While in indium for the analysis of the data earlier work could be referred to, in silver a detailed analysis of the isotope shift and hyperfine structure was performed by means of ab initio calculations and semi-empirical procedures. Thereby the configuration interactions were especially considered. The nuclear moments were discussed in the framework of existing nuclear models regarding nuclear-spectroscopic informations. (orig./HSI) [de

  1. Validation of radioactive isotope activity measurement in homogeneous waste drum using Monte Carlo codes

    International Nuclear Information System (INIS)

    Thanh, Tran Thien; Tran, Le Bao; Ton, Thai Van; Chuong, Huynh Dinh; Tao, Chau Van; VNUHCM-Univ. of Science, Ho Chi Minh City; Tam, Hoang Duc; Quang, Ma Thuy

    2017-01-01

    In this work, the angular dependent efficiency recorded by collimated NaI(Tl) detector is determined a quantification of the activity of mono- and multi-energy gamma emitting isotopes positioning in a waste drum. The simulated efficiencies using both MCNP5 and Geant4 are in good agreement with experimental results. Referring to these simulated efficiencies, we recalculated the source activity with the highest deviation of 13%.

  2. Radioactive and radiogenic isotopes in sediments from Cooper Creek, Western Arnhem Land

    Energy Technology Data Exchange (ETDEWEB)

    Frostick, A. [Charles Darwin University, Darwin, NT 0909 (Australia); ERISS, GPO Box 461, Darwin, NT 0801 (Australia)], E-mail: alison.frostick@cdu.edu.au; Bollhoefer, A. [ERISS, GPO Box 461, Darwin, NT 0801 (Australia); Parry, D.; Munksgaard, N. [Charles Darwin University, Darwin, NT 0909 (Australia); Evans, K. [ERISS, GPO Box 461, Darwin, NT 0801 (Australia)

    2008-03-15

    Protection of the environment post-mining is a key objective of rehabilitation, especially where runoff and erosion from rehabilitated mine sites could potentially lead to contamination of the surrounding land and watercourses. As part of an overall assessment of the success of rehabilitation at the former Nabarlek uranium (U) mine, an appraisal of stable lead (Pb) isotopes, radionuclides and trace metals within sediments and soils was conducted to determine the off site impacts from a spatial and temporal perspective. The study found localised areas on and adjacent to the site where soils had elevated levels of trace metals and radionuclides. Lead isotope ratios are highly radiogenic in some samples, indicating the presence of U-rich material. There is some indication that erosion products with more radiogenic Pb isotope ratios have deposited in sediments downstream of the former ore body. However, there is no indication that the radiogenic erosion products found on the mine site at present have significantly contaminated sediments further downstream of Cooper Creek.

  3. Radioactive and radiogenic isotopes in sediments from Cooper Creek, Western Arnhem Land

    International Nuclear Information System (INIS)

    Frostick, A.; Bollhoefer, A.; Parry, D.; Munksgaard, N.; Evans, K.

    2008-01-01

    Protection of the environment post-mining is a key objective of rehabilitation, especially where runoff and erosion from rehabilitated mine sites could potentially lead to contamination of the surrounding land and watercourses. As part of an overall assessment of the success of rehabilitation at the former Nabarlek uranium (U) mine, an appraisal of stable lead (Pb) isotopes, radionuclides and trace metals within sediments and soils was conducted to determine the off site impacts from a spatial and temporal perspective. The study found localised areas on and adjacent to the site where soils had elevated levels of trace metals and radionuclides. Lead isotope ratios are highly radiogenic in some samples, indicating the presence of U-rich material. There is some indication that erosion products with more radiogenic Pb isotope ratios have deposited in sediments downstream of the former ore body. However, there is no indication that the radiogenic erosion products found on the mine site at present have significantly contaminated sediments further downstream of Cooper Creek

  4. Extended methods using thick-targets for nuclear reaction data of radioactive isotopes

    Science.gov (United States)

    Ebata, Shuichiro; Aikawa, Masayuki; Imai, Shotaro

    2017-09-01

    The nuclear transmutation is a technology to dispose of radioactive wastes. However, we do not have enough basic data for its developments, such as thick-target yields (TTY) and the interaction cross sections for radioactive material. We suggest two methods to estimate the TTY using inverse kinematics and to obtain the excitation function of the interaction cross sections which is named the thick-target transmission (T3) method. We deduce the energy-dependent conversion relation between the TTYs of the original system and its inverse kinematics, which can be replaced to a constant coefficient in the high energy region. Furthermore we show the usefulness of the T3 method to investigate the excitation function of the 12C + 27Al reaction in the simulation.

  5. Cesium removal using crystalline silicotitanate. Innovative technology summary report

    International Nuclear Information System (INIS)

    1999-05-01

    Approximately 100 million gallons of radioactive waste is stored in underground storage tanks at the Hanford Site, Idaho National Engineering and Environmental Laboratory (INEEL), Oak Ridge Reservation, and Savannah River Site (SRS). Most of the radioactivity comes from 137 Cs, which emits high-activity gamma radiation. The Cesium Removal System is a modular, transportable, ion-exchange system configured as a compact processing unit. Liquid tank waste flows through columns packed with solid material, called a sorbent, that selectively adsorbs cesium and allows the other materials to pass through. The sorbent is crystalline silicotitanate (CST), an engineered material with a high capacity for sorbing cesium from alkaline wastes. The Cesium Removal System was demonstrated at Oak Ridge using Melton Valley Storage Tank (MVST) waste for feed. Demonstration operations began in September 1996 and were completed during June 1997. Prior to the demonstration, a number of ion-exchange materials were evaluated at Oak Ridge with MVST waste. Also, three ion-exchange materials and three waste types were tested at Hanford. These bench-scale tests were conducted in a hot cell. Hanford's results showed that 300 times less sorbent was used by selecting Ionsiv IE-911 over organic ion-exchange resins for cesium removal. This paper gives a description of the technology and discusses its performance, applications, cost, regulatory and policy issues and lessons learned

  6. Charge breeding of radioactive isotopes at the CARIBU facility with an electron beam ion source

    Science.gov (United States)

    Vondrasek, R. C.; Dickerson, C. A.; Hendricks, M.; Ostroumov, P.; Pardo, R.; Savard, G.; Scott, R.; Zinkann, G.

    2018-05-01

    An Electron Beam Ion Source Charge Breeder (EBIS-CB) has been developed at Argonne National Laboratory as part of the californium rare ion breeder upgrade. For the past year, the EBIS-CB has been undergoing commissioning as part of the ATLAS accelerator complex. It has delivered both stable and radioactive beams with A/Q 18% into a single charge state. The operation of this device, challenges during the commissioning phase, and future improvements will be discussed.

  7. Determination of radioactive emission origins based on analyses of isotopic composition

    International Nuclear Information System (INIS)

    Devell, L.

    1987-01-01

    The nature of radioactivity emissions can be determined through gamma spectroscopy of air samples with good precision, which means that the type of source of the emission may be found, e.g. nuclear weapons test, of nuclear power plant accident. Combined with information on wind trajectories it is normally possible to recognize time and area for the emission. In this preliminary study, the knowledge of and preparedness for such measurements are described. (L.E.)

  8. Development and properties of crystalline silicotitanate (CST) ion exchangers for radioactive waste applications

    International Nuclear Information System (INIS)

    Miller, J.E.; Brown, N.E.

    1997-04-01

    Crystalline silicotitanates (CSTs) are a new class of ion exchangers that were jointly invented by researchers at Sandia National Laboratories and Texas A ampersand M University. One particular CST, known as TAM-5, is remarkable for its ability to separate parts-per-million concentrations of cesium from highly alkaline solutions (pH> 14) containing high sodium concentrations (>5M). It is also highly effective for removing cesium from neutral and acidic solutions, and for removing strontium from basic and neutral solutions. Cesium isotopes are fission products that account for a large portion of the radioactivity in waste streams generated during weapons material production. Tests performed at numerous locations with early lab-scale TAM-5 samples established the material as a leading candidate for treating radioactive waste volumes such as those found at the Hanford site in Washington. Thus Sandia developed a Cooperative Research and Development Agreement (CRADA) partnership with UOP, a world leader in developing, commercializing, and supplying adsorbents and associated process technology to commercialize and further develop the material. CSTs are now commercially available from UOP in a powder (UOP IONSIV reg-sign IE-910 ion exchanger) and granular form suitable for column ion exchange operations (UOP IONSIV reg-sign IE-911 ion exchanger). These materials exhibit a high capacity for cesium in a wide variety of solutions of interest to the Department of Energy, and they are chemically, thermally, and radiation stable. They have performed well in tests at numerous sites with actual radioactive waste solutions, and are being demonstrated in the 100,000 liter Cesium Removal Demonstration taking place at Oak Ridge National Laboratory with Melton Valley Storage Tank waste. It has been estimated that applying CSTs to the Hanford cleanup alone will result in a savings of more than $300 million over baseline technologies

  9. Development and properties of crystalline silicotitanate (CST) ion exchangers for radioactive waste applications

    Energy Technology Data Exchange (ETDEWEB)

    Miller, J.E.; Brown, N.E.

    1997-04-01

    Crystalline silicotitanates (CSTs) are a new class of ion exchangers that were jointly invented by researchers at Sandia National Laboratories and Texas A&M University. One particular CST, known as TAM-5, is remarkable for its ability to separate parts-per-million concentrations of cesium from highly alkaline solutions (pH> 14) containing high sodium concentrations (>5M). It is also highly effective for removing cesium from neutral and acidic solutions, and for removing strontium from basic and neutral solutions. Cesium isotopes are fission products that account for a large portion of the radioactivity in waste streams generated during weapons material production. Tests performed at numerous locations with early lab-scale TAM-5 samples established the material as a leading candidate for treating radioactive waste volumes such as those found at the Hanford site in Washington. Thus Sandia developed a Cooperative Research and Development Agreement (CRADA) partnership with UOP, a world leader in developing, commercializing, and supplying adsorbents and associated process technology to commercialize and further develop the material. CSTs are now commercially available from UOP in a powder (UOP IONSIV{reg_sign} IE-910 ion exchanger) and granular form suitable for column ion exchange operations (UOP IONSIV{reg_sign} IE-911 ion exchanger). These materials exhibit a high capacity for cesium in a wide variety of solutions of interest to the Department of Energy, and they are chemically, thermally, and radiation stable. They have performed well in tests at numerous sites with actual radioactive waste solutions, and are being demonstrated in the 100,000 liter Cesium Removal Demonstration taking place at Oak Ridge National Laboratory with Melton Valley Storage Tank waste. It has been estimated that applying CSTs to the Hanford cleanup alone will result in a savings of more than $300 million over baseline technologies.

  10. Experimental study on cesium immobilization in struvite structures

    International Nuclear Information System (INIS)

    Wagh, Arun S.; Sayenko, S.Y.; Shkuropatenko, V.A.; Tarasov, R.V.; Dykiy, M.P.; Svitlychniy, Y.O.; Virych, V.D.; Ulybkina, E.A.

    2016-01-01

    Graphical abstract: X-ray diffraction patterns of Ceramicrete forms, green representing struvite-K, and red, struvite-(K,Cs) with 10 wt.% CsCl in it. Cs substitutes partially for K, which immobilizes Cs at room temperature by the acid–base reaction. - Highlights: • Struvite structure of Ceramicrete is an excellent host of radioactive cesium. • The volatility problem of cesium can be avoided by this method. • This method can be used to produce cesium waste forms in ambient conditions. • It can also be used to pretreat cesium in glass vitrification technology. • It also provides a method to produce safe sealed radioactive sources of cesium. - Abstract: Ceramicrete, a chemically bonded phosphate ceramic, was developed for nuclear waste immobilization and nuclear radiation shielding. Ceramicrete products are fabricated by an acid–base reaction between magnesium oxide and mono potassium phosphate that has a struvite-K mineral structure. In this study, we demonstrate that this crystalline structure is ideal for incorporating radioactive Cs into a Ceramicrete matrix. This is accomplished by partially replacing K by Cs in the struvite-K structure, thus forming struvite-(K, Cs) mineral. X-ray diffraction and thermo-gravimetric analyses are used to confirm such a replacement. The resulting product is non-leachable and stable at high temperatures, and hence it is an ideal matrix for immobilizing Cs found in high-activity nuclear waste streams. The product can also be used for immobilizing secondary waste streams generated during glass vitrification of spent fuel, or the method described in this article can be used as a pretreatment method during glass vitrification of high level radioactive waste streams. Furthermore, it suggests a method of producing safe commercial radioactive Cs sources.

  11. Experimental study on cesium immobilization in struvite structures

    Energy Technology Data Exchange (ETDEWEB)

    Wagh, Arun S., E-mail: asw@anl.gov [Environmental Science Division, Argonne National Laboratory, 9700 S. Cass Avenue, IL 60439 (United States); Sayenko, S.Y.; Shkuropatenko, V.A.; Tarasov, R.V.; Dykiy, M.P.; Svitlychniy, Y.O.; Virych, V.D.; Ulybkina, E.A. [National Science Center, Kharkov Institute of Physics and Technology, Kharkov (Ukraine)

    2016-01-25

    Graphical abstract: X-ray diffraction patterns of Ceramicrete forms, green representing struvite-K, and red, struvite-(K,Cs) with 10 wt.% CsCl in it. Cs substitutes partially for K, which immobilizes Cs at room temperature by the acid–base reaction. - Highlights: • Struvite structure of Ceramicrete is an excellent host of radioactive cesium. • The volatility problem of cesium can be avoided by this method. • This method can be used to produce cesium waste forms in ambient conditions. • It can also be used to pretreat cesium in glass vitrification technology. • It also provides a method to produce safe sealed radioactive sources of cesium. - Abstract: Ceramicrete, a chemically bonded phosphate ceramic, was developed for nuclear waste immobilization and nuclear radiation shielding. Ceramicrete products are fabricated by an acid–base reaction between magnesium oxide and mono potassium phosphate that has a struvite-K mineral structure. In this study, we demonstrate that this crystalline structure is ideal for incorporating radioactive Cs into a Ceramicrete matrix. This is accomplished by partially replacing K by Cs in the struvite-K structure, thus forming struvite-(K, Cs) mineral. X-ray diffraction and thermo-gravimetric analyses are used to confirm such a replacement. The resulting product is non-leachable and stable at high temperatures, and hence it is an ideal matrix for immobilizing Cs found in high-activity nuclear waste streams. The product can also be used for immobilizing secondary waste streams generated during glass vitrification of spent fuel, or the method described in this article can be used as a pretreatment method during glass vitrification of high level radioactive waste streams. Furthermore, it suggests a method of producing safe commercial radioactive Cs sources.

  12. Nuclear structure from radioactive decay

    International Nuclear Information System (INIS)

    Wood, J.L.

    1991-01-01

    This report discusses nuclear structure from radioactive decay of the following: Neutron-Deficient Iridium Isotopes; Neutron-Deficient Platinum Isotopes; Neutron-Deficient Gold Isotopes; Neutron-Deficient Mercury Isotopes; Neutron-Deficient Thallium Isotopes; Neutron-Deficient Lead Isotopes; Neutron-Deficient Samarium Isotopes; Neutron-Deficient Promethium Isotopes; Neutron-Deficient Neodymium Isotopes; and Neutron-Deficient Praseodymium Isotopes. Also discussed are Nuclear Systematics and Models

  13. Device for flame combustion of liquid or solid samples in radioactive isotope trace indication

    International Nuclear Information System (INIS)

    Kaartinen, N.H.

    1979-01-01

    The plant or animal tissue containing T and/or 14 C isotope indicator is in a small ignition cage within the combustion chamber. The ignition cage consists of Nichrome which supports the ignition procedure. The combustion chamber is maintained at a temperature above the condensation temperature of the vapours escaping from the tissue (e.g. H 2 O). The thimble type ignition cage burns uniformly together with the sample. It is no longer necessary to make pellets of the sample. (DG) [de

  14. Cesium uptake capacity of simulated ferrocyanide tank waste. Interim report FY 1994, Ferrocyanide Safety Project

    International Nuclear Information System (INIS)

    Burgeson, I.E.; Bryan, S.A.; Burger, L.E.

    1994-09-01

    The objective of this project is to determine the capacity for 137 CS uptake by mixed metal ferrocyanides present in Hanford waste tanks, and to assess the potential for aggregation of these 137 CS exchanged materials to form tank ''hot-spots.'' This research, performed at the Pacific Northwest Laboratory (PNL) for the Westinghouse Hanford Company (WHC), stems from concerns of possible localized radiolytic heating within the tanks. If radioactive cesium is exchanged and concentrated by the remaining nickel ferrocyanide present in the tanks, this heating could cause temperatures to rise above the safety limits specified for the ferrocyanide tanks. For the purposes of this study, two simulants, In-Farm-2 and U-Plant-2, were chosen to represent the wastes generated by the scavenging processes. These simulants were formulated using protocols from the original cesium scavenging campaign. Later additions of cesium-rich wastes from various processes also were considered. The simulants were prepared and centrifuged to obtain a moist ferrocyanide sludge. The centrifuged sludges were treated with the original supernate spiked with a known amount of cesium nitrate. After analysis by flame atomic absorption spectrometry, distribution coefficients (K d ) were calculated. The capacity of solid waste simulants to exchange radioactive cesium from solution was examined. Initial results showed that the greater the molar ratio of cesium to cesium nickel ferrocyanide, the less effective the exchange of cesium from solution. The theoretical capacity of 2 mol cesium per mol of nickel ferrocyanide was not observed. The maximum capacity under experimental conditions was 0.35 mol cesium per mol nickel ferrocyanide. Future work on this project will examine the layering tendency of the cesium nickel ferrocyanide species

  15. Adsorption of iodine and cesium onto some cement materials

    Energy Technology Data Exchange (ETDEWEB)

    Mine, Tatsuya [Mitsui Shipbuilding and Engineering Co. Ltd., Tokyo (Japan); Mihara, Morihiro; Ito, Masaru [Power Reactor and Nuclear Fuel Development Corp., Tokai, Ibaraki (Japan). Tokai Works; Kato, Hiroshige [IDC, Tokai, Ibaraki (Japan)

    1997-06-01

    Cement materials, being expected to be used in structural materials in underground disposals of radioactive wastes, may adsorb nuclides resulting in retardation of their migration in environment. In this report adsorption behaviors of cement pastes toward iodine (as anion) and cesium (as cation) were studied. Adsorption of iodine was remarkable for OPC and MHP pastes that are known to have high molar ratio CaO/SiO{sub 2}, partition coefficient being 100 ml/g for initial tracer concentration of 10{sup -5} mol/l. Partition coefficient for cesium for PFA paste was found to be 5 ml/g on average. (S. Ohno)

  16. Adsorption of iodine and cesium onto some cement materials

    International Nuclear Information System (INIS)

    Mine, Tatsuya; Mihara, Morihiro; Ito, Masaru

    1997-06-01

    Cement materials, being expected to be used in structural materials in underground disposals of radioactive wastes, may adsorb nuclides resulting in retardation of their migration in environment. In this report adsorption behaviors of cement pastes toward iodine (as anion) and cesium (as cation) were studied. Adsorption of iodine was remarkable for OPC and MHP pastes that are known to have high molar ratio CaO/SiO 2 , partition coefficient being 100 ml/g for initial tracer concentration of 10 -5 mol/l. Partition coefficient for cesium for PFA paste was found to be 5 ml/g on average. (S. Ohno)

  17. Measurement of the stellar (n,γ) cross section of the shortlived radioactive isotope 147Pm

    International Nuclear Information System (INIS)

    Gerstenhoefer, T.W.

    1993-05-01

    During helium burning in the red giant phase of stellar evolution, nuclei with A>60 are produced by the slow neutron capture process (s-process). Starting from the iron group isotopes, the synthesis path works along the valley of beta stability by subsequent neutron captures and beta decays. An important feature of the s-process is the occurence of branchings in this path whenever unstable isotopes with half-lives comparable to the typical neutron capture time scale of about one year are encountered. The analysis of the corresponding abundance patterns can be used to derive estimates for the stellar neutron flux, temperature, and density. Quantitative branching analyses require reliable (n,γ) cross sections for the branch point nuclei. This report presents the first ever measured (n,γ) cross section for the branch point 147 Pm (t 1/2 =2.6 yr) in the neutron energy range 1 n 7 Li(p,n) 7 Be reaction that allowes to simulate a quasi-stellar neutron spectrum. To this end, the rf gas discharge ion source and optical components of the Karlsruhe 3.75 Van de Graaff accelerator were revised. Last but not least, the radiation hazard of the 147 Pm sample (180 GBq) had to be accounted for. In addition of the measurements on 147 Pm, the stellar (n,γ) cross section on its stable daughter, 147 Sm was also determined, mainly in order to verify the experimental technique with Moxon-Rae detectors. (orig.)

  18. Partitioning of Radioactive cesium in aquatic environment

    Energy Technology Data Exchange (ETDEWEB)

    Ewais, T A [Nuclear Power Plant Authority, Cairo (Egypt); Grant, A [Universty of East Anglia, School of Environment, (United Kingdom); Abdel-Fattah, A T [Atomic Energy Authority, Cairo (Egypt)

    1997-12-31

    Scavenging of radionuclides by intertidal estuarine sediment are affected by several factors. Such sediment collected from sea coast of norfolk county, UK, were subjected to specific analytical study to illustrate their physico-chemical properties on their sorption behavior of {sup 134} Cs. Clay fraction showed high uptake or KD values compared to other sediment fractions. Kinetic analysis of the uptake curves showed a very fast followed by a vary slow one. On the other hand, the noticeable uptake by sand fraction (63-90 Mm) was referred to the fine clay particles coating the sand particles. Other environmental factors affecting the KD values such as water salinity, grain size,sediment treatment, and PH are discussed in the text. 9 figs., 1 tab.

  19. Preliminary Evaluation of Cesium Distribution for Wet Sieving Process Planned for Soil Decontamination in Japan - 13104

    Energy Technology Data Exchange (ETDEWEB)

    Enokida, Y.; Tanada, Y.; Hirabayashi, D. [Graduate School of Engineering, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan); Sawada, K. [EcoTopia Science Institute, Nagoya University, 1 Furo-cho Nagoya-shi, Aichi-ken, 4648603 (Japan)

    2013-07-01

    For the purpose of decontaminating radioactive cesium from a huge amount of soil, which has been estimated to be 1.2x10{sup 8} m{sup 3} by excavating to a 5-cm depth from the surface of Fukushima Prefecture where a severe nuclear accident occurred at TEPCO's power generating site and has emitted a significant amount of radioactive materials, mainly radioactive cesium, a wet sieving process was selected as one of effective methods available in Japan. Some private companies have demonstrated this process for soil treatment in the Fukushima area by testing at their plants. The results were very promising, and a full-fledged application is expected to follow. In the present study, we spiked several aqueous samples containing soil collected from an industrial wet sieving plant located near our university for the recycling of construction wastes with non-radioactive cesium hydroxide. The present study provides scientific data concerning the effectiveness in volume reduction of the contaminated soil by a wet sieving process as well as the cesium distribution between the liquid phase and clay minerals for each sub-process of the full-scale one, but a simulating plant equipped with a process of coagulating sedimentation and operational safety fundamentals for the plant. Especially for the latter aspect, the study showed that clay minerals of submicron size strongly bind a high content of cesium, which was only slightly removed by coagulation with natural sedimentation (1 G) nor centrifugal sedimentation (3,700 G) and some of the cesium may be transferred to the effluent or recycled water. By applying ultracentrifugation (257,000 G), most of submicron clay minerals containing cesium was removed, and the cesium amount which might be transferred to the effluent or recycled water, could be reduced to less than 2.3 % of the original design by the addition of a cesium barrier consisting of ultracentrifugation or a hollow fiber membrane. (authors)

  20. Recovery of cesium

    Science.gov (United States)

    Izatt, Reed M.; Christensen, James J.; Hawkins, Richard T.

    1984-01-01

    A process of recovering cesium ions from mixtures of ions containing them and other ions, e.g., a solution of nuclear waste materials, which comprises establishing a separate source phase containing such a mixture of ions, establishing a separate recipient phase, establishing a liquid membrane phase in interfacial contact with said source and recipient phases, said membrane phase containing a ligand, preferably a selected calixarene as depicted in the drawing, maintaining said interfacial contact for a period of time long enough to transport by said ligand a substantial portion of the cesium ion from the source phase to the recipient phase, and recovering the cesium ion from the recipient phase. The separation of the source and recipient phases may be by the membrane phase only, e.g., where these aqueous phases are emulsified as dispersed phases in a continuous membrane phase, or may include a physical barrier as well, e.g., an open-top outer container with an inner open-ended container of smaller cross-section mounted in the outer container with its open bottom end spaced from and above the closed bottom of the outer container so that the membrane phase may fill the outer container to a level above the bottom of the inner container and have floating on its upper surface a source phase and a recipient phase separated by the wall of the inner container as a physical barrier. A preferred solvent for the ligand is a mixture of methylene chloride and carbon tetrachloride.

  1. Chemisorption of organic iodine compounds forming from fission isotopes of radioactive iodine

    International Nuclear Information System (INIS)

    Tot, G.; Galina, F.; Zel'd, E.

    1977-01-01

    Studied is ethyl iodine adsorption, labelled by iodine 131, on palladium black and on aluminium oxide activized by palladium. The desorption of adsorbed iodine in the temperature range of 20-600 deg C by the mass spectroscopy and thermal gravimetric methods was investigated. At the ethyl iodine and palladium interaction the bond between carbon and iodine in the ethyl iodine molecule breaks down and extracting iodine reacts with palladium, forming a stable compound at high temperatures. Desorption of adsorbed iodine is insignificant up to the temperatures of 250-300 deg C. Thus, sorbents, containing palladium, may be successfully applied for iodine absorption from the organic iodine compounds. These compounds spontaneously appear from the iodine fragment ratio isotopes during their interaction with some environmental organic impurities

  2. Geological interpretation of Eastern Cuba Laterites from an airborne magnetic and radioactive isotope survey

    Energy Technology Data Exchange (ETDEWEB)

    Batista, J.A; Blanco, J [Departamento de Geologia, Instituto Superior Minero Metalurgico de Moa, (Cuba); Perez-Flores, M.A [Centro de Investigacion Cientifica y Educacion Superior de Ensenada, Baja California (Mexico)

    2008-04-15

    In eastern Cuba area several geophysical techniques have been applied to distinguish the main geological characteristics of the laterites which are of economical importance for the extraction of iron, nickel and chrome. The geophysical measurements include an aeromagnetic survey and thorium (eTh), potassium (K) and uranium (eU) isotope measurements. The results of gamma spectrometer measurements make a distinction between laterite reservoirs. The application of the magnetic and isotope methods allowed the determination of the distribution and development of the laterite crust, as well as the determination of hydrothermal alterations affecting the laterites, which is very useful for mining exploration and exploitation. Such alterations indicate the presence of silicates, which have negative effects on the metallurgic process. It is known that laterite crust has a high content of eU and eTh. [Spanish] Se han utilizado varias tecnicas geofisicas en la region oriental de Cuba para distinguir las principales caracteristicas geologicas de las lateritas, que poseen importancia economica para la extraccion de hierro, niquel y cobalto. Las mediciones geofisicas incluyen un estudio aeromagnetico y mediciones de isotopos de torio (eTh), potasio (K) y uranio (eU). Los resultados de las mediciones espectrometricas establecen diferencias entre los yacimientos de lateritas. De la aplicacion del metodo magnetico e isotopico se determino la distribucion y desarrollo de las cortezas lateriticas, asi como la ubicacion de alteraciones hidrotermales que afectan a las lateritas, lo cual es muy util durante la exploracion y explotacion minera. Esas alteraciones indican la presencia de silicatos, que tienen un efecto negativo en el proceso metalurgico. Se conoce que las cortezas lateriticas tienen altos contenidos de eU y eTh. De los contenidos de eU y eTh se infiere que las lateritas de la region de Moa se formaron antes que las de Mayari. De estas mediciones fue posible inferir el

  3. Application of naturally occurring isotopes and artificial radioactive tracer for monitoring water flooding in oil field

    International Nuclear Information System (INIS)

    Ahmad, M.; Khan, I.H.; Farooq, M.; Tasneem, M.A.; Rafiq, M.; Din, U.G.; Gul, S.

    2002-03-01

    Water flooding is an important operation to enhance oil recovery. Water is injected in the oil formation under high pressure through an injection well. Movement of the injected water is needed to be traced to test the performance of water flood, investigate unexpected anomalies in flow and verify suspected geological barriers or flow channels, etc. In the present study environmental isotopes and artificial radiotracer (tritium) were used at Fimkassar Oil Field of Oil and Gas Development Company Limited (OGDCL) where water flooding was started in March 1996 in Sakessar formation to maintain its pressure and enhance the oil recovery. Environmental isotopes: /sup 18/O, /sup 2/H and /sup 3/H, and chloride contents were used to determine the breakthrough/transit time and contribution of fresh injected water. Water samples were collected from the injection well, production well and some other fields for reference indices of Sakessar Formation during June 1998 to August 1999. These samples were analyzed for the /sup 18/O, /sup 2/H and /sup 3/H, and chloride contents. Results show that the water of production well is mixture of fresh water and formation water. The fresh water contribution varied from 67% to 80%, while remaining component was the old recharged formation water. This percentage did not change significantly from the time of break-through till the last sampling which indicates good mixing in the reservoir and absence of any quick channel. The initial breakthrough time was 27 months as the fresh water contributed significantly in the first appearance of water in the production well in June 1998. Tritium tracer, which was injected in November 1998, appeared in the production well after 8 months. It show that breakthrough time decreased with the passage of time. /sup 14/C of inorganic carbon in the water in Chorgali and Sakessar Formations was also analyzed which indicates that the water is at least few thousand years old. (author)

  4. Measurements of neutron yields and radioactive isotope transmutation in collisions of relativistic ions with heavy nuclei

    International Nuclear Information System (INIS)

    Brandt, R.

    1999-01-01

    The paper is based on the report presented at the 85th Session of the JINR Scientific Council. Some aspects of experimental studies of the problem of reprocessing radioactive wastes by means of transmutation in the fields of neutrons generated by relativistic particle beams are discussed. Research results on measurement of neutron yields in heavy targets irradiated with protons at energies up to 3.7 GeV as well as transmutation cross sections of some fission products (I-129) and actinides (Np-237) using radiochemical methods, activation detectors, solid state nuclear track detectors and other methods are presented. Experiments have been performed at the accelerator complex of the Laboratory of High Energies, JINR. Analogous results obtained by other research groups are also discussed

  5. Environmental assessment for the relocation and storage of isotopic heat sources, Hanford Site, Richland, Washington

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-06-01

    As part of a bilateral agreement between the Federal Minister for Research and Technology of the Federal Republic of Germany (FRG) and the DOE, Pacific Northwest National Laboratory (PNNL) developed processes for the treatment and immobilization of high-level radioactive waste. One element of this bilateral agreement was the production of sealed isotopic heat sources. During the mid-1980s, 30 sealed isotopic heat sources were manufactured. The sources contain a total of approximately 8.3 million curies consisting predominantly of cesium-137 and strontium-90 with trace amounts of transuranic contamination. Currently, the sources are stored in A-Cell of the 324 Building. Intense radiation fields from the sources are causing the cell windows and equipment to deteriorate. Originally, it was not intended to store the isotopic heat sources for this length of time in A-cell. The 34 isotopic heat sources are classified as remote handled transuranic wastes. Thirty-one of the isotopic heat sources are sealed, and seals on the three remaining isotopic heat sources have not been verified. However, a decision has been made to place the remaining three isotopic heat sources in the CASTOR cask(s). The Washington State Department of Health (WDOH) has concurred that isotopic heat sources with verified seals or those placed into CASTOR cask(s) can be considered sealed (no potential to emit radioactive air emissions) and are exempt from WAC Chapter 246-247, Radiation Protection-Air Emissions.

  6. Environmental assessment for the relocation and storage of isotopic heat sources, Hanford Site, Richland, Washington

    International Nuclear Information System (INIS)

    1997-06-01

    As part of a bilateral agreement between the Federal Minister for Research and Technology of the Federal Republic of Germany (FRG) and the DOE, Pacific Northwest National Laboratory (PNNL) developed processes for the treatment and immobilization of high-level radioactive waste. One element of this bilateral agreement was the production of sealed isotopic heat sources. During the mid-1980s, 30 sealed isotopic heat sources were manufactured. The sources contain a total of approximately 8.3 million curies consisting predominantly of cesium-137 and strontium-90 with trace amounts of transuranic contamination. Currently, the sources are stored in A-Cell of the 324 Building. Intense radiation fields from the sources are causing the cell windows and equipment to deteriorate. Originally, it was not intended to store the isotopic heat sources for this length of time in A-cell. The 34 isotopic heat sources are classified as remote handled transuranic wastes. Thirty-one of the isotopic heat sources are sealed, and seals on the three remaining isotopic heat sources have not been verified. However, a decision has been made to place the remaining three isotopic heat sources in the CASTOR cask(s). The Washington State Department of Health (WDOH) has concurred that isotopic heat sources with verified seals or those placed into CASTOR cask(s) can be considered sealed (no potential to emit radioactive air emissions) and are exempt from WAC Chapter 246-247, Radiation Protection-Air Emissions

  7. Sorption kinetics of cesium on hydrous titanium dioxide

    International Nuclear Information System (INIS)

    Altas, Y.; Tel, H.; Yaprak, G.

    2003-01-01

    Two types of hydrous titanium dioxide possessing different surface properties were prepared and characterized to study the sorption kinetics of cesium. The effect of pH on the adsorption capacity were determined in both type sorbents and the maximum adsorption percentage of cesium were observed at pH 12. To elucidate the kinetics of ion-exchange reaction on hydrous titanium dioxide, the isotopic exchange rates of cesium ions between hydrous titanium dioxides and aqueous solutions were measured radiochemically and compared with each other. The diffusion coefficients of Cs + ion for Type1 and Type2 titanium dioxides at pH 12 were calculated as 2.79 x 10 -11 m 2 s -1 and 1.52 x 10 -11 m 2 s -1 , respectively, under particle diffusion controlled conditions. (orig.)

  8. Determination of the radioactive concentration of 137Cs in water

    International Nuclear Information System (INIS)

    1986-01-01

    The recently accepted standard method to determine the radioactive concentration of 137 Cs in water is based on the selective retention of cesium ions on ammonium-phosphorous-molybdate followed by the dissolution of the sorbent and the selective precipitation of cesium-hexa-chloro-platinate. The radioactive concentration is determined by the measurement of β disintegration rate of the preparate. (V.N.)

  9. Isotopic compositions of boron in sediments and their implications

    Digital Repository Service at National Institute of Oceanography (India)

    Shirodkar, P.V.; Yingkai, X.

    The abundance and isotopic compositions of boron in sediments from the salt lakes of Qaidam Basin, China have been determined by thermal ionization mass spectrometry of cesium borate. The results show large variations in the isotopic compositions...

  10. A method of and apparatus for, monitoring the radioactivity of a plurality of samples incorporating lower energy beta-emitting isotopes

    International Nuclear Information System (INIS)

    Warner, G.T.; Potter, C.G.

    1981-01-01

    A method for monitoring the radioactivity of a number of samples incorporating low energy beta-emitting isotopes which allows the simultaneous precipitation of many samples with a minimum of sample handling, is described. The samples are placed on a support so that they are not overlapping, the support and sample are permeated with liquid or gel scintillant and the sample areas are scanned. (U.K.)

  11. Isotopic techniques in radioactive waste disposal site evaluation: a method for reducing uncertainties I. T, T/3He, 4He, 14C, 36Cl

    International Nuclear Information System (INIS)

    Muller, A.B.

    1981-01-01

    This paper introduces five of the isotopic techniques which can help reduce uncertainties associated with the assessment of radioactive waste disposal sites. The basic principles and practical considerations of these best known techniques have been presented, showing how much additional site specific information can be acquired at little cost or consequence to containment efficiency. These methods, and the more experimental methods appearing in the figure but not discussed here, should be considered in any detailed site characterization, data collection and analysis

  12. Retrospective radiation-hygienic assessment of cesium-137 intake with feeding in the organisms of the Altai Territory habitants

    International Nuclear Information System (INIS)

    Meshkov, N.A.; Val'tseva, E.A.

    2016-01-01

    Radioactive precipitations as the result of atmospheric nuclear tests on the Semipalatinsk test site turned to local soil contamination by cesium-137 on the territory of the Altai Territory and Gorny Altai. The distribution of long-lived radioisotopes, cesium-137 in particular, in the main food staffs for local population is investigated. The retrospective analysis of cesium-137 specific activity in food products produced on these territories is carried out. It is ascertained that cesium-137 in meat has the general contribution to intake with food into organisms of adult population [ru

  13. Cesium reservoir and interconnective components

    International Nuclear Information System (INIS)

    1994-03-01

    The program objective is to demonstrate the technology readiness of a TFE (thermionic fuel element) suitable for use as the basic element in a thermionic reactor with electric power output in the 0.5 to 5.0 MW range. A thermionic converter must be supplied with cesium vapor for two reasons. Cesium atoms adsorbed on the surface of the emitter cause a reduction of the emitter work function to permit high current densities without excessive heating of the emitter. The second purpose of the cesium vapor is to provide space-charge neutralization in the emitter-collector gap so that the high current densities may flow across the gap unattenuated. The function of the cesium reservoir is to provide a source of cesium atoms, and to provide a reserve in the event that cesium is lost from the plasma by any mechanism. This can be done with a liquid cesium metal reservoir in which case it is heated to the desired temperature with auxiliary heaters. In a TFE, however, it is desirable to have the reservoir passively heated by the nuclear fuel. In this case, the reservoir must operate at a temperature intermediate between the emitter and the collector, ruling out the use of liquid reservoirs. Integral reservoirs contained within the TFE will produce cesium vapor pressures in the desired range at typical electrode temperatures. The reservoir material that appears to be the best able to meet requirements is graphite. Cesium intercalates easily into graphite, and the cesium pressure is insensitive to loading for a given intercalation stage. The goals of the cesium reservoir test program were to verify the performance of Cs-graphite reservoirs in the temperature-pressure range of interest to TFE operation, and to test the operation of these reservoirs after exposure to a fast neutron fluence corresponding to seven year mission lifetime. In addition, other materials were evaluated for possible use in the integral reservoir

  14. Social aspects concerning the cesium-137 accident

    International Nuclear Information System (INIS)

    Chaves, Elza Guedes

    1997-01-01

    The present work aims to understand how social representations constructed upon nuclear energy have influenced on molding and orienting public's behavior in the presence of the accident that occurred in Goiania with the capsule of Cesium-137. As a starting point, it is accepted here that panic caused by that accident could be properly understood only if dimension of subjectivity is taken into consideration. This perspective is required whenever events that put human life and environment in risk happen. Facing the accident, people internalized radioactivity, an unknown element, as certainty of cancer and death despite the fact that cancer and death could only outcome in case there had been excessive exposure to radioactivity. (author)

  15. Labeling pharmaceuticals with radioactive isotopes. Technical progress report, December 1, 1975--November 30, 1976

    International Nuclear Information System (INIS)

    Blau, M.; Bender, M.A.

    1976-01-01

    The purpose of this research is to prepare iodo- and bromo-aliphatic amino acid analogs labeled with γ-emitting isotopes ( 131 I, 123 I and 77 Br) for possible use as pancreas localizing agents. Studies on the halogen exchange reaction (I- for Cl-) for the synthesis of β-iodo-α-aminobutyric acid (a valine analog) have suggested that the iodo compound was formed initially. However, the desired compound cannot be isolated because of its chemical instability. Distribution studies in rats with the crude halogen exchange reaction mixture confirmed this finding. Studies on the addition of hydrogen iodine to allylglycine under various conditions for the synthesis of γ-iodo-α-aminopentanoic acid (a leucine analog) suffered the same obstacle; the chemical instability of the desired iodo compound precludes isolation and characterization. Convinced that the iodo analogs were too unstable for use as practical localizing agents, we turned to the possible use of Br for CH 3 substituted amino acids. The 14 C labeled β-bromo-α-aminobutyric acid methyl ester was synthesized. This methyl ester will be hydrolyzed and the distribution of free amino acid will be studied. Labeled with 77 Br this compound might be useful for pancreas localization

  16. Astrophysical Shrapnel: Discriminating Among Near-Earth Stellar Explosion Sources of Live Radioactive Isotopes

    CERN Document Server

    Fry, Brian J; Ellis, John R

    2015-01-01

    We consider the production and deposition on Earth of isotopes with half-lives in the range 10$^{5}$ to 10$^{8}$ years that might provide signatures of nearby stellar explosions, extending previous analyses of Core-Collapse Supernovae (CCSNe) to include Electron-Capture Supernovae (ECSNe), Super-Asymptotic Giant Branch (SAGBs) stars, Thermonuclear/Type Ia Supernovae (TNSNe), and Kilonovae/Neutron Star Mergers (KNe). We revisit previous estimates of the $^{60}$Fe and $^{26}$Al signatures, and extend these estimates to include $^{244}$Pu and $^{53}$Mn. We discuss interpretations of the $^{60}$Fe signals in terrestrial and lunar reservoirs in terms of a nearby stellar ejection ~2.2 Myr ago, showing that (i) the $^{60}$Fe yield rules out the TNSN and KN interpretations, (ii) the $^{60}$Fe signals highly constrain a SAGB interpretation but do not completely them rule out, (iii) are consistent with a CCSN origin, and (iv) are highly compatible with an ECSN interpretation. Future measurements could resolve the radio...

  17. Analysis of gaseous-phase stable and radioactive isotopes in the unsaturated zone, Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Yang, I.C.; Haas, H.H.; Weeks, E.P.; Thorstenson, D.C.

    1985-01-01

    The Nevada Nuclear Waste Storage Investigations Project of the US Department of Energy provides that agency with data for evaluating volcanic tuff beneath Yucca Mountain, Nevada, to determine its suitability for a potential repository of high-level radioactive waste. Thickness of the unsaturated zone, which consists of fractured, welded and nonwelded tuff, is about 1640 to 2460 feet (500 to 750 meters). One question to be resolved is an estimate of minimum ground-water traveltime from the disturbed zone of the potentail repository to the accessible environment. Another issue is the potential for diffusive or convective gaseous transport of radionuclides from an underground facility in the unsaturated zone to the accessible environment. Gas samples were collected at intervals to a depth of 1200 feet from the unsaturated zone at Yucca Mountain, Nevada. Samples were analyzed for major atmospheric gases; carbon dioxide in the samples was analyzed for carbon-14 activity and for delta 13 C; water vapor in the samples was analyzed for deuterium and oxygen-18. These data could provide insight into the nature of unsaturated zone transport processes. 15 refs., 4 figs., 4 tabs

  18. Sorption behaviour of some radioactive isotopes on treated fly ash. Vol. 3

    Energy Technology Data Exchange (ETDEWEB)

    Abdel Raouf, M W; El-Dessouky, M I; Aly, H F [Hot Laboratories Center, Atomic Energy Authority, Cairo, (Egypt)

    1996-03-01

    Fly ash is obtained as a by-product from burning mazoute (high molecular weight hydrocarbon) at Northern Cairo Electric Power Generator, was ordinarily disposed in land fill. The carbonaceous material of fly ash was investigated as a possible sorbent for some fission products radionuclides: Cs{sup 134}, Co{sup 60}, and Eu{sup 142+154} at room temperature. The original fly ash was prepared for adsorption studies by sieving to different particle sizes (fractions), and repeated washing by tap water to neutral PH. Some fractions were further treated (after neutralization) by dilute HCl or ethyl alcohol and other fractions were heated at 200, 500, and 800 degree C. The results obtained from sorption on treated fly ash revealed that the percentage uptake (%U) was in accordance with the valency of the cation used: Eu{sup 3+}>Co{sup 2+}>>Cs{sup +} at medium hydrogen ion concentrations. The heated samples at different temperatures showed that % U obeyed the order: 800 degree C >200 degree C. Comparative studies were conducted with pyrolysis residue of domestic waste showed analogous trend in sorption studies. The feasibility of fly ash as a very cheap material in the removal of different fission products from liquid radioactive waste was assessed.

  19. Studies of High-T$_{c}$ Superconductors Doped with Radioactive Isotopes

    CERN Multimedia

    Alves, E J; Goncalves marques, J; Cardoso, S; Lourenco, A A; Sousa, J B

    2002-01-01

    %title\\\\ \\\\We propose to study High T$_{c} $ Superconductors~(HTSc) doped with radioactive elements at ISOLDE, in order to investigate some of the problems that persist after use of conventional characterization techniques. Three main topics are proposed: \\begin{enumerate} \\item Characterization of the order/disorder of Hg in the Hg-planes of the HTSc family Hg$_{1}$Ba$_{2}$R$_{(n-1)}$Cu$_{n}$O$_{(2n+2+\\delta)}$ (T$_{c}$ > 130 K) due to defects or impurities such as C and Au. \\item Studies of the doping of Infinite Layers Cuprates (RCuO$_{2}$)$_{n}$, R=Ca, Sr or Ba, using unstable nuclei of the alkaline-earth (IIA) group which decay to the alkaline nuclei (IA) group. The purpose is to introduce charge carriers in these materials by changing the valence of the cations during the nuclear transmutation. The possibility of using ion implantation to introduce directly an alkaline dopant will also be studied. \\item Studies of the Hg/Au doping of high quality YBa$_{2}$Cu$_{3}$O$_{6+x}$ thin films. We intend to chara...

  20. Formation, decomposition and cesium adsorption mechanisms of highly alkali-tolerant nickel ferrocyanide prepared by interfacial synthesis

    International Nuclear Information System (INIS)

    Ichikawa, Tsuneki; Yamada, Kazuo; Osako, Masahiro; Haga, Kazuko

    2017-01-01

    Highly alkali-tolerant nickel ferrocyanide was prepared as an adsorbent for preventing the leaching of radioactive cesium from municipal solid waste incinerator fly ash containing large amounts of calcium hydroxide and potassium chloride, which act as an alkaline source and the suppressor for cesium adsorption, respectively. Nickel ferrocyanide prepared by contacting concentrated nickel and ferrocyanide solutions without mixing adsorbed cesium ions in alkaline conditions even the concentration of coexisting potassium ions was more than ten thousand times higher than that of the cesium ions. Large particles of nickel ferrocyanide slowly grew at the interface between the two solutions, which reduced the surface energy of the particles and therefore increased the alkali tolerance. The interfacially-synthesized nickel ferrocyanide was possible to prevent the leaching of radioactive cesium from cement-solidified fly ash for a long period. The mechanisms of the formation, selective cesium adsorption, and alkali-induced decomposition of the nickel ferrocyanide were elucidated. Comparison of the cesium adsorption mechanism with that of the other adsorbents revealed that an adsorbent can selectively adsorb cesium ions without much interference from potassium ions, if the following conditions are fulfilled. 1) The adsorption site is small enough for supplying sufficient electrostatic energy for the dehydration of ions adsorbed. 2) Both the cesium and potassium ions are adsorbed as dehydrated ions. 3) The adsorption site is flexible enough for permitting the penetration of dehydrated ions with the size comparable to that of the site. (author)

  1. Application of Radioactive and Stable Isotopes to Trace Anthropogenic Pollution in the Baltic Sea

    International Nuclear Information System (INIS)

    Lujaniene, G.; Valiulis, D.; Remeikaitė-Nikienė, N.; Barisevičiūtė, R.; Stankevičius, A.; Kulakauskaitė, I.; Mažeika, J.; Petrošius, R.; Jokšas, K.; Li, H.-C.; Garnaga, G.; Povinec, P.

    2015-01-01

    The Baltic Sea is one of the seas most contaminated by various pollutants including the chemical munitions dumped after the Second World War. Pu isotopes, Δ 14 C and δ 13 C of total organic carbon (TOC) as well as lipid and phospholipids (PL) fractions of the sediments were applied to study sources of pollutants including chemical warfare agents (CWA). The compound-specific δ 13 C analysis, PL–derived fatty acid biomarkers and an end-member mixing model were used to estimate a relative contribution of the marine, terrestrial and fossil as well as petroleum hydrocarbons (measured directly) sources to organic carbon in the sediments, to assess a possible effect of petroleum hydrocarbon contamination on radiocarbon signatures and to elucidate a possible leakage of CWA at the Gotland Deep dumpsite. Data on spatial distribution of As, Zn, Ni, Cr, Hg, Cd, Cu and Pb concentrations as well as 206 Pb/ 207 Pb and 208 Pb/ 207 Pb ratios in the surface sediments indicated the highest concentrations of Pb with their different pattern of distribution and insignificant variations of 206 Pb/ 207 Pb and 208 Pb/ 207 Pb ratios. The obtained data revealed the possible application of the Chernobyl-derived Pu to trace the pollutants of the terrestrial origin. Wide TOC variations with the strong impact of the terrestrial and fresh waters in the coastal areas were observed. Variations of Δ 14 C and δ 13 C values with the most depleted values of the Δ 14 C TOC (-453%) and Δ 14 C of total lipid extracts (-812.4%) at the CWA dumpsite were found. An excess (after subtracting the petroleum hydrocarbon) of fossil sources at the CWA dumpsite as compared to those at other stations in the Baltic Sea was detected. The obtained results indicated a possible effect of CWA on depleted Δ 14 C and δ 13 C values. This study was supported by the Research Council of Lithuania, contract No. MIP-080/2012. (author)

  2. Caesium absorption by barley - influence of its retention by the soil - competitive action of potassium; Absorption du cesium par l'orge - influence de sa retention dans le sol - action competitive du potassium

    Energy Technology Data Exchange (ETDEWEB)

    Ferron-Trosseau, F. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-06-01

    plants such as rice and cress growing on flooded soils. Radio-active caesium however incorporated without carrier into a soil of medium-exchange capacity (of about 150 milli-equivalents per kilo) presents relatively little danger because of the close interdependence of the radioactive caesium take-up from the soil by the plants and its retention by the soil. Our research has made it possible furthermore to examine the value of various partial decontamination methods for soils proposed by certain atomic scientists: just as isotopic dilution appears totally inadequate for this purpose, so does it seems that the addition of potassium salts in amounts greater than nutritive optimum is incapable of reducing the absorption of radioactive caesium by the plant. (author) [French] Nous avons recherche, dans divers milieux de culture, comment l'absorption du cesium par l'orge varie avec sa concentration et comment cette absorption peut etre concurrencee par un cation alcalin voisin,le potassium. En outre, nous avons considere la distribution du cesium dans le sol - notamment du cesium radioactif - entre terre et solution, en fonction du taux de cesium. De notre etude ressort une nette opposition entre le comportement de l'orge vis a vis du cesium d'une solution nutritive et vis a vis du cesium d'un sol: sur solution nutritive, la fraction du cesium (radioactif et stable) absorbee par l'orge demeure pratiquement constante en presence de proportions croissantes (relativement petites) de cesium stable; sur sol, la fraction du cesium radioactif absorbee par l'orge a augmente en meme temps que le taux (relativement petit) de cesium stable du sol, en relation avec une selectivite rapidement decroissante du sol pour Cs. La difference entre ces resultats est donc expliquee par une tres forte selectivite du sol illitique experimente pour Cs{sup +} tant que la proportion da cesium reste tres petite, de l'ordre de celle de la plupart des sols naturels

  3. Caesium absorption by barley - influence of its retention by the soil - competitive action of potassium; Absorption du cesium par l'orge - influence de sa retention dans le sol - action competitive du potassium

    Energy Technology Data Exchange (ETDEWEB)

    Ferron-Trosseau, F [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1964-06-01

    as rice and cress growing on flooded soils. Radio-active caesium however incorporated without carrier into a soil of medium-exchange capacity (of about 150 milli-equivalents per kilo) presents relatively little danger because of the close interdependence of the radioactive caesium take-up from the soil by the plants and its retention by the soil. Our research has made it possible furthermore to examine the value of various partial decontamination methods for soils proposed by certain atomic scientists: just as isotopic dilution appears totally inadequate for this purpose, so does it seems that the addition of potassium salts in amounts greater than nutritive optimum is incapable of reducing the absorption of radioactive caesium by the plant. (author) [French] Nous avons recherche, dans divers milieux de culture, comment l'absorption du cesium par l'orge varie avec sa concentration et comment cette absorption peut etre concurrencee par un cation alcalin voisin,le potassium. En outre, nous avons considere la distribution du cesium dans le sol - notamment du cesium radioactif - entre terre et solution, en fonction du taux de cesium. De notre etude ressort une nette opposition entre le comportement de l'orge vis a vis du cesium d'une solution nutritive et vis a vis du cesium d'un sol: sur solution nutritive, la fraction du cesium (radioactif et stable) absorbee par l'orge demeure pratiquement constante en presence de proportions croissantes (relativement petites) de cesium stable; sur sol, la fraction du cesium radioactif absorbee par l'orge a augmente en meme temps que le taux (relativement petit) de cesium stable du sol, en relation avec une selectivite rapidement decroissante du sol pour Cs. La difference entre ces resultats est donc expliquee par une tres forte selectivite du sol illitique experimente pour Cs{sup +} tant que la proportion da cesium reste tres petite, de l'ordre de celle de la plupart des sols naturels. Par ailleurs, l'ion K{sup +} n'a concurrence l

  4. Cesium-137. Environment. Man

    International Nuclear Information System (INIS)

    Moiseev, A.A.

    1985-01-01

    Analysis of all main sourses of cerium-137 formation and intake into the external medium is given. Special attention is paid to the estimation of possible influence of rapidly developing nuclear power industry on contamination of the external medium by the radionuclide. Levels of contamination of the external medium by cerium-137, main regularities of its migration through food chains, levels of its intake and accumulation in population's organisms in USSR and its separate regions, are considered. Great attention is paid to the control methods of external environmental contamination by cesium-137 and to its measurements in human body

  5. Technology for removing radioactive Cs from incineration fly ash

    International Nuclear Information System (INIS)

    Ichikawa, Seigo; Nishizaki, Yoshihiko; Takano, Takehiko; Kumagai, Naokazu

    2016-01-01

    Radioactive cesium contained in incineration fly ash is highly soluble in water. We took advantage of this fact to develop a method for first using water cleaning to transfer cesium to water and then using adsorbent to recover this cesium in high concentrations. Since the adsorbent becomes radioactive waste, inorganic minerals such as zeolite are desirable from the point of view of long-term storage stability; however, zeolite is not suitable for cleaning water containing materials that inhibit cesium adsorption such as K+ and Na+. The feature of the new technology is that it provides a method for effective recovery of cesium from contaminated cleaning water using insoluble ferro-cyanide which is synthesized in situ, and for heat treatment of this cesium adsorbed from the ferro-cyanide to zeolite, thereby achieving reduction of radioactive waste and improvement of stability for long-term storage. (author)

  6. Kinetics of 137cesium in cerebral structures and blood

    International Nuclear Information System (INIS)

    Ribas, B.; Gonzalez, M.D.; Rio, J. del; Reus, M.I.S.; Gonzalez-Baron, M.

    1987-01-01

    The old clinical use of cesium in epilepsy expresses a relation of this metal with the central nervous system. Two groups of male Wistar rats of 200 g were administered single doses of 50μCi intravenously for blood kinetics and 2μCi 137 CsCl in each lateral ventricle of the brain for the kinetics in the cerebral structures, respectively. In both cases under ether anesthesia. Blood samples of IV gouts were weighed, and cerebral structure hypothalamus, hypocampus, striatum, cortex, cerebellum, mesencephalon and medulla oblongata dissected, cleaned, washed, dried, weighed, and in both cases cpm of the samples evaluated submitting it to the gamma radiations detector. In both experimental values of the 137 CsCl kinetics are expressed and applying the retroprojection method; parameters and constants are obtained. tsub(1/2) alpha = 0.0358 h and tsub(1/2) beta = 6.7159 h. In tables the equations of the alpha and beta phases are expressed. In blood after the rapid diminution of the radioactivity in the first 5 min the equilibrium phase is reached in 30 min afterwards, and the values remain almost the same 4 h after the injection and cesium is slowly eliminated by the rat. Cerebral structures after its intracerebroventricular application show that cesium has a great uptake velocity, it is rapidly incorporated by hypothalamus and after by cortex, hypocampus, striatum, mesencephalon and medulla oblongata, the two last showing the slower incorporation. After 24 h the cesium radioactivity declines slowly and progressively. (author)

  7. Electrokinetic remediation of contaminated soil from heavy metals and cobalt radioactive isotope

    International Nuclear Information System (INIS)

    Abdel Raouf, M.W.; Abdel Aziz, M.M.

    2005-01-01

    The present work presents a simple and inexpensive method for the in situ electrokinetic remediation of simulated contamined soil samples. Soil samples were collcted at inshas site (Egypt) at different depths 2-4, 4-6, and 6-8 m, purified from large and hard lumps, and characterized. To improve their hydraulic mobility, equal weights from the simulated soil and sand (0.5kg) were throughly mixed. The soil mixtures were dried under an infrared lamp, ground to a fine powder using a hand mortar. In this study, the soil samples were loaded separately by 250 ml CuSo 4 (1M) for Cu 2+ or CdCl 2 (1M) for Cd 2+ ,/or with simulated aqueous radioactive solution of 60 Co. Contaminated soil samples were left in contact with contaminant solutions for 48 hours in a closed container. Oven dried loaded soils samples were wasted five times by water to remove the free cations; then intial contaminant concentration of copper, calmium, and cobalt in soil samples was measured. To permit for the passage of electric current, loaded soil samples were wet with synthetic ground water (100 ml). A bench scale cell (13.0 cm x 6.0 cm x 6.5 cm) made from plexiglas was packed with 0.2 kg soil sample. A platinum sheet (4 cm x 0.5 cm x 0.05 cm) represented the anode; a graphite bar (iameter 0.5 cm and height 4 cm) represented the cathode, 6.0 cm apart from the anode. In the cell, the applied electric current and potential difference was kept constant at 60 mA and 10V, respectively for three hours treatment duration. The used electrodes were immersed into fired clay pottery bodies (net internal volume 15 ml) full with synthetic ground water. Percent of removal (P r ) of Cu 2+ , Cd 2+ , and 60 Co obtained after three hours waslarger than 97% at current density 2.2mA.cm -2 , and energy consumption 0.12 W.h.kg -1 . The advantages of the applied technique included the close control over the direction of movement of water and dissolved contsminants, retention of the contaminants within a confined zone

  8. Sorption and desorption of cesium and strontium on TA-2 and TA-41 soils and sediments

    International Nuclear Information System (INIS)

    Kung, K. Stephen; Li, Benjamin W.; Longmire, P.A.; Fowler, M.M.

    1996-04-01

    Current environmental monitoring has detected radioactive contaminants in alluvial groundwater, soils, and sediments in the TA-2 and TA-41 areas along the north central edge of Los Alamos National Laboratory. Because of this contamination, this study was initiated. The objective of this study is to quantify the sorptivity of cesium and strontium onto TA-2 and TA-41 site specific soil samples under a controlled environment in the laboratory. The purposes of this work are to determine cesium and strontium sorption coefficient for these sit specific soils and to evaluate the potential transport of cesium and strontium. Based on this information, a risk assessment and remediation strategy can be developed

  9. Cesium-137 inventory of the undisturbed soil areas in the Londrina Region, Parana, Brazil

    International Nuclear Information System (INIS)

    Andrello, Avacir C.; Appoloni, Carlos Roberto

    2005-01-01

    Cesium-137 is an artificial radionuclide introduced in the environment through the radioactive fallout of the superficial tests of nuclear weapons. The cesium-137 deposition occurred to middles of the 1980-decade and, due to the Chernobyl accident, great part of Europe had a additional fallout of cesium-137. The contaminations of this accident do not have reached Southern Hemisphere. Cesium-137 is an alkaline metal, high electropositive, that in contact with the soil is strongly adsorbed to the clay in the FES (Frayed Edge Sites) and RES (Regular Edge Sites) positions, and it movement by chemical processes in the soil is insignificant. Because of this, cesium-137 became a good soil marker, and its movement is related to the soil movement particles, so that the cesium-137 have been used in the study of the soil redistribution processes, as a tool of quantifying the rates of soil losses and gain. To use this methodology, it is necessary the knowledge of the reference inventory of cesium-137, that is given as function of the total concentration of cesium-137 deposited in an area by the radioactive fallout. If a sampling point presents less cesium-137 than the reference inventory, this point is considered a point with soil loss; otherwise, the point is considered a point with soil deposition. To evaluate the cesium-137 inventory in the Londrina region, four areas of the undisturbed soil were sampling in grid of 3x3, with a distance of 9 meters among the points. Of these four sampling areas, three areas were of native forest (labeled Mata1, Mata2 and Mata UEL), and one was a pasture area. Cesium-137 inventory was 223 ± 41 Bq m -2 , 240 ± 65 Bq m -2 and 305 ± 36 Bq m -2 for Mata UEL, Mata1 and Mata2, respectively, and of 211 ± 28 Bq m -2 for the native pasture. Considering the deviation in each value, it is not possible to conclude that there are differences among the values of cesium-137 inventory, so that the average reference inventory of cesium-137 for the

  10. Radioactive contamination in environment and food in Poland in 1992

    International Nuclear Information System (INIS)

    Grabowski, D.; Muszynski, W.; Petrykowska, M.; Rubel, B.; Smagala, G.; Wilgos, J.

    1993-01-01

    The level analysis of the level of radioactive contamination in environment and food samples was carried out in Poland in 1992. The results were compared to the data from 1985-1991 period. Since the Chernobyl accident gradual decrease of contamination level has been stated. The gamma dose rate and the contamination of air, fallout, tap and surface water were at the level of 1985. Still higher contamination level of cesium isotopes in soil has been reported and as a consequence food contamination was higher particularly the animal food. Actually, the source of additional dose is ingestion of artificial isotopes with food as a result of food contamination. The average effective dose equivalent, due to the contaminated food consumption, was estimated at the level 15 μSv for a Pole in 1992. (author). 13 refs, 6 figs, 20 tabs

  11. Diffusion of cesium in sodium-borosilicate glasses for nuclear waste immobilisation. Diffusie van cesium in natrium borosilicaat glazen voor het immobiliseren van radioaktief afval

    Energy Technology Data Exchange (ETDEWEB)

    Janssen, F.J.J.G.; Sengers, E.G.F. (Keuring van Electrotechnische Materialen NV, Arnhem (Netherlands)); Waal, H. de (TPD-TNO-Glass technology, Eindhoven (Netherlands))

    1989-09-26

    Diffusion of cesium in borosilicate glass for high-level radioactive waste is discussed. For this purpose model glasses with non-radioactive elements are being made, in accordance with the specifications of the reprocessing plants, from which concentration couples are composed. A concentration couple consists of two cylinders of borosilicate glass which contain different amounts of cesium. After heat treatment the couples are studied by means of the scanning electron microscopy and X-ray microanalysis. The model study will provide a basis for predictions of the containment achieved over a longer period of time. (author). 11 refs.; 2 figs.; 2 tabs.

  12. Method of producing a solution of radioactive lanthanum-140 from radioactive barium-140 in an isotope generator and installation to carry out the method

    International Nuclear Information System (INIS)

    Akerman, K.; Jacobs, G.; Sauerwein, K.

    1979-01-01

    A method of separating radioactive lanthanum-140 from radioactive Ba-140 is proposed. The lanthanum-140 will be washed out of a sulphate precipitate and separated from Ba-140-sulphate by a granular filter mass of CaSO 4 and BaSO 4 . Details of the process are given. (UWI) [de

  13. The diffusivity of cesium, strontium, carbon and nickel in concrete and mixtures of sodium bentonite and crushed rock

    International Nuclear Information System (INIS)

    Muurinen, A.; Penttilae-Hiltunen, P.; Rantanen, J.

    1986-07-01

    The engineering barriers suggested to be used for the disposal of low and intermediate level wastes in Finland are concrete and crushed rock or mixtures of crushed rock and bentonite. In the repository the barriers are saturated by groundwater and radionuclides may be released by diffusion through the barries. For safety analysis, the mechanisms by which the nuclides migrate and corresponding parameters should be known. In this study diffusion measurements on different types of concrete and mixtures of sodium bentonite and crushed rock were carried out. Radioactive isotopes of cesium, strontium, carbon and nickel were used as tracers. The apparent diffusivities (Dsub(a)) were evaluated on the basis of the measurements. The apparent diffusivity of cesium in concretes was 10 -14 ...10 -15 m 2 /s. Strontium was mainly sorbed on cement where it diffuses slowly. Part of strontium propably penetrates in the rock ballast by diffusion. The diffusivities of carbon and nickel in the concrete was low. The upper limit was evaluated to be Dsub(a) -14 m 2 /s. The diffusivity of cesium in the mixtures of crushed rock and bentonite varies between 0.5x10 -12 and 7x10 -12 m 2 /s. Cesium was mainly sorbed on the rock. The diffusivity of strontium was 2x10 -11 ...2x10 -12 m 2 /s. Strontium was mainly sorbed on bentonite. The diffusion of the sorbed ions (surface diffusion) seems to be a additional migration mechanism in the case of cesium and strontium in the mixture of bentonite and crushed rock. The diffusivity of carbon in the mixtures of crushed rock and bentonite was 6x10 -11 ...4x10 -12 m 2 /s. No sorption was found in the case of carbon. The measured Dsub(a) of nickel in the mixtures of crushed rock and bentonite was 4x10 -14 ...2x10 -15 m 2 /s. The experimental arrangement was not, however, in the stationary state and the more correct values would propably be 10 -13 ...10 -14 m 2 /s. No surface diffusion was found in the case of nickel. (author)

  14. The Eurisol report. A feasibility study for a European isotope-separation-on-line radioactive ion beam facility

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2003-12-01

    The Eurisol project aims at a preliminary design study of the next-generation European isotope separation on-line (ISOL) radioactive ion beam (RIB) facility. In this document, the scientific case of high-intensity RIBs using the ISOL method is first summarised, more details being given in appendix A. It includes: 1) the study of atomic nuclei under extreme and so-far unexplored conditions of composition (i.e. as a function of the numbers of protons and neutrons, or the so-called isospin), rotational angular velocity (or spin), density and temperature, 2) the investigation of the nucleosynthesis of heavy elements in the Universe, an important part of nuclear astrophysics, 3) a study of the properties of the fundamental interactions which govern the properties of the universe, and in particular of the violation of some of their symmetries, 4) potential applications of RIBs in solid-state physics and in nuclear medicine, for example, where completely new fields could be opened up by the availability of high-intensity RIBs produced by the ISOL method. The proposed Eurisol facility is then presented, with particular emphasis on its main components: the driver accelerator, the target/ion-source assembly, the mass-selection system and post-accelerator, and the required scientific instrumentation. Special details of these components are given in appendices B to E, respectively. The estimates of the costs of the Eurisol, construction and running costs, have been performed in as much details as is presently possible. The total capital cost (installation manpower cost included) of the project is estimated to be of the order of 630 million Euros within 20%. In general, experience has shown that operational costs per annum for large accelerator facilities are about 10% of the capital cost. (A.C.)

  15. Mineral resource of the month: cesium

    Science.gov (United States)

    Angulo, Marc A.

    2010-01-01

    The article offers information on cesium, a golden alkali metal derived from the Latin word caesium which means bluish gray. It mentions that cesium is the first element discovered with the use of spectroscopy. It adds that the leading producer and supplier of cesium is Canada and there are 50,000 kilograms of cesium consumed of the world in a year. Moreover, it states that only 85% of the cesium formate can be retrieved and recycled.

  16. Marine Biogenic Minerals Hold Clues About Changes in Ocean Chemistry and Climate: Some Important Lessons Learned from Studies of Stable and Radioactive Isotopes of Be and Al

    Directory of Open Access Journals (Sweden)

    Devendra Lal

    2002-01-01

    Full Text Available The elements Be and Al exhibit very short residence time in ocean waters, and therefore serve as useful tracers for the study of biogeochemical processes in seawater. A unique feature of these tracers is that nuclear interactions of cosmic rays in the atmosphere produce appreciable amounts of two radioactive isotopes, 10Be (with a half-life of 1.5 my and 26Al (with a half-life of 0.7 my, which are introduced in the hydrosphere, cryosphere, and lithosphere via precipitation. Thus, these elements are labeled by their respective radioactive isotopes, which help quantitative tagging of their biogeochemical cycles. Finally, as we report here, several marine organisms incorporate them in their skeletal shells in certain fixed proportions to their concentrations in the seawater, so that it seems possible to study changes in the ocean chemistry and climate over the past several million years. We summarize here the recent discovery by Dong et al.[9] of significant enrichments of intrinsic Be and Al in marine foraminiferal calcite and coral aragonite, and of Al in opal (radiolarians and aragonite (corals, which should make it possible to determine 10Be/Be and 26Al/Al in oceans in the past. We also summarize their measured 10Be/9Be in foraminiferal calcite in Pacific Ocean cores, which reveal that the concentrations and ratios of the stable and cosmogenic isotopes of Be and Al have varied significantly in the past 30 ky. The implications of these results are discussed.

  17. Cesium contamination of mosses in county Vas, Hungary

    International Nuclear Information System (INIS)

    Golya, I.; Sebestyen, R.

    1993-01-01

    Two species of mosses were examined to assess radiocesium contamination of Vas county, and to analyse some aspects of mosses for use as indicator of radioactive contamination. Experimental results demonstrated that the distribution of contamination in a given region could be characterized by the cesium contamination of mosses. Sampling sites should be selected with special attention paid to spots with high contamination. Regression analysis proved that the contamination of mosses originated from Chernobyl fallout. (author) 4 refs.; 2 figs

  18. Radioactive fallout has different effects in Lapland

    International Nuclear Information System (INIS)

    Rissanen, K.

    1993-01-01

    The effects of radioactive fallout in Lapland differ from those in southern Finland. The subarctic area is poor in vegetation and nutrients, for which reason radioactive substances enter food chains rapidly. As potassium is low in supply in the north, plants use cesium to replace it. Thus cesium is accumulated very effectively in food chain. When in the food chain, cesium is enriched in reindeer and further in Lapp people, who eat reindeer meat frequently. The Finnish Centre for Radiation and Nuclear Safety established a regional laboratory in northern Finland in the 1970's to monitor radiation and carry out research an the area.(author)

  19. Cesium diffusion in graphite

    International Nuclear Information System (INIS)

    Evans, R.B. III; Davis, W. Jr.; Sutton, A.L. Jr.

    1980-05-01

    Experiments on diffusion of 137 Cs in five types of graphite were performed. The document provides a completion of the report that was started and includes a presentation of all of the diffusion data, previously unpublished. Except for data on mass transfer of 137 Cs in the Hawker-Siddeley graphite, analyses of experimental results were initiated but not completed. The mass transfer process of cesium in HS-1-1 graphite at 600 to 1000 0 C in a helium atmosphere is essentially pure diffusion wherein values of (E/epsilon) and ΔE of the equation D/epsilon = (D/epsilon) 0 exp [-ΔE/RT] are about 4 x 10 -2 cm 2 /s and 30 kcal/mole, respectively

  20. Sericitization of illite decreases sorption capabilities for cesium

    Science.gov (United States)

    Choung, S.; Hwang, J.; Han, W.; Shin, W.

    2017-12-01

    Release of radioactive cesium (137Cs) to environment occurs through nuclear accidents such as Chernobyl and Fukushima. The concern is that 137Cs has long half-life (t1/2 = 30.2 years) with chemical toxicity and γ-radiation. Sorption techniques are mainly applied to remove 137Cs from aquatic environment. In particular, it has been known well that clay minerals (e.g, illite) are effective and economical sorbents for 137Cs. Illite that was formed by hydrothermal alteration exist with sericite through "sericitization" processes. Although sericite has analogous composition and lattice structure with illite, the sorptive characteristics of illite and sericite for radiocesium could be different. This study evaluated the effects of hydrothermal alteration and weathering process on illite cesium sorption properties. Natural illite samples were collected at Yeongdong area in Korea as the world-largest hydrothermal deposits for illite. The samples were analyzed by XRF, XRD and SEM-EDX to determine mineralogy, chemical compositions and morphological characteristics, and used for batch sorption experiments. The Yeongdong illites predominantly consist of illite, sericite, quartz, and albite. The measured cesium sorption distribution coefficients (Kd,Cs) of reference illite and sericite were approximately 6000 and 400 L kg-1 at low aqueous concentration (Cw 10-7 M), respectively. In contrast, Kd,Cs values for the Yeongdong illite samples ranged from 500 to 4000 L kg-1 at identical concentration. The observed narrow and sharp XRD peak of sericite indicated that the sericite has better crystallinity compared to illite. These experimental results suggested that sericitization processes of illite can decline the sorption capabilities of illite for cesium under various hydrothermal conditions. In particular, weathering experiments raised the cesium sorption to illite, which seems to be related to the increase of preferential sorption sites for cesium through crystallinity destruction

  1. Feasibility Assessment of Cesium Removal using Microaglae

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Ilgook; Ryu, Byung-Gon; Seo, Bum-Kyoung; Moon, Jei Kwon; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The aim of this work is to assess the feasibility of selected one of microalgae in the uptake of Cs+. The obtained results showed the maximum Cs+ removal by D. armatus SCK was 280μM indicating 70% removal efficiency. Also, D. armatus SCK could uptake Cs+ in the presence of K+, is particularly known to be transported into cells as an analog of Cs+ in freshwater condition. Recently, increased attention has been directed on the use of biological technologies for the removal of radionuclides as the cheap and eco-friendly alternative to the non-biological methods. Metal including radioactive compounds uptake by microorganisms can be occurred by metabolism –independent and/or -dependent processes. One involves biosorption based on the ability of microbial cells to bind dissolved metals; on the other involves bioaccumulation, which depends on the metabolic ability of cells to transport metals into the cytoplasm. The purpose of this work is to investigate the feasibility of microalgae in bioaccumulation system to remove cesium from solution. The effect of different environmental parameters on cesium removal was also examined.

  2. Return of isotope capsules to the Waste Encapsulation and Storage Facility

    International Nuclear Information System (INIS)

    1994-05-01

    Cesium-137 and strontium-90 isotopes were removed from Hanford Site high-level tank wastes, and were encapsulated at the Hanford Site's Waste Encapsulation and Storage Facility (WESF), beginning in 1974. Over the past several years, radioactive isotope capsules have been sent to other U.S. Department of Energy (DOE)-controlled sites to be used for research and development applications, as well as leased to a number of commercial facilities for commercial applications (e.g., sterilization of medical supplies). Due to uncertainty regarding the cause of the release of a small quantity of cesium-137 to an isolated water basin from a WESF cesium-137 capsule in a commercial facility in Decatur, Georgia, the DOE has determined that it needs to return leased capsules from IOTECH, Incorporated (IOTECH), Northglenn, Colorado; Pacific Northwest Laboratory (PNL), Richland, Washington; and the Applied Radiant Energy Corporation (ARECO), Lynchburg, Virginia; to the WESF Facility on the Hanford Site, to ensure safe management and storage, pending final disposition. All of these capsules located at the commercial facilities were successfully tested during Calendar Year 1993, and none showed any indication of off-normal specifications. Storage at the WESF will continue under the actions selected in the Record of Decision for the Final Environmental Impact Statement: Disposal of Hanford Defense High-Level, Transuranic and Tank Wastes, Hanford Site, Richland, Washington

  3. Isotope method for the recognition of groundwater formation in China's preselected high level radioactive waste disposal repository site

    International Nuclear Information System (INIS)

    Guo Yonghai; Wang Ju; Liu Shufen; Su Rui; Lu Chuanhe

    2005-01-01

    Yemaquan region in Beishan area. Gansu province, is one of the preselected sites of disposal repository for high level radioactive waste (HLW) in our country. Hydrogeological condition is an important aspect for site evaluation and the groundwater formation is a key factor to reflect the hydrogeological conditions for a certain area. Isotopic method is the one of the important means to determine the groundwater formation. Through the sampling and analysis of shallow groundwater isotopes of Yemaquan region, combined with geological, hydrogeological and hydrogeochemical characteristics, the issue of groundwater formation in the study region was discussed. The main cognition is that the groundwater in the region was formed from the infiltration of modern rainfall and the strong evaporation was happened for the shallow groundwater, which indicates the circulation conditions were relatively good for the shallow groundwater. This cognition provides very important hydrogeological information and basis for the evaluation of Yemaquan preselected site. (authors)

  4. Production of radioactive ion beams and resonance ionization spectroscopy with the laser ion source at on-line isotope separator ISOLDE

    International Nuclear Information System (INIS)

    Fedosseev, V.N.; )

    2005-01-01

    Full text: The resonance ionisation laser ion source (RILIS) of the ISOLDE on-line isotope separation facility at CERN is based on the method of laser step-wise resonance ionisation of atoms in a hot metal cavity. Using the system of dye lasers pumped by copper vapour lasers the ion beams of many different metallic elements have been produced at ISOLDE with an ionization efficiency of up to 27%. The high selectivity of the resonance ionization is an important asset for the study of short-lived nuclides produced in targets bombarded by the proton beam of the CERN Booster accelerator. Radioactive ion beams of Be, Mg, Al, Mn, Ni, Cu, Zn, Ga, Ag, Cd, In, Sn, Sb, Tb, Yb, Tl, Pb and Bi have been generated with the RILIS. Setting the RILIS laser in the narrow line-width mode provides conditions for a high-resolution study of hyperfine structure and isotopic shifts of atomic lines for short-lived isotopes. The isomer selective ionization of Cu, Ag and Pb isotopes has been achieved by appropriate tuning of laser wavelengths

  5. Process for recovering cesium from pollucite

    International Nuclear Information System (INIS)

    Mein, P.G.

    1985-01-01

    Cesium is recovered from a cesium-bearing mineral such as pollucite by extraction with hydrochloric acid to obtain an extract of cesium chloride and other alkali metal and polyvalent metal chlorides. The iron and aluminum chlorides can be precipitated as the hydroxides and separated from the solution of the alkali metal chlorides to which is added potassium permanganate or other water-soluble permanganate to selectively precipitate cesium permanganate. The cesium precipitate is then separated from the residual solution containing the metal chlorides. The cesium permanganate, which is in a very pure form, can be converted to other cesium compounds by reaction with a reducing agent to obtain cesium carbonate and cesium delta manganese dioxide

  6. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    Energy Technology Data Exchange (ETDEWEB)

    NA

    2004-11-22

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this modeling activity is to predict dissolved concentrations or solubility limits for 14 elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) important to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are in the form of tabulated functions with pH and log (line integral) CO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. The output data from this report are fundamental inputs for Total System Performance Assessment for the License Application (TSPA-LA) to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for all of the actinides. These models cover broad ranges of environmental conditions so that they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise addressed.

  7. Chernobyl cesium in the soil of Montenegro, eight years after the accident

    International Nuclear Information System (INIS)

    Borisov, G. I.; Kuzmic, V. V.; Vukotic, P.; Dapcevic, S.; Antovic, N.; Mirkovic, M.; Fustic, B.

    1996-01-01

    Radioactive cesium contamination of the territory of Montenegro is measured by in situ method of semiconductor gamma-spectrometry at the end of the end of the year 1994. On basis of geological and pedological characteristics of the region, 42 measurement sites are chosen, which are representative for large area and uniformly distributed over the territory of Republic. It is found that degree of contamination varies strongly from region to region. Surface activities of 137 Cs span 3700 to 74000 Bq/m 2 range. Radioactive cesium is mostly remained in the surface part of uncultivated soil. 14 refs.; 3 figs

  8. Heat Transfer During Evaporation of Cesium From Graphite Surface in an Argon Environment

    Directory of Open Access Journals (Sweden)

    Bespala Evgeny

    2016-01-01

    Full Text Available The article focuses on discussion of problem of graphite radioactive waste formation and accumulation. It is shown that irradiated nuclear graphite being inalienable part of uranium-graphite reactor may contain fission and activation products. Much attention is given to the process of formation of radioactive cesium on the graphite element surface. It is described a process of plasma decontamination of irradiated graphite in inert argon atmosphere. Quasi-one mathematical model is offered, it describes heat transfer process in graphite-cesium-argon system. Article shows results of calculation of temperature field inside the unit cell. Authors determined the factors which influence on temperature change.

  9. Prussian blue caged in spongiform adsorbents using diatomite and carbon nanotubes for elimination of cesium

    Energy Technology Data Exchange (ETDEWEB)

    Hu, Baiyang [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Fugetsu, Bunshi, E-mail: hu@ees.hokudai.ac.jp [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Yu, Hongwen [Graduate School of Environmental Science, Hokkaido University, Sapporo 060-0810 (Japan); Abe, Yoshiteru [Kyoei Engineering Corporation, Niigata 959-1961 (Japan)

    2012-05-30

    Highlights: Black-Right-Pointing-Pointer Prussian blue was sealed in cavities of diatomite using carbon nanotubes. Black-Right-Pointing-Pointer The caged Prussian blue after being permanently immobilized in polyurethane spongy showed a 167 mg/g capability for absorbing cesium. Black-Right-Pointing-Pointer Cesium elimination was accomplished by simply adding the Prussian-blue based spongiform adsorbent to radioactive water. - Abstract: We developed a spongiform adsorbent that contains Prussian blue, which showed a high capacity for eliminating cesium. An in situ synthesizing approach was used to synthesize Prussian blue inside diatomite cavities. Highly dispersed carbon nanotubes (CNTs) were used to form CNT networks that coated the diatomite to seal in the Prussian blue particles. These ternary (CNT/diatomite/Prussian-blue) composites were mixed with polyurethane (PU) prepolymers to produce a quaternary (PU/CNT/diatomite/Prussian-blue), spongiform adsorbent with an in situ foaming procedure. Prussian blue was permanently immobilized in the cell walls of the spongiform matrix and preferentially adsorbed cesium with a theoretical capacity of 167 mg/g cesium. Cesium was absorbed primarily by an ion-exchange mechanism, and the absorption was accomplished by self-uptake of radioactive water by the quaternary spongiform adsorbent.

  10. Cesium-137 accumulation in higher plants before and after Chernobyl

    International Nuclear Information System (INIS)

    Sawidis, T.; Drossos, E.; Papastefanou, C.; Heinrick, G.

    1990-01-01

    Cesium-137 concentrations in plant species of three biotypes of northern Greece, differing in location as well as in vegetation, are reported following the Chernobyl reactor accident. The cesium uptake by plants was due to the foliar deposition rather than the root uptake. The highest level of cesium in plants was found in Ranunculus sardous, a pubescent plant. The 137 Cs concentration was about 22kBq kg -1 d.w. A high level of cesium was also found in Salix alba ( 137 Cs: 19.6 kBq kg -1 d.w.), a deciduous tree showing that hairy leaves or leaves having rough and large surfaces can absorb greater amounts of radioactivity (surface effect). A comparison is also made between the results of measurements of the present study and the results of measurements of some herbarium plants collected one year before the accident as well as the results of measurements of some new plants grown and collected one year after the accident resulting in a natural removal rate of 137 Cs in plants varying from 14 to 130 days

  11. Hot demonstration of proposed commercial cesium removal technology

    International Nuclear Information System (INIS)

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

    1997-12-01

    This report describes the work done in support of the development of technology for the continuous removal and concentration of radioactive cesium in supernatant from Melton Valley Storage Tanks (MVSTs) at the ORNL site. The primary objective was to test candidate absorbers and ion exchangers under continuous-flow conditions using actual supernatant from the MVSTs. An experimental system contained in a hot-cell facility was constructed to test the materials in columns or modules using the same batch of supernatant to allow comparison on an equal basis. Resorcinol/formaldehyde (RF) resin was evaluated at three flow rates with 50% breakthrough ranges of 35 to 50 column volumes (CV) and also through a series of five loading/elution/regeneration cycles. The results reported here include the cesium loading breakthrough curves, elution curves (when applicable), and operational problems and observations for each material. The comparative evaluations should provide critical data for the selection of the sorbent for the ORNL Cesium Removal Demonstration project. These results will be used to help determine the design parameters for demonstration-scale systems. Such parameters include rates of cesium removal, quantity of resin or sorbent to be used, and elution and regeneration requirements, if applicable

  12. Validation and Application of Concentrated Cesium Eluate Physical Property Models

    International Nuclear Information System (INIS)

    Choi, A.S.

    2004-01-01

    This work contained two objectives. To verify the mathematical equations developed for the physical properties of concentrated cesium eluate solutions against experimental test results obtained with simulated feeds. To estimate the physical properties of the radioactive AW-101 cesium eluate at saturation using the validated models. The Hanford River Protection Project (RPP) Hanford Waste Treatment and Immobilization Plant (WTP) is currently being built to extract radioisotopes from the vast inventory of Hanford tank wastes and immobilize them in a silicate glass matrix for eventual disposal at a geological repository. The baseline flowsheet for the pretreatment of supernatant liquid wastes includes removal of cesium using regenerative ion-exchange resins. The loaded cesium ion-exchange columns will be eluted with nitric acid nominally at 0.5 molar, and the resulting eluate solution will be concentrated in a forced-convection evaporator to reduce the storage volume and to recover the acid for reuse. The reboiler pot is initially charged with a concentrated nitric acid solution and kept under a controlled vacuum during feeding so the pot contents would boil at 50 degrees Celsius. The liquid level in the pot is maintained constant by controlling both the feed and boilup rates. The feeding will continue with no bottom removal until the solution in the pot reaches the target endpoint of 80 per cent saturation with respect to any one of the major salt species present

  13. Studies on the synthesis and characterization of cesium-containing iron phosphate glasses

    Science.gov (United States)

    Joseph, Kitheri; Govindan Kutty, K. V.; Chandramohan, P.; Vasudeva Rao, P. R.

    2009-02-01

    Isotopes of cesium and strontium can be utilized as radiation source for various industrial and medical applications after their separation from high level nuclear waste. However, these elements need to be immobilized in a suitable matrix. In the present work, a systematic approach has been made to immobilize inactive cesium into iron phosphate glass. Up to 36 mol% of Cs 2O has been loaded successfully without crystallization. The glass transition temperature of the cesium loaded glass was found to increase initially and then decrease as a function of Cs 2O content. Mössbauer studies show that the concentration of Fe 3+ ions in the cesium loaded glasses is >95%. Volatilization experiments at 1263 K show that the weight loss is >0.5% for a period of 4 h. The 36 mol% of Cs 2O loaded iron phosphate glass with high Fe 3+ content described in this paper is reported for the first time.

  14. Prussian blue caged in spongiform adsorbents using diatomite and carbon nanotubes for elimination of cesium.

    Science.gov (United States)

    Hu, Baiyang; Fugetsu, Bunshi; Yu, Hongwen; Abe, Yoshiteru

    2012-05-30

    We developed a spongiform adsorbent that contains Prussian blue, which showed a high capacity for eliminating cesium. An in situ synthesizing approach was used to synthesize Prussian blue inside diatomite cavities. Highly dispersed carbon nanotubes (CNTs) were used to form CNT networks that coated the diatomite to seal in the Prussian blue particles. These ternary (CNT/diatomite/Prussian-blue) composites were mixed with polyurethane (PU) prepolymers to produce a quaternary (PU/CNT/diatomite/Prussian-blue), spongiform adsorbent with an in situ foaming procedure. Prussian blue was permanently immobilized in the cell walls of the spongiform matrix and preferentially adsorbed cesium with a theoretical capacity of 167 mg/g cesium. Cesium was absorbed primarily by an ion-exchange mechanism, and the absorption was accomplished by self-uptake of radioactive water by the quaternary spongiform adsorbent. Copyright © 2012 Elsevier B.V. All rights reserved.

  15. Suicide with cesium 137

    International Nuclear Information System (INIS)

    Krushkov, I.; Vassileva, B.

    1978-01-01

    Report on first case of suicide with radioactive substance in Bulgaria is given. A defectoscopist with cyclothymic structure of character and psychotraumatic family environment made a second and successful attempt at suicide, this time by means of external irradiation with 137 Cs with an activity of 5.3 C in the course of two hours. He irradiated his heart region and the first three fingers of his right hand. A grave picture of acute, local irradiation injury lasting four months with lethal outcome. The authors treat the psychological motives in the behaviour of these suicides and the reasons which determine the small number of suicide carried out with radioactive substance. (author)

  16. A distribution of adsorbed forms of cesium 137 and strontium 90 in flood-plain formations of Sozh river

    International Nuclear Information System (INIS)

    Kuznetsov, V.A.; Generalova, V.A.

    1999-01-01

    The distribution of strontium 90 and cesium 137 forms in flood-plain geochemical system 'alluvial deposits - flood-plain turf - humus horizon - soil-source rock', where sorption and colloidal processes play main role in the isotopes migration, was studied. The bulk amount of strontium 90 is presented in adsorbed form in all investigated objects, whereas only 6% of cesium 137 amount in alluvial deposits, flood-plain turf and humus horizon is in adsorbed form. The content of exchange forms of cesium 137 and strontium 90 increases with the depth of the layer. The race of this increase for strontium 90 is large than for cesium 137. The distribution of radionuclides through the different parts of flood-plain of Sozh river has some distinctions due to more lability of adsorbed strontium 90 forms in comparison with cesium 137 ones

  17. Effects of natural radioactivity on food radioactivity measurement

    International Nuclear Information System (INIS)

    Ennyu, Atsuhito

    2012-01-01

    Since the accident of the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Company, groups and individuals including local governments, food manufacturers, distribution circles, retail circles, and citizens are eager to measure the radioactivity of food, in order to confirm the safety of food from the concerns about radioactive contamination. The measurement of radioactivity of food is done by quantitatively determining gamma rays due to radioactive cesium that was incorporated into the biosphere cycle after having been released into the environment. As for the radioactivity measurement of food using gamma-ray spectrometry with a potassium iodide scintillation detector, which is very commonly used, this paper describes the handling method of obtained data, the principle of erroneous detection of radioactive cesium and iodine interrupted by natural radionuclides, and countermeasures for it. Major natural radioactivity sources are uranium series and thorium series. This paper explains gamma rays, which are characteristic in the decay process of uranium series and often affect the measurement of radioactive cesium in food and water. (O.A.)

  18. Rapid analysis of U isotopes in vegetables using ICP-MS. Application to the emergency U monitoring after the nuclear accident at TEPCO's Fukushima Dai-ichi power station

    International Nuclear Information System (INIS)

    Jian Zheng; Keiko Tagami; Shigeo Uchida

    2012-01-01

    After the nuclear accident at TEPCO's Fukushima Dai-ichi power station in March, hydrogen explosions and reactor building explosion resulted in releases of radionuclides in the environment. Severe radioactive cesium and iodine contaminations have been observed in fallout deposition samples and soils in the East Japan. Radioactive cesium, iodine, uranium, and transuranic radionuclides were set as the monitoring targets in food safety tests. However, so far, only radioactive cesium and iodine were daily measured and reported by the Ministry of Health, Labour, and Welfare. The tedious and time consuming conventional alpha spectrometric method hampered the emergency monitoring U contamination in foods. In this work, we propose a simple and rapid analytical method for 238 U and 235 U/ 238 U isotope ratio analysis in fresh vegetables. This method was applied to the emergency monitoring of radioactive contamination after the nuclear accident at TEPCO's Fukushima Dai-ichi power station. The results showed no U contamination in fresh vegetables collected in Chiba and Ibaraki prefectures in April and May, 2011. (author)

  19. Cesium Concentration in MCU Solvent

    International Nuclear Information System (INIS)

    Walker, D

    2006-01-01

    During Modular Caustic-Side Solvent Extraction (CSSX) Unit (MCU) operations, Cs-137 concentrations in product streams will vary depending on the location in the process and on the recent process conditions. Calculations of cesium concentrations under a variety of operating conditions reveal the following: (1) Under nominal operations with salt solution feed containing 1.1 Ci Cs-137 per gallon, the maximum Cs-137 concentration in the process will occur in the strip effluent (SE) and equal 15-16.5 Ci/gal. (2) Under these conditions, the majority of the solvent will contain 0.005 to 0.01 Ci/gal, with a limited portion of the solvent in the contactor stages containing ∼4 Ci/gal. (3) When operating conditions yield product near 0.1 Ci Cs-137/gal in the decontaminated salt solution (DSS), the SE cesium concentration will be the same or lower than in nominal operations, but majority of the stripped solvent will increase to ∼2-3 Ci/gal. (4) Deviations in strip and waste stream flow rates cause the largest variations in cesium content: (a) If strip flow rates deviate by -30% of nominal, the SE will contain ∼23 Ci/gal, although the cesium content of the solvent will increase to only 0.03 Ci/gal; (b) If strip flow rate deviates by -77% (i.e., 23% of nominal), the SE will contain 54 Ci/gal and solvent will contain 1.65 Ci/gal. At this point, the product DSS will just reach the limit of 0.1 Ci/gal, causing the DSS gamma monitors to alarm; and (c) Moderate (+10 to +30%) deviations in waste flow rate cause approximately proportional increases in the SE and solvent cesium concentrations. Recovery from a process failure due to poor cesium stripping can achieve any low cesium concentration required. Passing the solvent back through the contactors while recycling DSS product will produce a ∼70% reduction during one pass through the contactors (assuming the stripping D value is no worse than 0.36). If the solvent is returned to the solvent hold tank (containing additional

  20. A study on the radioactive waste management for DUPIC fuel cycle

    Energy Technology Data Exchange (ETDEWEB)

    Chun, Kwan Sik; Park, H. S.; Park, J. J.; Kim, J. H.; Cho, Y. H.; Shin, J. M.; Kim, Y. K.; Kim, J. S.; Kim, J. G.; Park, S. D.; Suh, M. Y.; Sohn, S. C.; Song, B. C.; Lee, C. H.; Jeon, Y. S.; Jo, K. S.; Jee, K. Y.; Jee, C. S.; Han, S. H.

    1997-09-01

    Part 1: The characteristics if the radioactive wastes coming from the DUPIC fuel manufacturing process were analyzed and evaluated. The gross {alpha}-activity and {alpha}-, {gamma}-spectrum of irradiated zircaloy specimens form KORI unit 1 were analyzed. In order to develop the trapping media of radioactive ruthenium oxides, trapping behavior of volatilized ruthenium oxides on various metal oxides or carbonates was analyzed. Fly ash was selected as a trapping materials for gaseous cesium. And reaction characteristics of CsNO{sub 3} and CsI with fly ash have been investigated. Also, trapping material were performed to test fly ash filter for removal of gaseous cesium under the air and hydrogen atmosphere. The applicability of fly ash to the vitrification of the spent filter was analyzed in the aspects of predictability, leachability. Good quality of Borosilicate glass was formed using Cesium spent filter. Offgas treatment system of DUPIC fuel manufacturing facility was designed and constructed in order to trap of gaseous radioactive waste from 100 batch of OREOXA furnace (the capacity : 500 g/batch). Part II: To develop chemical analysis techniques necessary for understanding chemical properties of the highly radioactive materials related to the development of DUPIC fuel cycle technology, the following basic studies were performed : dissolution of SIMFUEL (simulated fuel), determination of uranium by potentiometry and UV/Vis absorption spectrophotometry, separation of PWR spent fuel, group separation of fission products from uranium, individual separation for analysis of actinides, determination of free acid in a artificial dissolved solution of PWR spent fuel, group separation of fission products form uranium, individual separation of Sm from a mixed rare earth elements and measurement of its isotopes by TI-mass spectrometry, and characteristics of detectors in inductively coupled plasma atomic emission spectrometer (ICP-AES) suitable for analysis of trace fission

  1. A study on the radioactive waste management for DUPIC fuel cycle

    International Nuclear Information System (INIS)

    Chun, Kwan Sik; Park, H. S.; Park, J. J.; Kim, J. H.; Cho, Y. H.; Shin, J. M.; Kim, Y. K.; Kim, J. S.; Kim, J. G.; Park, S. D.; Suh, M. Y.; Sohn, S. C.; Song, B. C.; Lee, C. H.; Jeon, Y. S.; Jo, K. S.; Jee, K. Y.; Jee, C. S.; Han, S. H.

    1997-09-01

    Part 1: The characteristics if the radioactive wastes coming from the DUPIC fuel manufacturing process were analyzed and evaluated. The gross α-activity and α-, γ-spectrum of irradiated zircaloy specimens form KORI unit 1 were analyzed. In order to develop the trapping media of radioactive ruthenium oxides, trapping behavior of volatilized ruthenium oxides on various metal oxides or carbonates was analyzed. Fly ash was selected as a trapping materials for gaseous cesium. And reaction characteristics of CsNO 3 and CsI with fly ash have been investigated. Also, trapping material were performed to test fly ash filter for removal of gaseous cesium under the air and hydrogen atmosphere. The applicability of fly ash to the vitrification of the spent filter was analyzed in the aspects of predictability, leachability. Good quality of Borosilicate glass was formed using Cesium spent filter. Offgas treatment system of DUPIC fuel manufacturing facility was designed and constructed in order to trap of gaseous radioactive waste from 100 batch of OREOXA furnace (the capacity : 500 g/batch). Part II: To develop chemical analysis techniques necessary for understanding chemical properties of the highly radioactive materials related to the development of DUPIC fuel cycle technology, the following basic studies were performed : dissolution of SIMFUEL (simulated fuel), determination of uranium by potentiometry and UV/Vis absorption spectrophotometry, separation of PWR spent fuel, group separation of fission products from uranium, individual separation for analysis of actinides, determination of free acid in a artificial dissolved solution of PWR spent fuel, group separation of fission products form uranium, individual separation of Sm from a mixed rare earth elements and measurement of its isotopes by TI-mass spectrometry, and characteristics of detectors in inductively coupled plasma atomic emission spectrometer (ICP-AES) suitable for analysis of trace fission products. (author

  2. Radioactivity and food

    International Nuclear Information System (INIS)

    Olszyna-Marzys, A.E.

    1990-01-01

    Two topics relating to radioactivity and food are discussed: food irradiation for preservation purposes, and food contamination from radioactive substances. Food irradiation involves the use of electromagnetic energy (x and gamma rays) emitted by radioactive substances or produced by machine in order to destroy the insects and microorganisms present and prevent germination. The sanitary and economic advantages of treating food in this way are discussed. Numerous studies have confirmed that under strictly controlled conditions no undesirable changes take place in food that has been irradiated nor is radioactivity induced. Reference is made to the accident at the Chernobyl nuclear power station, which aroused public concern about irradiated food. The events surrounding the accident are reviewed, and its consequences with regard to contamination of different foods with radioactive substances, particularly iodine-131 and cesium-137, are described. Also discussed are the steps that have been taken by different international organizations to set limits on acceptable radioactivity in food.15 references

  3. Application of crown ethers to selective extraction and quantitative analysis of technetium 99, iodine 129 and cesium 135 in effluents

    International Nuclear Information System (INIS)

    Paviet, P.

    1992-01-01

    Properties of crown ethers are first recalled. Then extraction of technetium 99 is studied in actual radioactive effluents. Quantitative analysis is carried out by liquid scintillation and interference of tritium is corrected. Iodine 129 is extracted from radioactive effluents and determined by gamma spectrometry. Finally cesium 135 is extracted and determined by thermo ionization mass spectroscopy

  4. Process for cesium decontamination and immobilization

    Science.gov (United States)

    Komarneni, Sridhar; Roy, Rustum

    1989-01-01

    Cesium can be selectively recovered from a nuclear waste solution containing cesium together with other metal ions by contact with a modified phlogopite which is a hydrated, sodium phlogopite mica. Once the cesium has entered the modified phlogopite it is fixed and can be safely stored for long periods of time.

  5. Process for cesium decontamination and immobilization

    Science.gov (United States)

    Komarneni, S.; Roy, R.

    1988-04-25

    Cesium can be selectively recovered from a nuclear waste solution containing cesium together with other metal ions by contact with a modified phlogopite which is a hydrated, sodium phlogopite mica. Once the cesium has entered the modified phlogopite it is fixed and can be safely stored for long periods of time. 6 figs., 2 tabs.

  6. Concentration of Cs in plants and water resulting from radioactive pollution

    Energy Technology Data Exchange (ETDEWEB)

    Ishizaki, A., E-mail: azusa.ishizaki@qse.tohoku.ac.jp [Department of Quantum Science and Energy Engineering, Tohoku University, Aramaki-Aza-Aoba 6-6-01, Aoba-ku, Sendai 980-8579 (Japan); Ishii, K.; Matsuyama, S.; Fujishiro, F.; Arai, H.; Osada, N.; Sugai, H.; Koshio, S.; Yamauchi, S.; Kusano, K.; Nozawa, Y.; Karahashi, M.; Oshikawa, S.; Kikuchi, K.; Watanabe, K.; Itoh, S.; Kasahara, K.; Toyama, S. [Department of Quantum Science and Energy Engineering, Tohoku University, Aramaki-Aza-Aoba 6-6-01, Aoba-ku, Sendai 980-8579 (Japan); Suzuki, Y. [Graduate School of Biomedical Engineering, Tohoku University, Aramaki-Aza-Aoba 6-6-04, Aoba-ku, Sendai 980-8578 (Japan)

    2014-01-01

    The consumption of plants cultivated in soils contaminated by radioactive cesium can lead to internal exposure and health problems in humans. It is therefore very important to clarify the uptake mechanism of radioactive cesium from contaminated soils. In this study, the variation of cesium concentrations in plants was examined using mediums that contained no potassium and different cesium concentrations of 50, 100, 250 and 500 ppm. Raphanus sativus was selected as a typical edible vegetable and hydroponically cultivated. Cesium concentrations in leaves were analyzed with a submilli-PIXE camera. The concentration of cesium in plants was observed to increase as concentrations in the medium increased. As the concentration of cesium in the medium increased, the transfer coefficient decreased. However, there was little difference between the 250 and 500 ppm treatments. In future work, PIXE analysis will be performed on different mediums and the relationship with other materials will be investigated.

  7. Analysis of cesium-137 vertical distribution in the profile of plowed chernozems at different schemes of their assaying

    International Nuclear Information System (INIS)

    Paramonova, T.A.; Komissarova, O.L.; Belyaev, V.R.; Ivanov, M.M.

    2016-01-01

    In 2011-2015 the assessment of profile cesium-137 distribution in agrocenosis of chernozem zone on the territory of the Plavsk radioactive spot in Tula region formed after the Chernobyl accident has been carried out. It is shown that up until now non-uniformity of cesium-137 vertical distribution over the plowed chernozems profile may be occurred, it should be taken into account at radioecological survey of post-Chernobyl landscapes. For correct evaluation of radioecological state of plowed soils their systematic monitoring on the base of preliminary analysis of cesium-137 distribution and also with the account of agrotechnical peculiarities of various crops cultivation is recommended. On the Plavsk radioactive spot territory the most adequate assessments of cesium-137 stores in plowed chernozems one can obtain on the base of assaying the upper 30-cm soil depth, including not only current topsoil, but also old-arable horizon formed by deep rehabilitation plowing [ru

  8. Cesium separation using integrated electro-membrane technique

    International Nuclear Information System (INIS)

    Fors, Patrik; Lillfors-Pintér, Christina; Widestrand, Henrik; Velin, Anna; Bengtsson, Bernt

    2014-01-01

    Conventional separation technologies such as ion exchange, electro-deionisation and cross flow filtration are not always effective to eliminate nuclides, which are weekly ionised, complexed or hydrated in effluents. Specific nuclide selective absorbers perform well for the treatment of active and contaminated wastewaters but most absorbers generate additional waste while treating high volumes of contaminated water and often show limitations in operating at high flow rates. Electrochemical Ion Exchange (EIX) and EIX in combination with absorbers may offer an alternative solution that overcomes those limitations. This paper reports on the optimization and performance of the integrated technique EIX, for the treatment of low activity effluents that contain cesium and other nuclides. The three-compartment EIX system, which operates with authentic reactor coolant with enhanced nuclide content, indicates high, over 90%, elimination of cesium in a single pass operation mode. With the in-situ and instant ion exchange regeneration, the system successfully reduces the activity from an initial range of 400-2600 Bq/kg to close to detection limit at a velocity of 10-15 cm/min. The applied current density varies between 50-200 mA/cm 2 and the mass balance is close to 100%. During the process, the eliminated cesium and other nuclides are concentrated up to the limits where reverse migration from the concentrated chamber occurs. The concentrate could then be treated with specific absorbents at low flow rates. EIX in combination with cesium-selective ion exchanger CsTreat ® separates the cesium-137 efficiently, but up to now the process does not perform according to EIX principles for the treatment of low grade radioactive wastewaters it rather performs as an irreversible adsorber. The aim with the outcome of the presently ongoing long-term tests is to further support the Best Available Technique Minimizing All Nuclide (BATMAN) projects of Vattenfall NPPs. (author)

  9. Analysis of cesium extracting solvent using GCMS and HPLC

    International Nuclear Information System (INIS)

    White, T.L.; Herman, C.C.; Crump, S.L.; Marinik, A.R.; Lambert, D.P.; Eibling, R.E.

    2007-01-01

    A high-level waste (HLW) remediation process scheduled to begin in 2007 at the Savannah River Site is the Modular Caustic Side Solvent Extraction (CSSX) Unit (MCU). The MCU will use a hydrocarbon solvent (diluent) containing a cesium extractant, a calix[4]arene compound, to extract radioactive cesium from caustic HLW. The resulting decontaminated HLW waste or raffinate will be processed into grout at the Saltstone Production Facility (SPF). The cesium containing CSSX stream will undergo washing with dilute nitric acid followed by stripping of the cesium nitrate into a very dilute nitric acid or the strip effluent stream and the CSSX solvent will be recycled. The Defense Waste Processing Facility (DWPF) will receive the strip effluent stream and immobilize the cesium into borosilicate glass. Excess CSSX solvent carryover from the MCU creates a potential flammability problem during DWPF processing. Bench-scale DWPF process testing was performed with simulated waste to determine the fate of the CSSX solvent components. A simple high performance liquid chromatography (HPLC) method was developed to identify the modifier (which is used to increase Cs extraction and extractant solubility) and extractant within the DWPF process. The diluent and trioctylamine (which is used to suppress impurity effect and ion-pair disassociation) were determined using gas chromatography mass spectroscopy (GCMS). To close the organic balance, two types of sample preparation methods were needed. One involved extracting aqueous samples with methylene chloride or hexane, and the second was capturing the off gas of the DWPF process using carbon tubes and rinsing the tubes with carbon disulfide for analysis. This paper addresses the development of the analytical methods and the bench-scale simulated waste study results. (author)

  10. Hydrological methods preferentially recover cesium from nuclear waste salt cake

    International Nuclear Information System (INIS)

    Brooke, J.N.; Hamm, L.L.

    1997-01-01

    The Savannah River Site is treating high level radioactive waste in the form of insoluble solids (sludge), crystallized salt (salt cake), and salt solutions. High costs and operational concerns have prompted DOE to look for ways to improve the salt cake treatment process. A numerical model was developed to evaluate the feasibility of pump and treat technology for extracting cesium from salt cake. A modified version of the VAM3DCG code was used to first establish a steady-state flow field, then to simulate 30 days of operation. Simulation results suggest that efficient cesium extraction can be obtained with low displacement volumes. The actual extraction process will probably be less impressive because of nonuniform properties. 2 refs., 2 figs

  11. Concentration of caesium isotopes in foodstuffs in Poland

    International Nuclear Information System (INIS)

    Grabowski, D.; Rubel, B.; Muszynski, W.; Kurowski, W.; Swietochowska, J.; Smagala, G.

    2000-01-01

    One of the sources of the radioactive doses obtained by people resulting from the radiological contamination of the environment, is the transfer of radionuclides to the organism via ingestion. Radioactive isotopes in foodstuffs appear as a result of nuclear activities on the globe, mainly because of nuclear explosion and, recently, after the Chernobyl accident. Since the early sixties the network of Service for Measurement of Radioactive Contamination in Poland systematically controlled all kinds of important food products. Radiochemical methods and gamma spectrometry has been used to determination the activity of radioactive isotopes. This contribution reports of the determination of 134 Cs and 137 Cs concentration in milk, meat, vegetables, fruits, cereals and 'forest products' during period 1985-1999. In 1985 the average 137 Cs level was below 1 Bq/kg (except forest products). Moreover, no regional differences were observed the whole territory of Poland. After the Chernobyl accident situation changed completely. Average activity of 137 Cs in milk was 25 Bq/l in May 1986, 20-25 Bq/kg in beef and 10-15 Bq/kg in pork (summer months). Also fruit picked up in June and July was contaminated, mainly currents. The contamination of vegetables was less important. The activity of cesium isotopes in forest mushrooms and wild game were much higher than in other tested foodstuffs. From the 1987 level of radioactive contamination was decreasing gradually. In 1999 the activity of 137 Cs of vegetables, cereals, fruit was on level as it has been in 1985 as for meat and milk it is higher. Level of radiocesium in 'forest products' is still high. The average annual effective dose from ingestion of radiocesium was on level 0.088 mSv in 1986 and 0.006 mSv in 1999. (author)

  12. Research on isotope geology. Assessment of heat production potential of granitic rocks and development of geothermal exploration techniques using radioactive/stable isotopes and fission track 2

    Energy Technology Data Exchange (ETDEWEB)

    Shin, Seong Cheon; Chi, Se Jung [Korea Inst. of Geology Mining and Materials, Taejon (Korea, Republic of)

    1995-12-01

    Radioelements and heat production rates of granitic rocks and stable isotopes of groundwaters were analyzed to investigate the geothermal potential of Wolchulsan granite complex in the southern Yeongam area. Wolchulsan granite complex is composed mainly by Cretaceous pink alkali-feldspar granite and partly Jurassic biotite granite. The main target for the geothermal exploration is the alkali-feldspar granite that is known in general to be favorable geothermal reservoir(e.g., Shap granite in UK). To develop exploration techniques for geothermal anomalies, all geochemical data were compared to those from the Jeonju granite complex. Heat production rates(HPR) of the alkali-feldspar granite is 1.8 - 10.6 {mu}Wm{sup -3}. High radio-thermal anomalies were revealed from the central western and northern parts of the granite body. These are relatively higher than the Caledonian hot dry granites in the UK. The integrated assessment of Wolchulsan granite complex suggests potential of the Cretaceous alkali-feldspar granite as a geothermal targets. Groundwater geochemistry of the Yeongam area reflects simple evaporation process and higher oxidation environment. Stable isotope data of groundwaters are plotted on or close to the Meteoric Water Line(MWL). These isotopic data indicate a significant meteoric water dominance and do not show oxygen isotope fractionation between groundwater and wall rocks. In despite of high HPR values of the Yeongam alkali-feldspar granite, groundwater samples do not show the same geochemical properties as a thermal water in the Jeonju area. This reason can be well explained by the comparison with geological settings of the Jeonju area. The Yeongam alkali-feldspar granite does not possess any adjacent heat source rocks despite its high radio-thermal HPR. While the Jeonju granite batholith has later heat source intrusive and suitable deep fracture system for water circulation with sedimentary cap rocks. (Abstract Truncated)

  13. Selective extraction of cesium: from compound to process

    International Nuclear Information System (INIS)

    Simon, N.; Eymard, S.; Tournois, B.; Dozol, J.F.

    2000-01-01

    Under the French law of 30 December 1991 on nuclear waste management, research is conducted to recover long-lived fission products from high-level radioactive effluents generated by spent fuel reprocessing, in order to destroy them by transmutation or encapsulate them in specific matrices. Cesium extraction with mono and bis-crown calix(4)arenes (Frame 1) is a candidate for process development. These extractants remove cesium from highly acidic or basic pH media even with high salinity. A real raffinate was treated in 1994 in a hot cell to extract cesium with a calix-crown extractant. The success of this one batch experiment confirmed the feasibility of cesium decontamination from high-level liquid waste. It was then decided to develop a process flowchart to extract cesium selectively from high-level raffinate, to be included in the general scheme of long-lived radionuclide partitioning. It was accordingly decided to develop a process based on liquid-liquid extraction and hence optimize a calixarene/diluent solvent according to: - hydraulic properties: density, viscosity, interfacial tension, - chemical criteria: sufficient cesium extraction (depending on the diluent), kinetics, third phase elimination... New mono-crown-calixarenes branched with long aliphatic groups (Frame 2) were designed to be soluble in aliphatic diluents. To prevent third phase formation associated with nitric acid extraction, the addition of modifiers (alcohol, phosphate and amide) in the organic phase was tested (Frame 3). Table 1 shows examples of calixarene/diluent systems suitable for a process flowchart, and Figure 2 provides data on cesium extraction with these new systems. Alongside these improvements, a system based on a modified 1,3-di(n-octyl-oxy)2,4-calix[4]arene crown and a modified diluent was also developed, considering a mixed TPH/NPHE system as the diluent, where TPH (hydrogenated tetra propylene) is a common aliphatic industrial solvent and NPHE is nitrophenyl

  14. Cesium transport data for HTGR systems

    International Nuclear Information System (INIS)

    Myers, B.F.; Bell, W.E.

    1979-09-01

    Cesium transport data on the release of cesium from HTGR fuel elements are reviewed and discussed. The data available through 1976 are treated. Equations, parameters, and associated variances describing the data are presented. The equations and parameters are in forms suitable for use in computer codes used to calculate the release of metallic fission products from HTGR fuel elements into the primary circuit. The data cover the following processes: (1) diffusion of cesium in fuel kernels and pyrocarbon, (2) sorption of cesium on fuel rod matrix material and on graphite, and (3) migration of cesium in graphite. The data are being confirmed and extended through work in progress

  15. Results of several years experiments on the absorption of radioactive strontium and caesium by cultivated plants (1962); Compte rendu d'experiences de plusieurs annees sur l'absorption du strontium et du cesium radioactifs par des plantes cultivees (1962)

    Energy Technology Data Exchange (ETDEWEB)

    Michon, M [Commissariat a l' Energie Atomique, Dept. de Protection Sanitaire, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires; Benard, M; Flanzy, M [Station Centrale de Technologie des Produits Vegetaux, 11 - Narbonne (France); Fioramonti, M; Marty, M [Station Agronomique de Toulouse, 31 (France); Barbier, M; Le Blaye, M; Brossard, M [Societe Centrale d' Agronomie, 78 - Versailles (France)

    1962-07-01

    This report follows on to the report number CEA 1860 and uses results obtained in 1960 to give more precise details concerning the data presented in the preceding report. First results obtained on the vine are given. The Sr absorption coefficient has varied very little from one year to the next and that of caesium has slightly diminished. The values obtained suggest that the concentrations of {sup 90}Sr and {sup 137}Cs in irrigation water should not exceed 1/5 of the maximum permissible concentration in drinking water. (authors) [French] Ce rapport fait suite au rapport CEA 1860 et precise grace aux resultats acquis en 1960 les donnees exprimees dans le precedent rapport. Il y est fait mention des premiers resultats obtenus pour la vigne. Le coefficient d'absorption du Sr a peu varie d'une annee sur l'autre et celui du cesium legerement diminue. Les valeurs obtenues permettent de penser qu'il serait souhaitable que la concentration en {sup 90}Sr et en {sup 137}Cs dans l'eau d'irrigation ne depasse pas le 1/5 de la concentration maxima admissible pour l'eau de boisson. (auteurs)

  16. Method of processing radioactive liquid waste

    International Nuclear Information System (INIS)

    Motojima, Kenji; Kawamura, Fumio.

    1981-01-01

    Purpose: To increase the efficiency of removing radioactive cesium from radioactive liquid waste by employing zeolite affixed to metallic compound ferrocyanide as an adsorbent. Method: Regenerated liquid waste of a reactor condensation desalting unit, floor drain and so forth are collected through respective supply tubes to a liquid waste tank, and the liquid waste is fed by a pump to a column filled with zeolite containing a metallic compound ferrocyanide, such as with copper, zinc, manganese, iron, cobalt, nickel or the like. The liquid waste from which radioactive cesium is removed is dried and pelletized by volume reducing and solidifying means. (Yoshino, Y.)

  17. Radioactivity in the Marine Environment. Chapter 1

    International Nuclear Information System (INIS)

    Zal U'yun Wan Mahmood; Abdul Kadir Ishak; Norfaizal Mohamad; Wo, Y.M.; Kamarudin Samuding

    2015-01-01

    Radionuclide (radioactive isotopes or radioisotopes is widely distributed on the ground primarily in marine environments. Nowadays, more than 340 isotopes has been identified exist in our earth especially in marine environment. From that total, 80 isotopes was radioactive. The existence of radioactivity in the marine environment is through the direct and indirect distribution of radionuclides

  18. The Effect of Pretreatment on the Cesium Adsorption Ability of IONSIV(C)IE-911

    International Nuclear Information System (INIS)

    Fondeur, F.F.

    1999-01-01

    The recovery of plutonium from reactor fuel elements at the Savannah River Site generated nearly 34 million gallons of high level waste. The Site stores the waste as a mixture of precipitated metal hydroxides and associated supernatant liquid with elevated concentrations of free hydroxide. The liquid fraction contains the majority of the radioactive cesium

  19. Uranium isotopic analysis of depleted uranium in presence of other radioactive materials by using nondestructive gamma-ray measurements in coaxial and planar Ge detectors

    International Nuclear Information System (INIS)

    Yucel, H.; Yeltepe, E.; Dikmen, H.; Turhan, Sh.; Vural, M.

    2006-01-01

    Full text: The isotopic abundance of depleted uranium samples in the presence of other radioactive materials, especially actinide isotopes such as Th 232, Np 237-Pa 233 and Am 241 can be determined from two gamma-ray spectrometric methods. One is the absolute method which employs non-destructive gamma-ray spectrometry for energies below 1001 keV using a coaxial Ge detector calibrated with a set of standards. The other is the multi-group analysis (MGA) method using the low energy region (< 300 keV) with a planar Ge detector intrinsically calibrated with gamma and X-rays of uranium without use of standards. At present absolute method, less intense but cleaner gamma peaks at 163.33 keV (5.08 percent) and 205 keV(5.01 percent) of U 235 are preferred over more intense peaks at 143.76 keV(10.76 percent), possible interference with 143.25 keV(0.44 percent) of Np 237 and 185.705 keV(57.2 percent), possible interference with 186.21 keV(3.51 percent) of Ra 226. In the high energy region the 1001.03 keV(0.837 percent) peak of Pa 234 m is used for the isotopic abundance analysis because the more intense 63.3 keV peak of Th 234 daughter of U 238 parent has a fully multiplet(62.86 keV+63.29 keV) and include the interferences of the 62.70 keV(1.5 percent) peak of Pa 234, the 63.81 keV(0.263 percent) peak of Th 232 and the 63.90 keV(0.011 percent) peak of Np 237. Although the MGA method is quicker and more practical, the more laborious absolute gamma spectrometric method can give more accurate results for the isotopic determination of depleted uranium samples. The relative uranium abundances obtained with the second method (i,e., MGA) are in general inconsistent with the declared values for the uranium samples in the presence of the above mentioned actinides. The reason for these erroneous results is proposed to be the interference of the gamma and X-rays of uranium in the 80-130 keV region used in MGA with those emissions from other radioactive materials present

  20. Isotopic marking and tracers

    International Nuclear Information System (INIS)

    Morel, F.

    1997-01-01

    The use of radioactive isotopes as tracers in biology has been developed thanks to the economic generation of the required isotopes in accelerators and nuclear reactors, and to the multiple applications of tracers in the life domain; the most usual isotopes employed in biology are carbon, hydrogen, phosphorus and sulfur isotopes, because these elements are present in most of organic molecules. Most of the life science knowledge appears to be dependent to the extensive use of nuclear tools and radioactive tracers; the example of the utilization of radioactive phosphorus marked ATP to study the multiple reactions with proteins, nucleic acids, etc., is given

  1. Cesium absorption from acidic solutions using ammonium molybdophosphate on a polyacrylonitrile support (AMP-PAN)

    International Nuclear Information System (INIS)

    Miller, C.J.; Olson, A.L.; Johnson, C.K.

    1995-01-01

    Recent efforts at the Idaho Chemical Processing Plant (ICPP) have included evaluation of cesium removal technologies as applied to ICPP acidic radioactive waste streams. Ammonium molybdophosphate (AMP) immobilized on a polyacrylonitrile support (AMP-PAN) has been studied as an ion exchange agent for cesium removal from acidic waste solutions. Capacities, distribution coefficients, elutability, and kinetics of cesium-extraction have been evaluated. Exchange breakthrough curves using small columns have been determined from 1M HNO 3 and simulated waste solutions. The theoretical capacity of AMP is 213 g Cs/kg AMP. The average experimental capacity in batch contacts with various acidic solutions was 150 g Cs/kg AMP. The measured cesium distribution coefficients from actual waste solutions were 3287 mL/g for dissolved zirconia calcines, and 2679 mL/g for sodium-bearing waste. The cesium in the dissolved alumina calcines was analyzed for; however, the concentration was below analytical detectable limits resulting in inconclusive results. The reaction kinetics are very rapid (2-10 minutes). Cesium absorption appears to be independent of acid concentration over the range tested (0.1 M to 5 M HNO 3 )

  2. Localization of the placenta in the 3 trimester of gestation with the use of a gamma-camera and radioactive sup(113m)In indium isotope

    Energy Technology Data Exchange (ETDEWEB)

    Brudnik, A.; Chromy, G.; Ulfik, A.; Bielawski, J.; Wasylewski, A. (Slaska Akademia Medyczna, Katowice (Poland))

    1980-01-01

    In 56 women, treated because of uterine bleedings in the 3 trimester of gestation the localization of the placenta was looked for with use of a gamma camera (Toshiba Co.) and indium radioisotope 113-In. The methodic procedures were elaborated for the application of the gamma-camera and the utilization of radioactive marker /sup 125/Sb in the anatomic reference areas. Full conformity of results with findings at cesarean section was met. Isotope placentography with the application of gamma camera gives a high percentage of adequate diagnoses, least dose of exposition, uncomplicated procedures. The negative diagnosis in suspected cases of placenta previa permitted to decrease the time of hospital stay in a number of cases observed because of uterine bleedings in the 3 trimester of pregnancy.

  3. Localization of the placenta in the 3 trimester of gestation with the use of a gamma-camera and radioactive sup(113m)In indium isotope

    International Nuclear Information System (INIS)

    Brudnik, A.; Chromy, G.; Ulfik, A.; Bielawski, J.; Wasylewski, A.

    1980-01-01

    In 56 women, treated because of uterine bleedings in the 3 trimester of gestation the localization of the placenta was looked for with use of a gamma camera (Toshiba Co.) and indium radioisotope 113-In. The methodic procedures were elaborated for the application of the gamma-camera and the utilization of radioactive marker 125 Sb in the anatomic reference areas. Full conformity of results with findings at cesarean section was met. Isotope placentography with the application of gamma camera gives a high percentage of adequate diagnoses, least dose of exposition, uncomplicated procedures. The negative diagnosis in suspected cases of placenta previa permitted to decrease the time of hospital stay in a number of cases observed because of uterine bleedings in the 3 trimester of pregnancy. (author)

  4. Environmental radioactivity in Greenland 1977

    International Nuclear Information System (INIS)

    Aarkrog, A.; Lippert, J.

    1978-07-01

    Measurements of fallout radioactivity in Greenland in 1977 are reported. Strontium-90 (and Cesium-137 in most cases) was determined in samples of precipitation, sea water, vegetation, animals, and drinking water. Estimates are given of the mean contents of 90 Sr and 137 Cs in the human diet in Greenland in 1977. (author)

  5. Hybrid micro-particles as a magnetically-guidable decontaminant for cesium-eluted ash slurry

    Science.gov (United States)

    Namiki, Yoshihisa; Ueyama, Toshihiko; Yoshida, Takayuki; Watanabe, Ryoei; Koido, Shigeo; Namiki, Tamami

    2014-09-01

    Decontamination of the radioactive cesium that is widely dispersed owing to a nuclear power station accident and concentrated in fly ash requires an effective elimination system. Radioactive fly ash contains large amounts of water-soluble cesium that can cause severe secondary contamination and represents a serious health risk, yet its complete removal is complicated and difficult. Here it is shown that a new fine-powder formulation can be magnetically guided to eliminate cesium after being mixed with the ash slurry. This formulation, termed MagCE, consists of a ferromagnetic porous structure and alkaline- and salt-resistant nickel ferrocyanide. It has potent cesium-adsorption- and magnetic-separation-properties. Because of its resistance against physical and chemical attack such as with ash particles, as well as with the high pH and salt concentration of the ash slurry, MagCE simplifies the decontamination process without the need of the continued presence of the hazardous water-soluble cesium in the treated ash.

  6. Radioactive fall-out in Norway after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Skjerve, Eystein [Dept. of Food Hygiene, Norwegian College of Veterinary Medicine (Norway)

    1986-07-01

    During the fall-out from the atmosphere during the fifties and sixties, a system of local control of radioactive contamination of food was built up. (LORACON - LOcal RAdioactivity COntrol). The different Meat and Food Inspection Services were equipped with Geiger Mueller instruments. The system was in operation until late seventies. From 1977 there was no testing and calibration of the instruments. The development towards a reduction of the state of readiness was accelerated when the Norwegian Parliament decided that Norway should not establish any nuclear power plants (1979). Only the universities and special institutions as the National Institute of Radiation Hygiene and the Institute for Energy Technique were still able to analyse on radioactive isotopes. The confusion about how much radioactive fall-out from the Chernobyl reactor accident Norway received lasted for some weeks in Norway. Partially, this was due to the lack of instruments, but also many experts rejected the idea that an accident so far away might cause these amounts of fall-out consisted of Iodine and Cesium. The fall-out followed a very irregular pattern both nationally and locally with the mountain areas in Middle Norway most affected.

  7. Radioactive fall-out in Norway after the Chernobyl accident

    International Nuclear Information System (INIS)

    Skjerve, Eystein

    1986-01-01

    During the fall-out from the atmosphere during the fifties and sixties, a system of local control of radioactive contamination of food was built up. (LORACON - LOcal RAdioactivity COntrol). The different Meat and Food Inspection Services were equipped with Geiger Mueller instruments. The system was in operation until late seventies. From 1977 there was no testing and calibration of the instruments. The development towards a reduction of the state of readiness was accelerated when the Norwegian Parliament decided that Norway should not establish any nuclear power plants (1979). Only the universities and special institutions as the National Institute of Radiation Hygiene and the Institute for Energy Technique were still able to analyse on radioactive isotopes. The confusion about how much radioactive fall-out from the Chernobyl reactor accident Norway received lasted for some weeks in Norway. Partially, this was due to the lack of instruments, but also many experts rejected the idea that an accident so far away might cause these amounts of fall-out consisted of Iodine and Cesium. The fall-out followed a very irregular pattern both nationally and locally with the mountain areas in Middle Norway most affected

  8. Shape coexistence in krypton and selenium light isotopes studied through Coulomb excitation of radioactive ions beams; Etude de la coexistence de formes dans les isotopes legers du krypton et du selenium par excitation Coulombienne de faisceaux radioactifs

    Energy Technology Data Exchange (ETDEWEB)

    Clement, E

    2006-06-15

    The light krypton isotopes show two minima in their potential energy corresponding to elongated (prolate) and compressed (oblate) quadrupole deformation. Both configuration are almost equally bound and occur within an energy range of less than 1 MeV. Such phenomenon is called shape coexistence. An inversion of the ground state deformation from prolate in Kr{sup 78} to oblate in Kr{sup 72} with strong mixing of the configurations in Kr{sup 74} and Kr{sup 76} was proposed based on the systematic of isotopic chain. Coulomb excitation experiments are sensitive to the quadrupole moment. Coulomb excitation experiments of radioactive Kr{sup 74} and Kr{sup 76} beam were performed at GANIL using the SPIRAL facility and the EXOGAM spectrometer. The analysis of these experiments resulted in a complete description of the transition strength and quadrupole moments of the low-lying states. They establish the prolate character of the ground state and an oblate excited state. A complementary lifetime measurement using a 'plunger' device was also performed. Transition strength in neighboring nuclei were measured using the technique of intermediate energy Coulomb excitation at GANIL. The results on the Se{sup 68} nucleus show a sharp change in structure with respects to heavier neighboring nuclei. (author)

  9. Development and test of a cryogenic trap system dedicated to confinement of radioactive volatile isotopes in SPIRAL2 post-accelerator

    Science.gov (United States)

    Souli, M.; Dolégiéviez, P.; Fadil, M.; Gallardo, P.; Levallois, R.; Munoz, H.; Ozille, M.; Rouillé, G.; Galet, F.

    2011-12-01

    A cryogenic trap system called Cryotrap has been studied and developed in the framework of nuclear safety studies for SPIRAL2 accelerator. The main objective of Cryotrap is to confine and reduce strongly the migration of radioactive volatile isotopes in beam lines. These radioactive gases are produced after interaction between a deuteron beam and a fissile target. Mainly, Cryotrap is composed by a vacuum vessel and two copper thermal screens maintained separately at two temperatures T1=80 K and T2=20 K. A Cryocooler with two stages at previous temperatures is used to remove static heat losses of the cryostat and ensure an efficient cooling of the system. Due to strong radiological constraints that surround Cryotrap, the coupling system between Cryocooler and thermal screens is based on aluminum thermo-mechanical contraction. The main objective of this original design is to limit direct human maintenance interventions and provide maximum automated operations. A preliminary prototype of Cryotrap has been developed and tested at GANIL laboratory to validate its design, and determine its thermal performance and trapping efficiency. In this paper, we will first introduce briefly SPIRAL2 project and discuss the main role of Cryotrap in nuclear safety of the accelerator. Then, we will describe the proposed conceptual design of Cryotrap and its main characteristics. After that, we will focus on test experiment and analyze experimental data. Finally, we will present preliminary results of gas trapping efficiency tests.

  10. Measures against radioactive contamination due to Fukushima First Nuclear Power Plant accidents. Part 3. Removing and decontamination of contaminated soil

    International Nuclear Information System (INIS)

    Ishii, K.; Terakawa, A.; Matsuyama, S.

    2012-01-01

    We studied the structure of radioactive cesium distribution in soil and found the exponential dependence. This behavior could be explained theoretically. We developed a useful method to decontaminate the soil contaminated with radioactive cesium atoms. We applied our method to the contaminated school yards of elementary schools of Marumori town and decontaminated total area of about 7000 m"2. (author)

  11. Isotopic composition of water in a deep unsaturated zone beside a radioactive-waste disposal area near Beatty, Nevada

    Science.gov (United States)

    Stonestrom, David A.; Prudic, David E.; Striegl, Robert G.; Morganwalp, David W.; Buxton, Herbert T.

    1999-01-01

    The isotopic composition of water in deep unsaturated zones is of interest because it provides information relevant to hydrologic processes and contaminant migration. Profiles of oxygen-18 (18O), deuterium (D), and tritium (3H) from a 110-meter deep unsaturated zone, together with data on the isotopic composition of ground water and modern-day precipitation, are interpreted in the context of water-content, water-potential, and pore-gas profiles. At depths greater than about three meters, water vapor and liquid water are in approximate equilibrium with respect to D and 18O. The vapor-phase concentrations of D and 18O have remained stable through repeated samplings. Vapor-phase 3H concentrations have generally increased with time, requiring synchronous sampling of liquid and vapor to assess equilibrium. Below 30 meters, concentrations of D and 18O in pore water become approximately equal to the composition of ground water, which is isotopically lighter than modern precipitation and has a carbon-14 (14C) concentration of about 26 percent modern carbon. These data indicate that net gradients driving fluxes of water, gas, and heat are directed upwards for undisturbed conditions at the Amargosa Desert Research Site (ADRS). Superimposed on the upward-directed flow field, tritium is migrating away from waste in response to gradients in tritium concentrations.

  12. Psychological and mobile evaluation of intra-uterus children exposed to the radiation with cesium-137

    International Nuclear Information System (INIS)

    Ferreira, Celia Marly

    1995-01-01

    The presented work had as objective the accomplishment of a comparative study of cesium-137 radioactive element effects in the psychological and motor development of children which were going submitted the intra-uterus irradiation during the chronological age of three years. The comparison of the results of study is done through a group-control composed for five children without any involvement with the cesium-137 accident - occurred in 1987 in Goiania, Brazil - of same social, economic and cultural level and with the same age of the reached

  13. Separation of cesium from simulated active waste using zinc hexacyanoferrate supported composite

    International Nuclear Information System (INIS)

    Somida, H.H.; El Zahhar, A.A.; Shehata, M.K.; El Naggar, H.A.

    2003-01-01

    Potassium zinc hexacyanoferrate (KZnHCF) was prepared and supported on polyacrylonitrile (PAN) binding polymer. This composite was characterized and used to study the elimination of cesium from acidic radioactive waste containing Sr(II), Eu(II), Am(II), Zr(IV), Hf(IV) and Nb(V) using batch and column techniques. The sorption capacity of this composite for cesium was found to be 1.14 meq/g for column technique. The effect of presence of NH 4 SCN, NaNo 3 and other complexing agents in the aqueous solutions was studied

  14. Radioactivity levels of trees before and after the Chernobyl reactor accident as well as in vitro determinations of cesium to evaluate leaf uptake and deep zone distribution in adaxial leaf cuticles

    International Nuclear Information System (INIS)

    Ertel, J.

    1990-12-01

    It was the aim of the study described here to investigate into radionuclide concentrations in various species of trees encountered in forests that are detectable over prolonged periods of time after the Chernobyl accident. Separate radionuclide measurements for the individual tree organs (leaves, needles and branches of different ages, wood, fruit and semen) permitted conclusions to be drawn as to the fate of the isotopes under investigation. A survey is given of the distribution of invading radionuclides, changes over time and their migration into newly grown parts of trees. The findings are evaluated in the context of measurements made in comparable samples obtained before the Chernobyl accident. (orig.) [de

  15. Suicide with 137 cesium

    International Nuclear Information System (INIS)

    Vasileva, B.

    1976-01-01

    A case report is presented of suicide by radiation exposure after a preceding attempt with potassium ferrocyanide. The subject, a 30-year-old nondestructive-testing technician, held with his right fingers and then placed in his left shirt pocket a metal-canned 5,3-Ci 137 Cs source. Despite appearance of signs of severe topical injury by day 3 after the incident and development of systemic toxicity symptoms with indications of affection of internal organs by day 16, medical aid was not sought until day 21 when efforts at management proved unable to prevent fatal outcome. A prominent distinguishing characteristic of this mode of suicide is that the deed's sequelae are delayed in coming into effect. Cases known to have occurred are extremely rare (only two have been described in the literature). This is likely to be related to a distinct unpopularity of radioactive materials as well as their limited availability to the general public. The subjects that did use them were radiation workers having access to such substances; being acquainted with the biological effects of radiation, they, nevertheless, have chosen this protracted and distressful way of taking their lives. (A.B.)

  16. Method for primary containment of cesium wastes

    International Nuclear Information System (INIS)

    Angelini, P.; Arnold, W.D.; Blanco, R.E.; Bond, W.D.; Lackey, W.J.; Stinton, D.P.

    1983-01-01

    A method for producing a cesium-retentive waste form, characterized by a high degree of compositional stability and mechanical integrity, is provided by subjecting a cesium-loaded zeolite to heat under conditions suitable for stabilizing the zeolite and immobilizing the cesium, and coating said zeolite for sufficient duration within a suitable environment with at least one dense layer of pyrolytic carbon to seal therein said cesium to produce a final, cesium-bearing waste form. Typically, the zeolite is stabilized and the cesium immobilized in less than four hours by confinement within an air environment maintained at about 600 0 C. Coatings are thereafter applied by confining the calcined zeolite within a coating environment comprising inert fluidizing and carbon donor gases maintained at 1,000* C. For a suitable duration

  17. Cesium-137, a drama recounted

    International Nuclear Information System (INIS)

    Vieira, Suzane de Alencar

    2013-01-01

    The radiological accident with Cesium-137, which started on Goiania in 1987, did not stop with the end of radiological contamination and continues in a judicial, scientific and narrative process of identification and recognition of new victims. The drama occupies a central place on the dynamics of radiological event, as it extends its limits, inflects its intensity and updates the event. As a narrative of the event, the ethnography incorporates and brings up to date the drama as an analysis landmark and the description of the theme as it is absorbed by a dramatic process. Cesium-137, a drama recounted is a textual experimentation based on real events and characters picked out from statements reported in various narratives about the radiological accident. (author)

  18. Myocardial imaging with cesium-130

    International Nuclear Information System (INIS)

    Harper, P.V.; Resnekov, L.; Stark, V.; Odeh, N.

    1984-01-01

    Recently comparative studies using nitrogen-13 ammonia and cesium-130 have shown strikingly different myocardial localization patterns in the same subjects with ischemic heart disease. Initial localization of ammonia, an avidly extracted agent, reflects the perfusion pattern in viable myocardial tissue. The myocardial localization of cesium ion, taking place more slowly over 15 to 20 minutes, is apparently much less flow dependent, causing uptake defects shown with ammonia to be largely filled in. Cesium thus appears to provide information on the extent of the viable myocardial mass, apart from perfusion. Cesium-130 (t1/2 30 m) decays by positron emission and electron capture. The whole body radiation absorbed dose, assuming uniform distribution, is 24 mrad/mCi. While abundant production of Cs-130 results from proton bombardment of natural xenon [Xe-130(rho,n)Cs-130] at 15 MeV, small amounts of Cs-129, -131, and -132 are also produced, and enriched Xe-130 is not available. Alternatively almost completely uncontaminated Cs-130 is available by alpha bombardment of natural I-127. Anhydrous sodium iodide is dissolved in acetone and a thin layer (≅20 mg per centimeter squared) is evaporated onto the gold plated tip of the internal target backing which is oscillated vertically to spread out the area upon which the beam is incident. The target surface is inclined 2.5 degrees to the beam giving a power density of about 400 watts per centimeter squared at 100μA which is adequately handled by water cooling. A 30-minute bombardment yields 4 to 5 mCi of Cs-130 which is dissolved directly from the target. This approach appears to offer a new and helpful method for evaluating ischemic heart disease by permitting evaluation of viable myocardial mass

  19. Cesium migration in LMFBR fuel pins

    International Nuclear Information System (INIS)

    Karnesky, R.A.; Jost, J.W.; Stone, I.Z.

    1978-10-01

    The factors affecting the axial migration of cesium in mixed oxide fuel pins and the effects of cesium migration on fuel pin performance are examined. The development and application of a correlated model which will predict the occurrence of cesium migration in a mixed oxide (75 w/o UO 2 + 25 w/o PuO 2 ) fuel pins over a wide range of fabrication and irradiation conditions are described

  20. Strontium Isotopes in Pore Water as an Indicator of Water Flux at the Proposed High-Level Radioactive Waste Repository, Yucca Mountain, Nevada

    International Nuclear Information System (INIS)

    Marshall, B.; Futa, K.

    2004-01-01

    The proposed high-level radioactive waste repository at Yucca Mountain, Nevada, would be constructed in the high-silica rhyolite (Tptp) member of the Miocene-age Topopah Spring Tuff, a mostly welded ash-flow tuff in the ∼500-m-thick unsaturated zone. Strontium isotope compositions have been measured in pore water centrifuged from preserved core samples and in leachates of pore-water salts from dried core samples, both from boreholes in the Tptp. Strontium isotope ratios ( 87 Sr/ 86 Sr) vary systematically with depth in the surface-based boreholes. Ratios in pore water near the surface (0.7114 to 0.7124) reflect the range of ratios in soil carbonate (0.7112 to 0.7125) collected near the boreholes, but ratios in the Tptp (0.7122 to 0.7127) at depths of 150 to 370 m have a narrower range and are more radiogenic due to interaction with the volcanic rocks (primarily non-welded tuffs) above the Tptp. An advection-reaction model relates the rate of strontium dissolution from the rocks with flow velocity. The model results agree with the low transport velocity (∼2 cm per year) calculated from carbon-14 data by I.C. Yang (2002, App. Geochem., v. 17, no. 6, p. 807-817). Strontium isotope ratios in pore water from Tptp samples from horizontal boreholes collared in tunnels at the proposed repository horizon have a similar range (0.7121 to 0.7127), also indicating a low transport velocity. Strontium isotope compositions of pore water below the proposed repository in core samples from boreholes drilled vertically downward from tunnel floors are more varied, ranging from 0.7112 to 0.7127. The lower ratios ( 87 Sr/ 86 Sr of 0.7115. Ratios lower than 0.7115 likely reflect interaction of construction water with concrete in the tunnel inverts, which had an 87 Sr/ 86 Sr < 0.709. These low Sr ratios indicate penetration of construction water to depths of ∼20 m below the tunnels within three years after construction, a transport velocity of ∼7 m per year. These studies show that

  1. Electrically switched cesium ion exchange

    International Nuclear Information System (INIS)

    Lilga, M.A.; Orth, R.J.; Sukamto, J.P.H.; Schwartz, D.T.; Haight, S.M.; Genders, J.D.

    1997-04-01

    Electrically Switched Ion Exchange (ESIX) is a separation technology being developed as an alternative to conventional ion exchange for removing radionuclides from high-level waste. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution are controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. A case study for the KE Basin on the Hanford Site was conducted based on the results of the development testing. Engineering design baseline parameters for film deposition, film regeneration, cesium loading, and cesium elution were used for developing a conceptual system. Order of magnitude cost estimates were developed to compare with conventional ion exchange. This case study demonstrated that KE Basin wastewater could be processed continuously with minimal secondary waste and reduced associated disposal costs, as well as lower capital and labor expenditures

  2. Cesium heat-pipe thermostat

    Energy Technology Data Exchange (ETDEWEB)

    Wu, F.; Song, D.; Sheng, K.; Wu, J. [Changcheng Institute of Metrology and Measurement, 100095, Beijing (China); Yi, X. [China National South Aviation industry CO., LTD., 412002, Hunan (China); Yu, Z. [Dalian Jinzhou Institute of Measurement and Testing, 116100, Liaoning (China)

    2013-09-11

    In this paper the authors report a newly developed Cesium Heat-Pipe Thermostat (Cs HPT) with the operation range of 400 °C to 800 °C. The working medium is cesium (Cs) of 99.98% purity and contains no radioisotope. A Cs filing device is developed which can prevent Cs being in contact with air. The structural material is stainless steel. A 5000 h test has been made to confirm the compatibility between cesium and stainless steel. The Cs HPT has several thermometer wells of 220mm depth with different diameters for different sizes of thermometers. The temperature uniformity of the Cs HPT is 0.06 °C to 0.20 °C. A precise temperature controller is used to ensure the temperature fluctuation within ±0.03 °C. The size of Cs HPT is 380mm×320mm×280mm with foot wheels for easy moving. The thermostat has been successfully used for the calibration of industrial platinum resistance thermometers and thermocouples.

  3. Chernobyl radioactivity in Turkish tea

    International Nuclear Information System (INIS)

    Molzahn, D.; Tufail, M.; Patzelt, P.

    1990-01-01

    Radioactivity measurement of Turkish tea of 1986 crops is reported. The total cesium activity ranged from about 5500 Bq kg -1 up to 43600 Bq kg -1 . Some other fission products from Chernobyl could be detected in the tea samples, e.g., 95 Zr, 95 Nb, 103 Ru, 106 Ru, 110m Ag and 125 Sb. In addition, some activity values found in tea from USSR are given. The transfer rate of cesium from tea leaves to tea water was found to be about 74%. (author) 6 refs.; 1 fig.; 2 tabs

  4. Estimation of Plutonium-240 Mass in Waste Tanks Using Ultra-Sensitive Detection of Radioactive Xenon Isotopes from Spontaneous Fission

    Energy Technology Data Exchange (ETDEWEB)

    Bowyer, Theodore W. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Gesh, Christopher J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Haas, Daniel A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hayes, James C. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Johns, Jesse M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lukins, Craig D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mahoney, Lenna A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Meacham, Joseph E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mendoza, Donaldo P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Olsen, Khris B. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Prinke, Amanda M. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Reid, Bruce D. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sevigny, Gary J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Sinkov, Sergey I. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Woods, Vincent T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2017-05-24

    This report details efforts to develop a technique which is able to detect and quantify the mass of 240Pu in waste storage tanks and other enclosed spaces. If the isotopic ratios of the plutonium contained in the enclosed space is also known, then this technique is capable of estimating the total mass of the plutonium without physical sample retrieval and radiochemical analysis of hazardous material. Results utilizing this technique are reported for a Hanford Site waste tank (TX-118) and a well-characterized plutonium sample in a laboratory environment.

  5. Studies of cesium and strontium migration in unconsolidated Canadian geological materials

    International Nuclear Information System (INIS)

    Gillham, R.W.; Lindsay, L.E.; Reynolds, W.D.; Kewen, T.J.; Cherry, J.A.; Reddy, M.R.

    1981-06-01

    Distribution coefficients (Ksub(d)) were measured for cesium and strontium in 16 samples of Canadian unconsolidated geological materials. The samples were collected to cover a wide range of grain size, clay-mineral composition, cation exchange capacity and carbonate mineral content. Distribution coefficients ranged between 10 2 and 2.0 x 10 4 ml/g for cesium and between 2.5 and 10 2 ml/g for strontium, indicating that most unconsolidated geological materials have a substantial ability to retard the migration of cesium, while strontium could generally be expected to be somewhat more mobile. The measured K values were not significantly correlated with the measured soil properties, but appeared to be significantly affected by the background concentration of stable isotopes of the respective radionuclides

  6. Radiochemical determination of strontium-90 and cesium-137 in waters of the Pacific Ocean and its neighboring seas

    International Nuclear Information System (INIS)

    Borisenko, G.S.; Kandinskii, P.A.; Gedeonov, L.I.; Ivanova, L.M.; Petrov, A.A.

    1987-01-01

    Depending on the salinity of the water, two versions of strontium-90 and cesium-137 concentration from water samples are presented. Cesium-137 was concentrated by precipitating sparingly soluble mixed hexacyanoferrates (II), and strontium-90 by precipitating carbonates together with calcium. A scheme has been given for radiochemical analysis of the concentrates. Strontium-90 and cesium-137 contents in the waters of the Pacific Ocean and its neighboring seas have been determined by the radiochemical method described. The levels of radionuclide content in the water and atmospheric precipitations have been shown to be inter-related. Strontium-90 and cesium-137 contents in the surface water of the northwestern Pacific were found to be much lower in 1980 than in the early seventies. The area of technogenic radioactive pollution was found to persist in the region of the Columbia mouth into the Pacific Ocean

  7. Study of isotopic exchange of radioactive calcium and cerium cations with y zeolites in aqueous and alcoholic solution

    Energy Technology Data Exchange (ETDEWEB)

    Guilloux, M

    1974-12-31

    Thesis. The isotopic exchange of y zeolite cations with calcium and cerium was studied. The experimental work was carried out utilizing the heterogeneous isotopic exchange between aqueous and alcoholic solutions of the cation considered and a zeolite powder containing a corresponding radioisotope. Aqueous phase exchanges demonstrate that a complex diffusion phenomenon is taking place which is capable of being decomposed into at least two distinct phases: a very slowly occurring phase representing 25 to 30% of the total exchange at ordinary temperatures and a very rapidly occurring phase. In alcoholic solutions, a rapid phase is always observed together with a slow diffusion phase although the exchange rates and diffusion coefficients may vary considerably with the nature and composition of the solvent. The results enable a hypothesis to be advanced on the ion exchange mechanism. The migration of the ions requires the crossing of two types of barrier: the large windows of the supercages (8A); the windows of the sodalite cages (2A). The two stages of the exchange kinetics can be related to these two types of barrier. (FR)

  8. Development of Innovative Radioactive Isotope Production Techniques at the Pennsylvania State University Radiation Science and Engineering Center

    Energy Technology Data Exchange (ETDEWEB)

    Johnsen, Amanda M. [Pennsylvania State Univ., State College, PA (United States). Radiation Science and Engineering Center; Heidrich, Brenden [Pennsylvania State Univ., State College, PA (United States). Radiation Science and Engineering Center; Durrant, Chad [Pennsylvania State Univ., State College, PA (United States). Department of mechanical and Nuclear Engineering Center; Bascom, Andrew [Pennsylvania State Univ., State College, PA (United States). Department of mechanical and Nuclear Engineering Center; Unlu, Kenan [Pennsylvania State Univ., State College, PA (United States). Radiation Science and Engineering Center

    2013-08-15

    The Penn State Breazeale Nuclear Reactor (PSBR) at the Radiation Science and Engineering Center (RSEC) has produced radioisotopes for research and commercial purposes since 1956. With the rebirth of the radiochemistry education and research program at the RSEC, the Center stands poised to produce a variety of radioisotopes for research and industrial work that is in line with the mission of the DOE Office of Science, Office of Nuclear Physics, Isotope Development and Production Research and Application Program. The RSEC received funding from the Office of Science in 2010 to improve production techniques and develop new capabilities. Under this program, we improved our existing techniques to provide four radioisotopes (Mn-56, Br-82, Na-24, and Ar-41) to researchers and industry in a safe and efficient manner. The RSEC is also working to develop new innovative techniques to provide isotopes in short supply to researchers and others in the scientific community, specifically Cu-64 and Cu-67. Improving our existing radioisotopes production techniques and investigating new and innovative methods are two of the main initiatives of the radiochemistry research program at the RSEC.

  9. Strontium-90 and cesium-137 in freshwater (from Sept. 1983 to Dec. 1983)

    International Nuclear Information System (INIS)

    1983-01-01

    Fresh water, 100 l each, was collected, and to which the carriers of strontium and cesium were added immediately after the sampling. The sample was vigorously stirred and filtered, and passed through a cation exchange column. Strontium and cesium were eluted with hydrochloric acid from the cation exchange column. The eluate was used for radiochemical analysis. The chemical separation of strontium-90 and cesium-137 was carried out, and the chemical yields were determined. The precipitates were counted for the activity using low background beta counters normally for 60 min. The net sample counting rate was corrected for the counter efficiency, recovery, self-absorption and decay, to obtain the radioactivity per sample aliquot, and the concentrations of these nuclides in the original samples were calculated. The data at six sampling locations in Japan from September to December, 1983, on fresh water are reported. (Kako, I.)

  10. Use of cesium-137 to assess soil erosion rates under soybean, coffee and pasture

    International Nuclear Information System (INIS)

    Andrello, A.C.; Appoloni, C.R.; Guimaraes, M.F.

    2003-01-01

    The methodology cesium-137 was used to assess soil erosion and deposition rates in a small watershed with varied crops, at 23 deg 16' S and 51 deg 17' W, in a district of Cambe, Parana State, Brazil. A theoretical equation which considers soil loss or gain directly proportional to the cesium-137 redistribution was utilized in this study. In the watershed, soil redistribution was assessed by transect sampling, and the regional input of cesium-137 by radioactive rainfall determined based on samples from a point in the native forest. Most sampled pasture points presented soil loss, as well as the points in the soybean area under conventional tillage, while in the coffee crop there was neither soil loss nor gain. (author)

  11. Physical Property Modeling of Concentrated Cesium Eluate Solutions, Part I - Derivation of Models

    Energy Technology Data Exchange (ETDEWEB)

    Choi, A.S.; Pierce, R. A.; Edwards, T. B.; Calloway, T. B.

    2005-09-15

    Major analytes projected to be present in the Hanford Waste Treatment Plant cesium ion-exchange eluate solutions were identified from the available analytical data collected during radioactive bench-scale runs, and a test matrix of cesium eluate solutions was designed within the bounding concentrations of those analytes. A computer model simulating the semi-batch evaporation of cesium eluate solutions was run in conjunction with a multi-electrolyte aqueous system database to calculate the physical properties of each test matrix solution concentrated to the target endpoints of 80% and 100% saturation. The calculated physical properties were analyzed statistically and fitted into mathematical expressions for the bulk solubility, density, viscosity, heat capacity and volume reduction factor as a function of temperature and concentration of each major analyte in the eluate feed. The R{sup 2} of the resulting physical property models ranged from 0.89 to 0.99.

  12. Determination of the cesium distribution coeficient in Goiania and Abadia de Goias cities soils

    International Nuclear Information System (INIS)

    Marumo, J.T.; Suarez, A.A.

    1989-01-01

    In September, 1987, an unauthorized removal of a cesium-therapy unit and its violation caused an accident, where several places of Goiania's city, capital of Goias, Brazil, were contaminated. The removal of the radioactive wastes generated from decontamination process, was made to Abadia de Goias's city (near Goiania), where an interim storage was constructed. Soil samples collected from the 57 th Street (Goiania) and from the interim storage permitted to determine, through static method, the cesium distribution coefficient for different cesium solution concentrations. Those results allows for some migration/retention evaluations in disposal site selection. Some soils parameters (water content, density, granulometric analysis etc) as well as clay minerals constituents were also determined. (author) [pt

  13. Determination of the cesium distribution coefficient in Goiania and Abadia de Goias cities soils

    International Nuclear Information System (INIS)

    Marumo, J.T.; Suarez, A.A.

    1989-10-01

    In September, 1987, an unauthorized removal of a cesium-therapy unit and its violation caused an accident, where several places of Goiania's city, capital of Goias, Brazil, were contaminated. The removal of the radioactive wastes generated from decontamination process, was made to Abadia de Goias city (near Goiania), where an interim storage was constructed. Soil samples collected from the 57 th Street (Goiania) and from the interim storage permitted to determine, through static method, the cesium distribution coefficent for different cesium solution concentrations. Those results allows for some migration/retention evaluations in disposal site selection. Some soils parameters (water content, density, granulometric analysis etc) as well as clay minerals constituents were also determined. (author) [pt

  14. Sorption of iodine, chlorine, technetium and cesium in soil

    International Nuclear Information System (INIS)

    Soederlund, M.; Lusa, M.; Lehto, J.; Hakanen, M.; Vaaramaa, K.

    2011-01-01

    The safety assessment of final disposal of spent nuclear fuel will include an estimate for the behavior of waste nuclides in the biosphere. As a part of this estimate also the sorption of radioactive iodine, chlorine, technetium and cesium in soil is to be considered. The chemistry and the sorption of these radionuclides in soils are described in this literature survey. Behavior of I-129, Cl-36 and Tc-99 in the environment is of great interest because of their long half-lives and relatively high mobilities. The importance of Cs-135 arises from its high content in spent nuclear fuel and long physical half-life, even though it is considered relatively immobile in soil. Factors affecting the migration and sorption of radionuclides in soils can be divided into elemental and soil specific parameters. The most important elemental factor is the speciation of the element, which is influenced by the soil redox potential, pH and complex forming ligands. Soil micro-organisms can either serve as sorbents for radionuclides or affect their speciation by altering the prevailing soil redox conditions. Soil organic matter content and mineral properties have a marked influence on the retention of radionuclides. The sorption of anionic radionuclides such as I-, Cl- and TcO 4 - is pronounced in the presence of organic matter. Clay minerals are known to bound cesium effectively. The effect of speciation of radioactive iodine, chlorine, technetium and cesium in soil is considered in this study, as well as the effect of soil micro-organisms, organic matter and mineral properties. (orig.)

  15. Cesium-134 and strontium-85 turnover rates in the centipede Scolopocryptops nigridia McNeill

    International Nuclear Information System (INIS)

    Yates, L.R.; Crossley, D.A. Jr.

    1979-07-01

    Radioactive tracers are providing significant information about the ecology of food chains, including such phenomena as accumulation of radioactive fission products, movement of materials along food chains, assimilation and ingestion rates, and nutrient accumulation and turnover. In this study the ingestion, assimilation and turnover to two radioactive tracers were investigated for Scolopocryptops nigridia, an abundant species in forests of the southeastern United States. The two tracers utilized, cesium-134 and strontium-85, are metabolic analogs of potassium and calcium, respectively. The research was performed as part of a larger investigation on the population ecology of the centipede species, emphasizing its relations to nutrient cycling and energy flow in a forest floor system

  16. Dose control programme of Hot Cell facility at Isotope Wing

    International Nuclear Information System (INIS)

    Sapkal, Jyotsna A.; Suresh, Manju; Shreenivas, V.; Amruta, C.T.; Yadav, R.K.B.; Gopalkrishanan, R.K.; Patil, B.N.; Sastry, K.V.S.

    2015-01-01

    Hot Cell Facility of Board of Radiation Isotope Technology (BRIT) at Radiological Laboratories (RLG) is involved in fabrication of sealed radioisotopes like Cobalt-60, Cesium-137 and Iridium-192 radioisotopes which are widely used for various medical and industrial applications. In the field of Medicine, above radioactive sources are used for treatment procedures such as Teletherapy and Brachytherapy. 192 Ir radioisotope is widely used for industrial radiography particularly for non-destructive testing of welds in steel in the oil and gas industries. In spite of the increased production of these radioisotopes to meet the requirements from medical and industrial sector, the annual Collective Dose for BRIT facility, during 2011-2013 has shown a downward trend. This paper describes in brief the measures adopted by the facility based on the radiological safety inputs provided by Radiation Hazards Control (RHC) Unit of Isotope Wing, RLG for reducing the collective dose during year 2012 and 2013 by nearly 40% of collective dose consumed for year-2011. Strict implementation of the radiological safety measures during handling of radioactive sources, administrative controls and engineered safety measures resulted in lowering of collective dose during year 2011-2013. (author)

  17. Atmospheric plume progression as a function of time and distance from the release point for radioactive isotopes.

    Science.gov (United States)

    Eslinger, Paul W; Bowyer, Ted W; Cameron, Ian M; Hayes, James C; Miley, Harry S

    2015-10-01

    The radionuclide network of the International Monitoring System comprises up to 80 stations around the world that have aerosol and xenon monitoring systems designed to detect releases of radioactive materials to the atmosphere from nuclear explosions. A rule of thumb description of plume concentration and duration versus time and distance from the release point is useful when designing and deploying new sample collection systems. This paper uses plume development from atmospheric transport modeling to provide a power-law rule describing atmospheric dilution factors as a function of distance from the release point. Consider the plume center-line concentration seen by a ground-level sampler as a function of time based on a short-duration ground-level release of a nondepositing radioactive tracer. The concentration C (Bq m(-3)) near the ground varies with distance from the source with the relationship C=R×A(D,C) ×e (-λ(-1.552+0.0405×D)) × 5.37×10(-8) × D(-2.35) where R is the release magnitude (Bq), D is the separation distance (km) from the ground level release to the measurement location, λ is the decay constant (h(-1)) for the radionuclide of interest and AD,C is an attenuation factor that depends on the length of the sample collection period. This relationship is based on the median concentration for 10 release locations with different geographic characteristics and 365 days of releases at each location, and it has an R(2) of 0.99 for 32 distances from 100 to 3000 km. In addition, 90 percent of the modeled plumes fall within approximately one order of magnitude of this curve for all distances. Copyright © 2015 Elsevier Ltd. All rights reserved.

  18. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    International Nuclear Information System (INIS)

    P. Bernot

    2005-01-01

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO 2 as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with 231 Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or otherwise

  19. DISSOLVED CONCENTRATION LIMITS OF RADIOACTIVE ELEMENTS

    Energy Technology Data Exchange (ETDEWEB)

    P. Bernot

    2005-07-13

    The purpose of this study is to evaluate dissolved concentration limits (also referred to as solubility limits) of elements with radioactive isotopes under probable repository conditions, based on geochemical modeling calculations using geochemical modeling tools, thermodynamic databases, field measurements, and laboratory experiments. The scope of this activity is to predict dissolved concentrations or solubility limits for elements with radioactive isotopes (actinium, americium, carbon, cesium, iodine, lead, neptunium, plutonium, protactinium, radium, strontium, technetium, thorium, and uranium) relevant to calculated dose. Model outputs for uranium, plutonium, neptunium, thorium, americium, and protactinium are provided in the form of tabulated functions with pH and log fCO{sub 2} as independent variables, plus one or more uncertainty terms. The solubility limits for the remaining elements are either in the form of distributions or single values. Even though selection of an appropriate set of radionuclides documented in Radionuclide Screening (BSC 2002 [DIRS 160059]) includes actinium, transport of Ac is not modeled in the total system performance assessment for the license application (TSPA-LA) model because of its extremely short half-life. Actinium dose is calculated in the TSPA-LA by assuming secular equilibrium with {sup 231}Pa (Section 6.10); therefore, Ac is not analyzed in this report. The output data from this report are fundamental inputs for TSPA-LA used to determine the estimated release of these elements from waste packages and the engineered barrier system. Consistent modeling approaches and environmental conditions were used to develop solubility models for the actinides discussed in this report. These models cover broad ranges of environmental conditions so they are applicable to both waste packages and the invert. Uncertainties from thermodynamic data, water chemistry, temperature variation, and activity coefficients have been quantified or

  20. Thermal decomposition of woody wastes contaminated with radioactive materials using externally-heated horizontal kiln

    International Nuclear Information System (INIS)

    Iwasaki, Toshiyuki; Kato, Shigeru; Yamasaki, Akihiro; Ito, Takuya; Suzuki, Seiichi; Kojima, Toshinori; Kodera, Yoichi; Hatta, Akimichi; Kikuzato, Masahiro

    2015-01-01

    Thermal decomposition experiments of woody wastes contaminated with radioactive materials were conducted using an externally-heated horizontal kiln in the work area for segregation of disaster wastes at Hirono Town, Futaba County, Fukushima Prefecture. Radioactivity was not detected in gaseous products of thermal decomposition at 923 K and 1123 K after passage through a trap filled with activated carbon. The contents of radioactive cesium ( 134 Cs and 137 Cs) were measured in the solid and liquid products of the thermal decomposition experiments and in the residues in the kiln after all of the experiments. Although a trace amount of radioactive cesium was found in the washing trap during the start-up period of operation at 923 K, most of the cesium remained in the char, including the residues in the kiln. These results suggest that most of the radioactive cesium is trapped in char particles and is not emitted in gaseous form. (author)