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Sample records for cs sr actinides

  1. Sorption of Cs, I, and actinides in concrete systems

    International Nuclear Information System (INIS)

    Allard, B.; Eliasson, L.; Andersson, K.

    1984-09-01

    Samples of seven different concretes were prepared (Standard Portland cement of two kinds; sulphate resistant, blast furnace slag, high alumina, fly ash, and silica cements) and the corresponding pore waters were analyzed. Batch-wise distribution studies were performed in the various concrete/pore water systems, as well as for three old concrete samples from a hydro power station dam (more than 60 years old), for the elements Cs, I, Th, U, Np, Pu, and Am at trace concentration levels. Generally the sorption of Cs was low, and somewhat higher for I. All the actinides, including U and Np in their hexa- and pentavalent states, respectively, were strongly sorbed on the cement phase. (Author)

  2. SR-XRF imaging of Cs highly accumulated in vegetables

    International Nuclear Information System (INIS)

    Nakai, Izumi; Oda, Nahoko; Terada, Yasuko

    2011-01-01

    Accumulation of Cs in vegetables was studied with regard to the remediation of radioactive Cs from a nuclear plant accident in Fukushima. It was found that Brassica oleracea var. capitata, Brassica campestris var. perviridis, and Lactuca sativa accumulated Cs to a level of more than 10000 ppm (dry weight) when they were cultivated in 1 mM Cs solution. Two-dimensional distributions of Cs were revealed by SR-XRF imaging showing a homogeneous distribution of Cs in the plant bodies. (author)

  3. Cs-137 and Sr-90 level in diary products

    International Nuclear Information System (INIS)

    Petukhov, V.L.; Dukhanov, Y.A.; Sevryuk, I.Z.; Patrashkov, S.A.; Korotkevich, O.S.; Gorb, T.S.; Petukhov, I.V.

    2003-01-01

    About 70% of radioactive substances fell on the territory of the Byelorussian Republic after the Chernobyl Atom Power Station Disaster. Cs-137 and Sr-90 accumulation dynamics was studied in milk of the cows from the highest polluted Braginsky area. 408 milk samples of Black and White cows were investigated. In 1995 average Cs-137 and Sr-90 levels were 61.00 and 3.73 Bk/dm 3 respectively. Cs-137 and Sr-90 levels exceeded Byelorussian Republic upper limits RDU - 96 in 10 and 50% of milk samples respectively. After 5 years (by 2000) Cs-137 and Sr-90 levels had become almost 3 and 2 times less (21.70 Bk/dm 3 and 1.72 Bk/dm 3 respectively). Cs-137 and Sr-90 levels exceeded RDU - 96 in 1.5 and 5.5% of milk samples respectively. In the same periods Cs-137 and Sr-90 levels were 7 and 2 times higher than the similar indexes in the relatively clean Novosibirsk area. Thus, radioactive element levels in milk of Black and White cows of the Byelorussian Republic decreased significantly for the past years. (authors)

  4. Structural study of caesium-based britholites Sr7La2Cs(PO4)5(SiO4)F2

    International Nuclear Information System (INIS)

    Boughzala, K.; Gmati, N.; Bouzouita, K.; Ben Cherifa, A.; Gravereau, P.

    2010-01-01

    Several studies demonstrated the ability of britholites to retain radionuclides such as the caesium and actinides. Therefore, three compounds with formulas Sr 8 LaCs(PO 4 ) 6 F 2 , Sr 7 La 2 Cs(PO 4 ) 5 (SiO 4 )F 2 and Sr 2 La 7 Cs(SiO 4 ) 6 F 2 , were prepared by solid state reaction. However, it seems that only the mono-silicated composition was obtained in a pure state. In this present work, the X-ray diffraction and magnetic nuclear resonance have been used to investigate the structure for this composition. The results showed that in fact this phase was not pure, but it was mixed with a secondary phase, SrLaCs(PO 4 ) 2 . The refinement by the Rietveld method allowed also to precise the distribution of La 3+ and Cs + ions between the two cationic sites of the apatite. (authors)

  5. Experimental probe into adsorption of Sr, Cs in the Soil

    International Nuclear Information System (INIS)

    Yuan Guangyu; Bai Qingzhong

    1987-12-01

    There are some obstacles in researching on the adsorption patterns of Sr and Cs in soil. One of them is that it is difficult to compare and to consult between various results and data for different types and sizes of soil. For this reason, it is neccesary to do further research into adsorption patterns of Sr and Cs in single particles of soil. By using scanning electromicroscope, the microcosmic phenomena of nuclides adsorption is observed, and a possible mechanism is proposed. A certain amount of diluvial soil from Shanxi Province and a certain amount of alluvial soil from western Beijing suburban were chosen as detected samples. After determining the distributions of adsorbed Sr and Cs in varied mineral particles, it is pointed out that the defference of chemical components of various size soils effects Kd value of Sr and Cs obviously. The method for calculating Kd value of mixing samples according to the particle distribution coefficients are derived under the condition of surface adsorption as main. The authors expound that it is favourable for accuracy to select and control the particle sizes in static adsorptional experiment

  6. Radioactivity precipitation Sr-90 and Cs-137 in Plock

    International Nuclear Information System (INIS)

    Flakiewicz, W.; Majkowska, I.; Bonkowski, J.

    1986-01-01

    Methods of research and results for beta-activity measurements of precipitation in 1977-1983 with regard to Sr-90, Cs-137 - are presented. Climatic changes caused by big industrial plant, conditions of pollution propagation in atmosphere, parameters of pollution load of Plock region are described. 11 refs., 6 figs., 5 tabs. (author)

  7. 90Sr and 137Cs content in fishes

    International Nuclear Information System (INIS)

    Patin, S.A.; Petrov, A.A.

    1978-01-01

    Numerous data are presented and discussed on concentrations of 90 Sr in bones and 137 Cs in muscular tissues of main food fishes fished out in different regions of the ocean, seas, lakes and rivers. They are indicative of the absence of appreciable hygienic hazards for man from eating food fishes

  8. Determination of Sr-90 and Cs-137 in environmental samples

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    The comparison between the Ca concentration in the soil and the transfer factors involved indicates a clear dependence of Sr-90 soil-to-plant transport from the soil's Ca-content with the concentration level of 0.1 g Ca/kg soil appearing to be the limit level. Soil concentrations of Cs-137 determined to-date indicate a very even deposition density of Cs-137. The transfer factors of plant/soil in Chile differ but negligeably from those in Europe. (DG) [de

  9. Determination of Cs-137, Sr-89 and Sr-90 and gamma spectroscopy of water samples from the Danube River

    International Nuclear Information System (INIS)

    Tschurlovits, M.

    1980-01-01

    Radioactivity concentration of Cs-137, Sr-90, Sr-89, Co-60 and K-40 from the Danube water in the period of 1977-1979. A few systematic changes in the radioactivity concentrations were observed and presented. (author)

  10. Uptake and activity concentration of 137Cs and 90Sr in Salix viminalis

    International Nuclear Information System (INIS)

    Rosen, K.; Fircks, Y. von; Sennerby-Forsse, L.

    1999-01-01

    In order to gain a better understanding of the uptake, internal distribution of 137 Cs and 90 Sr and the effects of K-fertilisation of uptake of 137 Cs in Salix plantations, a K-fertilisation experiment including 137 Cs, 90 Sr and 40 K was performed. Previous studies with K-fertilization in Sweden have mainly dealt with the flow of 137 Cs between soil to plant in annual crops. The aim of this study was study the transfer of 137 Cs, 90 Sr and 40 K from soil to plants and to test the following hypothesis: that accumulation of 137 Cs and 90 Sr differs between plant organs, that there is a seasonal variation in uptake and concentration of 137 Cs and 90 Sr and that the availability of K is related to the uptake of 137 Cs. (au)

  11. Rapid method to determine actinides and 89/90Sr in limestone and marble samples

    International Nuclear Information System (INIS)

    Maxwell, S.L.; Culligan, Brian; Hutchison, J.B.; Utsey, R.C.; Sudowe, Ralf; McAlister, D.R.

    2016-01-01

    A new method for the determination of actinides and radiostrontium in limestone and marble samples has been developed that utilizes a rapid sodium hydroxide fusion to digest the sample. Following rapid pre-concentration steps to remove sample matrix interferences, the actinides and 89 / 90 Sr are separated using extraction chromatographic resins and measured radiometrically. The advantages of sodium hydroxide fusion versus other fusion techniques will be discussed. This approach has a sample preparation time for limestone and marble samples of <4 h. (author)

  12. The adsorption of Sr(II) and Cs(I) ions by irradiated Saccharomyces cerevisiae

    International Nuclear Information System (INIS)

    Yiming Tan; Jundong Feng; Liang Qiu; Zhentian Zhao; Xiaohong Zhang; Haiqian Zhang

    2017-01-01

    Adsorption behavior and mechanism of Sr(II) and Cs(I) in single and binary solutions using irradiated Saccharomyces cerevisiae was investigated. The effects of several environmental factors on Sr(II) and Cs(I) adsorption to irradiated Saccharomyces cerevisiae was determined. The equilibrium experimental data were simulated by different kinetic models and isotherm models. The combined effect of Sr(II) and Cs(I) on Saccharomyces cerevisiae is generally antagonistic. SEM and EDS analyses indicate that crystals formed on the cell surface are precipitate of Sr(II) and Cs(I), respectively. (author)

  13. 90Sr and 137Cs determination in milk and foodstuff samples in North and Middle Moravia

    International Nuclear Information System (INIS)

    Bartuskova, M.; Lusnak, J.; Rada, J.; Beckova, V.

    2008-01-01

    Activities of radionuclides Sr-90 and Cs-137 in milk and parts of foodstuff have been determined in National Radiation Protection Institute for many years. Sr-90 activity in those samples determinate branch Ostrava by radiochemical procedure - precipitation with oxalic acid and measuring with using gas-flow proportional detector. Gamma spectrometry with HPGe detector is using for 137 Cs determination. (authors)

  14. The characteristics of intake Cs-137 and Sr-90 with food by Ozersk's inhabitants

    International Nuclear Information System (INIS)

    Dronova, M.

    2000-01-01

    This work is based on a questionnaire of production plant 'MAYAK' workers eating habits. Cs-137 and Sr-90 were chosen as experimental radionuclides. Cs-137 is distributed in organisms equally. It is considered to be a source of genetic damage after entry into the human body. This radionuclide is almost completely absorbed as it passes into the bowels after peroral entry. In the blood Cs-137 is distributed almost evenly between organs and tissues. It was established that Cs-137 accumulates in muscle, kidney, heart, spleen, lungs, and liver to a higher degree. Although the half-life of Cs-137 exceeds Sr-90, Cs-137 leaves the body more rapidly. The radiation dose of Cs-137 per unit of intake is less than for Sr-90. In addition, Cs-137 is absorbed by plants to a lesser degree than Sr-90. Taking into account that a considerable part of the daily diet consists of vegetables, it should be noted that different radionuclides get into plants in different amounts and different ways. Cs-137 concentrates in cereal, beans, oil plants, potatoes. beets and tomatoes. Meat and milk are also a main source of Cs-137 in a person's diet. Sr-90 contributes to radiation dose for bone and marrow, almost all Sr-90 is taken up by organisms through milk, greens, and cereal. (authors)

  15. The selective separation of Cs and Sr ion on the inorganic ion-exchanger zeolites

    Energy Technology Data Exchange (ETDEWEB)

    Park, Hun Hwee; Min, Byeog Heon [Hoseo University, Taegu (Korea)

    1998-04-01

    This study shows the selective separation of Cs and Sr ion on the inorganic ion-exchanger zeolites such as clinoptilolite, Y-type CBV760, CBV780 and A-type 3A. The selective separation of Cs and Sr on these zeolites was examined using batch and continuous column experiments. For the selective separation of Cs and Sr from a synthetic wastewater, adsorption rate of Cs increased in the order, clinoptilolite> 3A>> CBV760> CBV780, adsorption rate of Sr increased in the other, 3A>> clinoptilolite> CBV760> CBV780. For the clinoptilolite, the adsorption rate of Cs reached about 96 {approx} 98% within 3h. The adsorption rate of Sr on 3A reached about 99% within 3h. (author). 40 refs., 27 figs., 4 tabs.

  16. Actinides

    International Nuclear Information System (INIS)

    Martinot, L.; Fuger, J.

    1985-01-01

    The oxidation behavior of the actinides is explained on the basis of their electronic structure. The actinide elements, actinium, thorium, protactinium, uranium, neptunium, plutonium, americium, curium, berkelium, californium, einsteinium, fermium, mendelevium, nobelium, and laurencium are included. For all except the last three elements, the points of discussion are oxidation states, Gibbs energies and potentials, and potential diagram for the element in acid solution; and thermodynamic properties of these same elements are tabulated. References are cited following discussion of each element with a total of 97 references being cited. 13 tables

  17. SPECIFICITY OF ACCUMULATION OF VARIOUS RADIONUCLIDES (137Cs и 90Sr IN SPINACH (Spinacia oleracea L.

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    A. V. Soldatenko

    2016-01-01

    Full Text Available Knowledge of the specificity of accumulation of 137Cs and 90Sr by plants and limits of accumulation by plant fruits plays a key role at breeding of vegetable crops, which make demand for ecological safety of the product. The article is concerned with the study of varietal sources of spinach (Spinacia oleracea L. aimed at development of ecological safety product on the territory polluted by radionuclides.The specificity of accumulation of radionuclides 137Cs and 90Sr was studied in 54 varieties of spinach at industrial contaminated and polluted lands. Experimental tests were conducted in the Moscow and Bryansk regions in 2012 and 2014. The absolute value of radionuclide 90Sr was higher than absolute value of radionuclide 137Cs in all studied zones. It was found that the hazard rate of 90Sr is higher because the level of pollution of product reaches up to 76% from maximum permissible concentration (MPC, while the level of product pollution by 137Cs is 26,4% from MPC. The spinach genotype differentiation for 90Sr in the most environments is lower than differentiation for 137Cs. The histograms of distribution 90Sr and 137Cs showed that samples amount in the groups of accumulation for both radionuclides are equal. Statistically significant data for radionuclides 137Cs and 90Sr in spinach were not obtained. The evaluation of spinach for low content of radionuclides should be conducted separately for each radionuclide on various backgrounds.

  18. Sorption behaviour of Cs, Sr radionuclides in the presence of various anions and surfactants in solutions

    International Nuclear Information System (INIS)

    Davydov, Yu.P.; Toropov, I.G.; Vasilevskaya, T.V.

    1997-01-01

    The state of 137 Cs and 90 Sr radionuclides was studied in solutions of different compositions to develop appropriate methodology and technology for treatment of spent decontamination solutions. Complex physico-chemical methods were used for this study. Particular attention was paid to the sorption of 137 Cs and 90 Sr on different natural and synthetic inorganic sorbents, as the most specific and selective sorbents for separation of these radionuclides from different solutions. Sorption of CS and Sr on different fractions of soil was also studied in connection with development of rehabilitation methods for contaminated territories. (author). 2 refs, 20 tabs

  19. On 99Tc, 137Cs and 90Sr in the Kara Sea

    International Nuclear Information System (INIS)

    Dahlgaard, H.

    1995-01-01

    Technetium-99 in the Arctic seas originate mainly from European reprocessing plants whereas 137 Cs and 90 Sr have many sources. It appears that for 137 Cs, re-mobilisation from the Irish Sea of sedimented activity from earlier discharges and the outflow of Baltic water contaminated with Chernobyl activity, are more important sources to the present contamination of the Kara Sea than new European discharges. As opposed to 137 Cs and 99 Tc, 90 Sr is correlated with low salinity waters. It is argued, that this is due to runoff of global atmospheric fallout 90 Sr from land. 7 refs., 4 figs., 1 tab

  20. Uptake and distributions of 90Sr and 137Cs in rice plants

    International Nuclear Information System (INIS)

    Tsukada, Hirofumi; Takeda, Akira; Hasegawa, Hidenao

    2008-01-01

    Polished rice is a staple food in Asian countries and ingestion of polished rice is one of the most important pathways of radionuclides into humans. Inedible parts of rice plants are returned to the soil as fertilizer and are used as an ingredient of feed for livestock. Strontium-90 and 137 Cs are important radionuclides for the assessment of radiation exposure to the public because of their high fission yield, long-half lives and transferability in the environment. The purpose of the present study is to obtain information on the distributions of 90 Sr and 137 Cs in rice plant components for better understanding of the fate of the radionuclides in an agricultural environment. Rice plants were cultivated in an experimental field and collected at harvest time. The concentrations of 90 Sr and 137 Cs in the soil were 5.6 and 4.4 Bq kg -1 , respectively. Rice plant samples were separated into polished rice, rice bran, hull, straw and root parts, and then the concentrations of 90 Sr and 137 Cs in the samples were determined. The concentrations of 90 Sr and 137 Cs in polished rice were 0.012 and 0.0048 Bq kg -1 dry weight, respectively. The concentrations of 90 Sr and 137 Cs varied by two and one orders of magnitudes in rice plant components, respectively. The edible component, polished rice, accounted for 32% of the total dry weight. In the entire rice plants, only 0.5% of the total 90 Sr and 10% of the total 137 Cs were found in polished rice. Contents of 90 Sr and 137 Cs in the above ground parts were 0.84 and 0.021 Bq m -2 , respectively. For each cropping, the percentages of 90 Sr and 137 Cs uptake from the upper soil layer to the aboveground biomass of rice plants were calculated as 0.094 and 0.0030% of their soil inventories, respectively. (author)

  1. Luminescence properties of undoped CsCaCl3 and CsSrCl3 crystalline scintillators

    International Nuclear Information System (INIS)

    Fujimoto, Yutaka; Saeki, Keiichiro; Koshimizu, Masanori; Asai, Keisuke; Yanagida, Takayuki

    2015-01-01

    Intrinsic luminescence properties of undoped CsCaCl 3 and CsSrCl 3 crystalline scintillators were studied. The crystal samples were grown by a vertical Bridgman method. Photoluminescence spectra of the crystals showed Auger-free luminescence (AFL) at 310 nm and self-trapped emission (STE) at 400 nm for CsCaCl 3 and 465 nm for CsSrCl 3 , when vacuum ultraviolet (VUV) light at 84 nm and 160 nm excited the crystals. X-ray excited radioluminescence spectra of the crystals showed some emission bands in the 280-600 nm wavelength range, which are owing to AFL, STE, and other origins such as lattice defects and impurities. Scintillation light yield was 400-300 ph/MeV, and the principal scintillation decay time about 2.5 ns and 12 ns for CsCaCl 3 and 1.8 ns and 13 ns for CsSrCl 3 . (author)

  2. The review of separation technology for fission nuclides 90Sr and 137Cs

    International Nuclear Information System (INIS)

    Zhang Huaming; Li Xingliang; Luo Shunzhong; Peng Shuming; Lei Jiarong

    2010-01-01

    The progress of separation technologies for fission nuclides 90 Sr and 137 Cs, including precipitation method, liquid-liquid extraction process and ion exchanging operation, are mainly reviewed. Crown ether (DtBuCH18C6) and calixarene-crown ether (BOBCalixC6) can be highly selective for 90 Sr and 137 Cs respectively in acidic waste; Ionic liquids extraction and supercritical fluid extraction can be applied for separation 90 Sr and 137 Cs from high level waste. Crystalline silicotitiate (CST) and metal sulfide (KMS-1) have highly selectivity for 90 Sr and 137 Cs separately in basic condition. The prospects of disposal technology for high level waste are also discussed in this review. (authors)

  3. Accumulation of 90Sr and 137Cs by fruit bodies of mushrooms

    International Nuclear Information System (INIS)

    Kozhevnikova, T.L.; Mishenkov, N.N.; Martyushova, L.N.; Krivolutskii, D.A.

    1994-01-01

    The dimensions of accumulation of 90 Sr and 137 Cs by mushrooms depends on the stores of forest litter: The greater they are, the higher the concentration. As the nuclides migrate from the forest litter, the dimensions of their accumulation decrease: In the tenth year of the investigation the concentration of 90 Sr in mushrooms had diminished by 1.5-3 times; and 137 Cs, by as much as 30 times. The fruit bodies of mushrooms accumulate 2.5-5 times more 137 Cs, and in individual cases up to 40 times more, than 90 Sr. The maximum amount of 90 Sr and 137 Cs is accumulated by annulated boletus; the minimum amount, by rough boletus

  4. Parameters of Cs 137 and Sr 90 transition from soil into salad crops

    International Nuclear Information System (INIS)

    Lazarevich, T.M.; Barashenko, V.V.

    2010-01-01

    Transition coefficients of Cs 137 and Sr 90 from soil into plants for potherb of bulb onion (Allium cepa), parsley (Petroselinum crispum), dill (Anethum graveolens), celery (Apium graveolens) and coriander (Coriandrum sativum) have been defined. (authors)

  5. Intercomparison of methods for determining 90Sr and 137Cs in plant samples

    International Nuclear Information System (INIS)

    Sha Lianmao; Zhao Min; Tian Guizhi

    1986-01-01

    The results of intercomparison of methods for determining 90 Sr and 137 Cs in plant samples are reported. Nine laboratories participated in the intercomparison. The samples used in intercomparison were reed and tea powders. The analytical results of 90 Sr in reed and 137 Cs in tea from different laboratories show good comparability and follow the normal-distribution. Some results reported of 137 Cs in reed are apparently lower than others. The results of 90 Sr in tea from different laboratories have poor comparability. The results obtained by HDEHP rapid extraction chromatograph appear to be too high, and it's cause is discussed. The 95% confidence intervals of content of 90 Sr and 137 Cs in reed and tea samples are given

  6. Coprecipitation of 137Cs and 85Sr microquantities with complex compound [M(18-crown-6)]BPH4 (M=Na+, Cs+) from neutral and alkaline solutions

    International Nuclear Information System (INIS)

    Konovalova, N.A.; Rumer, I.A.; Kulyukhin, S.A.

    2009-01-01

    The paper reports the possibility of joint separation of 137 Cs and 85 Sr from neutral and alkaline aqueous solutions by their coprecipitation with the solid phase of complex compounds [M(18-crown-6)]BPh 4 (M=Na + , Cs + ), as well as to study the coprecipitation of 137 Cs and 85 Sr with the solid phase CsBPh 4 . It is found that complex compounds [M(18-crown-6)]BPh 4 (M=Na + , Cs + ) increased the degree of 85 Sr separation from solutions virtually two- to threefold vs. CsBPh 4 . Chloride and nitrate were found to have hardly any impact on the coprecipitation of 137 Cs and 85 Sr with [M(18-crown-6)]BPh 4 (M = Na + , Cs + ). (orig.)

  7. Contents of 90Sr, 137Cs and 144Ce in tea

    International Nuclear Information System (INIS)

    Sha Lianmao; Qiu Yundian; Wang Zhihui; Wang Fenghua

    1996-01-01

    The determination results of 90 Sr, 137 Cs and 144 Ce contents in 18 kinds of tea goods are reported. The tea samples were pretreated by ashing and analyzed by combined radiochemical procedure. the results showed the average contents of 90 Sr, 137 Cs and 144 Ce in tea goods available in 1985 are 17, 2.2 and 0.8 Bq/kg respectively

  8. Sorption kinetics of Cs and Sr in sediments of a Savannah River Site reservoir

    International Nuclear Information System (INIS)

    Stephens, J.A.

    1997-07-01

    Laboratory measurements of the sorption and desorption of 134 Cs and 85 Sr to sediments were conducted. These sediments were sampled from the profundal zone of Par Pond at the Savannah River Site, Aiken, South Carolina. The isotopes 134 Cs and 85 Sr were used to trace the sorption properties of the main contaminants found in the reservoir which are 137 Cs and 90 Sr respectively. The sorption behavior of these two elements was studied using spiked sediment/water slurries of a known mass to volume ratio. The results reveal that Sr undergoes significant reversible sorption while a fraction of Cs irreversibly sorbs to the sediment. The calculated distribution coefficient Kd at equilibrium was (3 ± 0.6) x 10 3 for 134 Cs after 60 d and (1 ± 0.2) x 10 3 for 85 Sr after 7 d at pH ∼ 6 and slurry ratio of 1:1000 g/ml. The K d for 134 Cs ranged from 2 x 10 2 to 3 x 10 4 depending on pH and conductivity. The 85 Sr reached equilibrium in a few days, while 134 Cs reached an apparent equilibrium in 1--2 months. The K d for 134 Cs was a function of the slurry ratio, pH, conductivity, and contact time. These factors were interrelated since the sediments released ions to the slurry mixture which decreased the pH and increased the conductivity. A sorption isotherm measured for 134 Cs was linear at water concentrations from 60 mBq/ml to 20 Bq/ml. A kinetic model was proposed to describe the basic sorption of 134 Cs to Par Pond sediments under homogeneous laboratory conditions

  9. Cs+ and Sr2+ adsorption selectivity of zeolites in relation to radioactive decontamination

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    M.W. Munthali

    2015-09-01

    Full Text Available Zeolites are used as adsorbents of cationic elements in the radioactive decontamination process of water, soil and others. We determined Cs+ and Sr2+ adsorption selectivity of some zeolites to know effective zeolite species for the decontamination of radioactive Cs and Sr. A 30 mL mixed solution containing up to 15 mg L−1 of non-radioactive Cs+ or Sr+ and up to 0.50 M of Na+ or K+ was mixed with 0.5 g of Linde-type A, Na-P1, faujasite X, faujasite Y and mordenite. Among the zeolites, mordenite had the highest Cs+ adsorption selectivity, and the selectivity had no correlation to the cation exchange capacity (CEC of the zeolites. In contrast, Sr2+ adsorption selectivity of the zeolites positively correlated with the CEC of the zeolites; Linde-type A with the highest CEC showed the highest adsorption selectivity, and its adsorption rate was more than 99.9% even in the presence of 0.5 M K+. A simulated soil decontamination experiment of Cs from a Cs-retaining vermiculite by using mordenite and that of Sr from a Sr-retaining vermiculite by using Linde-type A showed decontamination rates of more than 90%.

  10. Comparison of transfer factors of Sr-85 and Cs-134 for soils and crops of Greece

    International Nuclear Information System (INIS)

    Skarlou, V.; Papanicolaou, E. P.; Nobeli, C.

    1994-01-01

    The transfer of Sr-85 and Cs-134 from soil to plant (CR) was studied in two successive and similar in design glasshouse experiments. Six plant species (wheat, alfalfa, radish, string bean, cucumber, lettuce - only for Sr-85 - and endives - only for Cs-134), were grown in pots on eight Greek soils differing significantly in their physical and chemical properties. After the necessary measurements and analyses, big differences were detected in the transfer factors of both radionuclides with the soil types. The CRs of Sr-85 were higher than those of Cs-134 and for the tested crops and soils ranged between 0.3 and 36.5 for Sr-85 and between < 0.01 and 1.72 for Cs-134. The CRs of grains and seeds were much lower than those of leafy material for Sr-85 while the difference was not so high for Cs-134. The correlation between CRs and pH, negative in all cases, was significant or highly significant for all tested crops or plant parts (for Sr-85 r-bar = - 0.89, for Cs-134 r-bar = - 0.82). The values of CRs indicated a trend for negative correlation with other soil properties (cation exchange capacity-CEC, clay %). From exchangeable cations, exchangeable (Ca + Mg) as well as exchangeable bases, expressed as percentages of CEC, gave a significant or highly significant correlation with CRs of both radionuclides. (author)

  11. A survey of 90Sr and 137Cs activity levels of retail foods in Japan

    International Nuclear Information System (INIS)

    Abukawa, J.; Tsubuku, C.; Hayano, K.; Hirano, K.

    1998-01-01

    A comprehensive survey was conducted on 90 Sr and 137 Cs activity levels in retail foods purchased from retail markets all over Japan during the period 1989-1994, and the annual effective dose equivalent due to dietary ingestion was estimated. The concentrations of 90 Sr and 137 Cs in the food samples were determined using γ-ray spectrometry and the radiochemical method. The following were clarified by this study: (1) The 90 Sr and 137 Cs activity concentration levels were below 1 Bq kg -1 for almost all food samples except for the dried foods. (2) The activity concentration levels of 90 Sr and 137 Cs in foods of animal origin were different from those of plant origin. Generally, the former had higher 137 Cs and lower 90 Sr activity concentrations than the latter. (3) The mean and maximum values of the annual effective dose equivalent from a dietary intake of 90 Sr and 137 Cs by the consumption of retail foods were estimated to be as low as 1·3 and 4·1 μSv, respectively. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

  12. Sr-90, Cs-137 and Ce-144 in commercial tea from several areas in China

    International Nuclear Information System (INIS)

    Sha Lianmao; Qiu Yundian; Wang Zhihui; Wang Fenghua

    1993-01-01

    18 kinds of tea, most of which are famous products, were collected in 1985 from 10 provinces of China. More than 1 kg of manufactured tea was collected from each sampling location and ashed in a stainless steel pan by a rapid ashing apparatus made in China Institute for Radiation Protection. A 10 g aliquot of the ashed sample was subjected to radiochemical analysis for 90 Sr. 117 Cs and 144 Ce. Strontium, Cesium and Cerium carriers were added to the samples. The chemical yield of Sr, Cs and Ce were determined by weighting. After the radiochemical separation the mounted precipitates were counted for activity using a thin window methane gas-flow proportional counter normally for 100 min. Statistical error due to counting in generally was 90 Sr, 2.2 +- 0.9 Bq/kg for 137 Cs and 0.8 +- 0.2 Bq/kg for 144 Ce. Among these data, the content of 144 Ce in each tea sample is the lowest for its shorter lift. Higher values of 90 Sr concentration occurred in each tea sample than that of 137 Cs. This seems to be due to the fact that 137 Cs is tightly bound by soil than 90 Sr and the extent to which 90 Sr is absorbed from the soil by plants is greater than 137 Cs. (2 figs., 1 tab.)

  13. The effect of phytohormones on the 133Cs and 88Sr accumulation in oilseed rape

    International Nuclear Information System (INIS)

    Guo Mengluo; Xu Changhe; Li Xinlei; Wang Dan

    2011-01-01

    The effect of uptake and distribution of 133 Cs and 88 Sr in the common plant-India mustard (Brassica napus L.) by exogenous phytohormones (Gibberelin-A 3 GA 3 , Salicylates, SA, 3-indole acetic acid, IAA) treatments were studied by using hydroponic experiment. The results shown as follows: the biomass of above-ground and that of roots of oilseed rape were obviously higher than that of contrary (non-hormone), and the accumulation of 133 Cs and 88 Sr increased as well, under the three phytohormones treatments. The distribution sequence of 133 Cs and 88 Sr in oilseed rape was roots>above-grounds, and the contents was 1 3 3 Cs> 88 Sr. The accumulation ability of phytohormones was GA>SA>IAA, the accumulation of 133 Cs or 88 Sr increased with the phytohormone concentration. The treatment of mid-level of Gibberelin-A 3 (500 mg/L) and Salicylates acid (500 μmol/L) increased the biomass, enrichment and the translocation factors under the low concentration of 133 Cs and 88 Sr stress (1 mmol/L). Therefore, the phyto-extraction efficiency was enhanced in oilseed rape by using exogenous phytohormones. (authors)

  14. Foliar uptake of 134Cs and 85Sr in strawberry as function by leaf age

    International Nuclear Information System (INIS)

    Fortunati, P.; Brambilla, M.; Speroni, F.; Carini, F.

    2004-01-01

    In this paper a study of the foliar uptake and translocation of 134 Cs and 85 Sr in a herbaceous fruit plant is presented. In particular, absorption, translocation and loss of these radionuclides in strawberry plants have been studied in relation to the age of contaminated leaves. Strawberry plants were contaminated by distributing droplets of an aqueous solution containing 134 CsCl and 85 SrCl 2 on the surface of two leaves per plant. One half of the plants was contaminated through two young leaves, a second half through two old leaves. Sets of plants were collected 1 day, 7 days and 15 days after contamination. One half of them was rinsed with double distilled water before gamma analysis. Rinsing contaminated leaves removes on average 55% of the applied 134 Cs and 45% of 85 Sr. The activity removed decreases during the 15 days of the experimental study, both for 134 Cs and for 85 Sr, suggesting an increase in foliar absorption during this period. The activity removed does not differ between old and young leaves. 'External loss' is lower for young than old contaminated leaves. 'Internal loss' through translocation occurs mainly for 134 Cs. Translocation coefficients from contaminated leaves to fruits are two orders of magnitude higher for 134 Cs (4.0%), than for 85 Sr (0.05%). Leaf to fruit translocation coefficients for 134 Cs are higher from young leaves (5.8%), than from old leaves (2.3%)

  15. 137Cs and 9Sr uptake by sunflower cultivated under hydroponic conditions

    International Nuclear Information System (INIS)

    Soudek, Petr; Valenova, Sarka; Vavrikova, Zuzana; Vanek, Tomas

    2006-01-01

    The 9 Sr and 137 Cs uptake by the plant Helianthus annuus L. was studied during cultivation in a hydroponic medium. The accumulation of radioactivity in plants was measured after 2, 4, 8, 16 and 32 days of cultivation. About 12% of 137 Cs and 20% of 9 Sr accumulated during the experiments. We did not find any differences between the uptake of radioactive and stable caesium and strontium isotopes. Radioactivity distribution within the plant was determined by autoradiography. 137 Cs was present mainly in nodal segments, leaf veins and young leaves. High activity of 9 Sr was localized in leaf veins, stem, central root and stomata. The influence of stable elements or analogues on the transfer behaviour was investigated. The percentage of non-active caesium and strontium concentration in plants decreased with the increasing initial concentration of Cs or Sr in the medium. The percentage of 9 Sr activity in plants decreased with increasing initial activity of the nuclide in the medium, but the activity of 137 Cs in plants increased. The influence of K + and NH 4 + on the uptake of 137 Cs and the influence of Ca 2+ on the uptake of 9 Sr was tested. The highest accumulation of 137 Cs (24-27% of the initial activity of 137 Cs) was found in the presence of 10 mM potassium and 12 mM ammonium ions. Accumulation of about 22% of initial activity of 9 Sr was determined in plants grown on the medium with 8 mM calcium ions

  16. Rapid determination of actinides and {sup 90}Sr in river water

    Energy Technology Data Exchange (ETDEWEB)

    Habibi, A., E-mail: azza.habibi@irsn.fr [IRSN/PRP-ENV/STEME/LMRE, Rue du belvédère, Bâtiment 501, Bois des rames, 91400 Orsay (France); Boulet, B. [IRSN/PRP-ENV/STEME/LMRE, Rue du belvédère, Bâtiment 501, Bois des rames, 91400 Orsay (France); Gleizes, M. [IRSN/PRP-ENV/STEME, 31 rue de l' écluse, 78116 Le Vésinet (France); Larivière, D. [Laboratoire de radioécologie, Département de chimie, Université Laval, 1045 Avenue de la médecine, G1V 0A6 Québec (Canada); Cote, G. [PSL Research University, Chimie ParisTech CNRS, Institut de Recherche de Chimie Paris, 11 rue Pierre et Marie Curie, 75005 Paris (France)

    2015-07-09

    Highlights: • A new method to separate six actinides and {sup 90}Sr was developed. • The method was applied successfully to river water samples. • The separation and the measure take about seven hours. • The method permits to reach high yields. - Abstract: Nuclear accidents occurred in latest years highlighted the difficulty to achieve, in a short time, the quantification of alpha and beta emitters. Indeed, most of the existing methods, though displaying excellent performances, can be very long, taking up to several weeks for some radioisotopes, such as {sup 90}Sr. This study focuses on alpha and beta radioisotopes which could be accidentally released from nuclear installations and which could be measured by inductively coupled plasma mass spectrometer (ICP-MS). Indeed, a new and rapid separation method was developed for {sup 234,235,236,238}U, {sup 230,232}Th, {sup 239,240}Pu, {sup 237}Np, {sup 241}Am and {sup 90}Sr. The main objective was to minimize the duration of the separation protocol by the development of a unique radiochemical procedure with elution media compatible with ICP-MS measurements. Excellent performances were obtained with spiked river water samples. These performances are characterized by total yields exceeding 80% for all monitored radionuclides, as well as good reproducibility (RSD ≤ 10%, n = 12). The proposed radiochemical separation (including counting time) required less than 7 h for a batch of 8 samples.

  17. 137Cs and 90Sr in dairy and farm milk in Finnish Lapland 1960-2000

    International Nuclear Information System (INIS)

    Kostiainen, E.; Rissanen, K.

    2003-01-01

    The decrease rates of 90 Sr and 137 Cs in milk were studied in the years following the atmospheric nuclear weapon testings and after the Chernobyl accident in 1986. The highest 90 Sr and 137 Cs concentrations in the 1960's in Finnish milk were recorded in Lapland even though the deposition of 90 Sr and 137 Cs did not significantly differ between other localities in Finland, and they were not greater in northern Finland. This was mainly due to the high proportion of peat soils and nutrient deficiency of the pastures in Lapland. 137 Cs deposition after the Chernobyl accident in 1986 in Lapland was less than 1 kBq m-2, and 90 Sr deposition was so low that there was no detectable increase in the 90 Sr concentration in milk. The ecological half-lives were estimated for the decrease in the concentrations of 137 Cs and 90 Sr after the end of nuclear weapon testings period and the Chernobyl fallout during short and longer time intervals. (orig.)

  18. Cancer risk due to Cs-137 and Sr-90 dietary intake after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Toader, M; Vasilache, R A [Institute of Hygiene and Public Health, Bucharest (Romania)

    1997-09-01

    The most important radionuclides carried by the radioactive plume over Romania were I{sup 131}, Cs{sup 134}, Cs{sup 137} and Sr{sup 90}. As in many other countries, in the first days, I{sup 131} had the main contribution to the irradiation dose released to the population. After its decay, and the decay of the other short-lived radionuclides, Cs{sup 137} and Sr{sup 90} remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. Assessments of radiation doses to people living in the Bucharest area have utilized data obtained from measurement of Cs{sup 137} and Sr{sup 90} content in dietary intake samples for a number of subjects of different ages and sexes. This paper summarizes the results of some of our measurements performed since April 1986 until March 1995. 7 refs, 8 figs.

  19. Cancer risk due to Cs-137 and Sr-90 dietary intake after the Chernobyl accident

    International Nuclear Information System (INIS)

    Toader, M.; Vasilache, R.A.

    1997-01-01

    The most important radionuclides carried by the radioactive plume over Romania were I 131 , Cs 134 , Cs 137 and Sr 90 . As in many other countries, in the first days, I 131 had the main contribution to the irradiation dose released to the population. After its decay, and the decay of the other short-lived radionuclides, Cs 137 and Sr 90 remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. Assessments of radiation doses to people living in the Bucharest area have utilized data obtained from measurement of Cs 137 and Sr 90 content in dietary intake samples for a number of subjects of different ages and sexes. This paper summarizes the results of some of our measurements performed since April 1986 until March 1995. 7 refs, 8 figs

  20. Sorption Characteristics of 137Cs and 90Sr into Rembang and Sumedang Soils

    Directory of Open Access Journals (Sweden)

    Budi Setiawan

    2016-12-01

    Full Text Available In order to understand the sorption behavior of 137Cs and 90Sr into soil sample from Rembang and Subang, it is important to estimate the effect of contact time, ionic strength and concentration of metal ion in the solution. For this reason, the interaction of 137Cs and 90Sr with soil sample has been examined. The study performed at trace concentration (~10-8 M of CsCl and SrCl2, and batch method was used. NaCl has been selected as a representative of the ionic strength with 0.1; 0.5 and 1.0 M concentrations. Concentration of 10-8~10-4 M CsCl and SrCl2 were used for study the effect of Cs and Sr concentrations in solution. Apparent distribution coefficient was used to predict the sorption behavior. The sorption equilibrium of 137Cs and 90Sr into soil was attained after 5 days contacted with Kd value around 3300-4200 mL/g, where Kd was defined as the ratio of number of radionuclide activity absorbed in solid phase per-unit mass to the number of radionuclide activity remains is solution per-unit volume. Presence of NaCl as background salt in the solution affected Kd values due to competition among metal ions into soil samples. Increase of Cs or Sr concentration in solution made Kd value decreased drastically. This information is expected could provide an important input for the planning and design of radioactive waste disposal system in Java Island in the future.

  1. Distributions of 137Cs and 90Sr in the soil of Uljin, South Korea

    International Nuclear Information System (INIS)

    Song, Ji Yeon; Kim, Wan; Maeng, Seong Jin; Lee, Sang Hoon

    2016-01-01

    For the purpose of baseline data collection and enhancement of environmental monitoring the distribution studies of 137 Cs and 90 Sr in the soil of Uljin province was performed and the relation between surface soil activities and soil properties (pH, TOC and median of the surface soil) was analyzed. For 14 spots within 10 km from the NPP surface soil samples were collected and soils for depth profile were sampled for 3 spots in April 2011. Using γ-ray spectrometry with HPGe detector, the concentrations of 137 Cs were determined and the concentrations of 90 Sr were measured by counting β-activity of 90 Y (in equilibrium with 90 Sr) in a gas flow proportional counter. The concentration ranges of 137 Cs and 90 Sr were <0.479-39.6 Bq (kg-dry)-1 (avg. 7.51 Bq·(kg-dry)-1) and 0.209-1.85 Bq·(kg-dry)-1 (avg. 0.74 Bq·(kg-dry)-1) which were similar to the reported values from other regions in Korea. The activity ratio of 137 Cs to 90 Sr in surface soils was around 9.67, which is much bigger than the initial value of 1.75 for worldwide fallouts because of faster downward movement of 90 Sr after fall-out than that of 137 Cs. For depth profile studies soils were collected down to 40 cm depth for the locations of Deokgu, Hujeong and Maehwa. The 137 Cs concentration distribution of the first two showed maximum values at top soils and decreased rapidly in exponential manner, while 90 Sr showed two local maximum values for soils near top and about 30 cm depth. Through linear fittings between the 137 Cs and 90 Sr concentrations of surface soil and pH, TOC and median of the surface soil, the only probable relationship obtained was between 137 Cs and TOC (determination coefficient R2=0.6). The concentration ranges of 137 Cs and 90 Sr in Uljin were similar to the reported values from other regions in Korea. The only probable relationship obtained between activities and soil properties was between 137 Cs and TOC

  2. Distributions of {sup 137}Cs and {sup 90}Sr in the soil of Uljin, South Korea

    Energy Technology Data Exchange (ETDEWEB)

    Song, Ji Yeon; Kim, Wan; Maeng, Seong Jin; Lee, Sang Hoon [Kyungpook National University, Daegu (Korea, Republic of)

    2016-05-15

    For the purpose of baseline data collection and enhancement of environmental monitoring the distribution studies of {sup 137}Cs and {sup 90}Sr in the soil of Uljin province was performed and the relation between surface soil activities and soil properties (pH, TOC and median of the surface soil) was analyzed. For 14 spots within 10 km from the NPP surface soil samples were collected and soils for depth profile were sampled for 3 spots in April 2011. Using γ-ray spectrometry with HPGe detector, the concentrations of {sup 137}Cs were determined and the concentrations of {sup 90}Sr were measured by counting β-activity of {sup 90}Y (in equilibrium with {sup 90}Sr) in a gas flow proportional counter. The concentration ranges of {sup 137}Cs and {sup 90}Sr were <0.479-39.6 Bq (kg-dry)-1 (avg. 7.51 Bq·(kg-dry)-1) and 0.209-1.85 Bq·(kg-dry)-1 (avg. 0.74 Bq·(kg-dry)-1) which were similar to the reported values from other regions in Korea. The activity ratio of {sup 137}Cs to {sup 90}Sr in surface soils was around 9.67, which is much bigger than the initial value of 1.75 for worldwide fallouts because of faster downward movement of {sup 90}Sr after fall-out than that of {sup 137}Cs. For depth profile studies soils were collected down to 40 cm depth for the locations of Deokgu, Hujeong and Maehwa. The {sup 137}Cs concentration distribution of the first two showed maximum values at top soils and decreased rapidly in exponential manner, while {sup 90}Sr showed two local maximum values for soils near top and about 30 cm depth. Through linear fittings between the {sup 137}Cs and {sup 90}Sr concentrations of surface soil and pH, TOC and median of the surface soil, the only probable relationship obtained was between {sup 137}Cs and TOC (determination coefficient R2=0.6). The concentration ranges of {sup 137}Cs and {sup 90}Sr in Uljin were similar to the reported values from other regions in Korea. The only probable relationship obtained between activities and soil properties

  3. Incorporating Cs and Sr into blast furnace slag inorganic polymers and their effect on matrix properties

    Science.gov (United States)

    Vandevenne, Niels; Iacobescu, Remus Ion; Pontikes, Yiannis; Carleer, Robert; Thijssen, Elsy; Gijbels, Katrijn; Schreurs, Sonja; Schroeyers, Wouter

    2018-05-01

    Minimizing harmful effects to the environment in waste-management practices requires continuous innovation. This is especially important in the field of radioactive waste management. Alternatives to the commonly used ordinary Portland cement matrices are being increasingly studied for improved immobilisation purposes. The development of inorganic polymers (IP) from industrial residues has been successfully studied for the immobilisation of caesium (Cs+) and strontium (Sr2+). However, knowledge of the effect of these introduced elements on the IP-matrix is scarce, especially considering that studied effects are dependent on the IP-precursor characteristics and the form in which the Cs+ and Sr2+ are introduced. In this study, IPs containing varying amounts of CsNO3 and Sr(NO3)2 were developed to study the effect of the introduced elements on the IP-characteristics. IP-samples were developed from ground granulated blast furnace slag (GGBFS) and 6 M NaOH activating solution. Cs+ and Sr2+ were added to account for 0.5, 1 and 2 wt% of the total IP-mass. Throughout the entire study, Cs+-addition showed no significant effects on the studied parameters. Calorimetric results showed that Sr2+ severely affects reaction kinetics, consuming hydroxide ions necessary for the alkali activation reaction. Sr2+-addition also caused a severe decrease in compressive strength, increased calcium leaching, and decreased sodium and hydroxide leaching. Micro-chemical analyses showed that Cs+ is almost fully incorporated in the formed IP-matrix, while Sr2+ mainly precipitates as Sr(OH)2 in concentrated regions throughout the IP-structure. The findings presented in this paper give insights on the effect of contaminant elements on the immobilising matrix.

  4. Assessment of 137Cs and 90Sr Fluxes in the Barents Sea

    Science.gov (United States)

    Matishov, Gennady; Usiagina, Irina; Kasatkina, Nadezhda; Ilin, Gennadii

    2014-05-01

    On the basis of published and own data the annual balance of radionuclide income/outcome was assessed for 137Cs and 90Sr in the Barents Sea for the period from 1950s to the presnt. The scheme of the isotope balance calculation in the Barents Sea included the following processes:atmospheric fallout; river run-off; liquid radioactive wastes releases, income from the Norwegian and the White Seas; outflow to the adjacent areas through the Novaya Zemlya straits and the transects Svalbard-Franz Josef Land and Franz Josef Land-Novaya Zemlya; radioactive decay. According to the multiyear dynamics, the inflow of 137Cs and 90Sr to the Barents Sea was significantly preconditioned by currents from the Norwegian Sea. Three peaks of 137Cs and 90Sr isotope concentrations were registered for the surface waters on the western border of the Barents Sea. The first one was observed in the mid-1960s and was conditioned by testing of nuclear weapons. The increase of isotope concentrations in 1975 and 1980 was preconditioned by the discharge of atomic waste by the Sellafield nuclear reprocessing plant. Nowadays, after the sewage disposal plant was built, the annual discharge of nuclear waste from Sellafield plant is low. The Norwegian Sea was a major source of 137Cs and 90Sr isotope income into the Barents Sea for the period of 1960-2014. Currently, the transborder transfer of 90Sr and 137Cs from the Norwegian Sea into the Barents Sea constitutes about 99% of income for each element. Atmospheric precipitation had a major impact in the 1950-1960s after the testing of the nuclear weapons, and in 1986 after the accident at Chernobyl Nuclear Power Station. In 1963, the atmospheric precipitation of 137Cs reached 1050 TBq; and that of 90Sr, 630 TBq. In 1986, a significant amount of 137Cs inflow (up to 1010 TBq/year) was registered. The 137Cs isotope income exceeded the 90Sr income in the 1960s-1980s, and equal amounts penetrated into the Barents Sea from the Norwegian Sea in the 1990s. Before

  5. Study on the mechanisms of solidification for Cs+ and Sr2+ in alkali-activated slag cement waste forms

    International Nuclear Information System (INIS)

    Yan Sheng; Shen Xiaodong; Lu Linchao; Wu Xuequan; Wen Yinghui

    1994-09-01

    The mechanisms of adsorption and chemical immobilization in Alkali-Activated Slag Cement (AASC) waste forms were quantitatively studied for Cs + and Sr 2+ . Experimental results show that, hardened AASC paste with zeolite and silica fume possesses strong adsorption ability and anti-desorption ability for Cs + and Sr 2+ . The results and analyzed by XRD show that CS + and SR 2+ could be incorporated into the lattice of C-S-H by replacing Ca 2+ in C-S-H. The d 111 values of C-S-H increase with increasing CsNO 3 and Sr(NO 3 ) 2 dosages in a limited and regular step. After washed out by deionized water in a ultrasonic washer, samples were analyzed by SEM-EDS and a lot of Cs + and Sr 2+ were detected. This means that the hydration products of AASC have a high retaining ability for Cs + and Sr 2+ . (3 tabs., 8 figs.)

  6. Analysis of the direct contamination pathway of 85Sr, 103Ru and 134Cs in soybean

    International Nuclear Information System (INIS)

    Yim, K. M.; Park, D. W.; Park, H. K.; Choi, Y. H.; Choi, S. D.; Lee, C. M.

    2001-01-01

    A solution containing 85 Sr, 103 Cs was sprayed to the aerial part of the soybean plant in a greenhouse at 6 different times before harvest and the direct contamination pathway of the radionuclide analyzed. Plant interception factor showed little difference among radionuclides. The maximum value was 0.93, which was observed at the middle growth stage. Translocation factors 85 Sr, 103 Cs in the soybean seed at harvest were in the range of 4.5x10 -5 ∼2.5x10 -3 , 6.0x10 -5 ∼2.3x10 -4 and 4.5x10 -3 ∼3.0x10 -1 , respectively. They were highest at the 3rd application for 85 Sr and 134 Cs and at the 2nd application for 103 Ru. Translocation factors of 85 Sr and 103 Ru in the soybean shell tended to increase with decreasing time interval between application and harvest but that of 134 Cs was highest at the 2nd application. The fractions of the initial deposition that remained in the soybeam plant at harvest were in the range of 0.14 ∼15.2% for 85 Sr and 103 Ru, 9.9∼41.9% for 134 Cs. These results can be utilized for predicting the radionuclide concentration in mature soybean plant and deciding counter-measures when an accidental deposition of the radionuclides occurs during the growing season of soybean

  7. On the geochemistry of 'Chernobyl' Cs-137 and Sr-90 in the Black Sea

    International Nuclear Information System (INIS)

    Batrakov, G.F.; Chudinovskikh, T.V.; Zemlyanoi, A.D.; Eremeev, V.N.

    1998-01-01

    The following correlations for Cs 137 and Sr 90 were found. For Cs-137, the relation of its concentration in suspended matter to that in the dissolved component is 2.4 centre dot 10 5 in the Dnieper waters and 0.0037 centre dot 10 5 in the North-West shelf waters; for Sr-90 - 0.44 centre dot 10 3 and 2.8 centre dot 10 3 , respectively. The relation of the concentration of dissolved Cs-137 in the sea and in the Dnieper waters is 4.3, and for Sr-90 - 0.25. It is evident that these basic correlations for Cs-137 are close to those for stable cesium. These correlations for Sr-90 differ very much from those for stable strontium. So, the situation formed for the last time in the boundary area 'the Dnieper river - the North-Western Black Sea' is close to the balanced one for Cs-137, while it is very far from that for Sr-90

  8. Leaching of Cs and Sr from sewage sludge ash buried in a landfill site

    International Nuclear Information System (INIS)

    Ishikawa, Nao; Umita, Teruyuki; Ito, Ayumi

    2014-01-01

    Radionuclide contamination from the nuclear accident at the Fukushima Daiichi Nuclear Power Plant has been found in sewage sludge ash produced in eastern Japan. When such contaminated waste contains less than 8,000 Bq/kg radiocesium, it is being disposed in controlled landfill sites. In order to assess the possible spread of the radionuclides by their leaching from the landfill sites, it is important to know the leaching behavior of the radionuclides from the sewage sludge ash and factors influencing the leaching behavior. In this study, leaching experiments using stable Cs and Sr were conducted for sewage sludge ash under several conditions to investigate effects of chemical composition of leachate, pH, and solid/liquid ratio on Cs and Sr leaching behaviors. In the pH range from 6 to 12, the leaching ratio of Cs or Sr was less than 5.2 or 0.21%, respectively. Additionally, the leaching ratio of Sr decreased with increasing pH of the leachate. In contrast, the higher the pH in the leachate was, the higher the leaching ratio of Cs was. Finally, possible radionuclide leaching from contaminated sewage sludge ash and then radionuclide concentrations in an actual landfill leachate were assessed. It could be suggested that 90 Sr leaching from the landfill site had the least effect on the environment, whereas 134+137 Cs leaching needed to be taken into account for spreading radioactive materials from the landfill site to the environment. (author)

  9. Annual intake of 137Cs and 90Sr from ingestion of main foodstuffs in Taiwan

    International Nuclear Information System (INIS)

    Wang, Chih-Jung; Lai, Shu-Ying; Huang, Ching-Chung; Lin, Yu-ming

    1996-01-01

    The radioactivities of eight main foodstuffs were investigated during 1985-1994 to evaluate the annual intake from the ingestion of 137 Cs and 90 Sr for the residents of Taiwan. The evaluation of annual intake was based on the results of radiochemical analysis of 90 Sr and gamma-ray spectrometry of 137 Cs as well as annual consumption rates of those foodstuffs in Taiwan. The annual intake 90 Sr and 137 Cs per capita is 13 and 60 Bq, respectively. Among the eight foodstuffs, fruit contributed the most to the annual intake of 90 Sr, vegetable second, rice the third and egg the least. For 137 Cs, rice contributed the most, then fruit, meat the third and flour the least. Based on the new conversion factors from ICRP 60, the annual committed effective doses of Taiwanese due to the ingestion of radionuclides 90 Sr and 137 Cs were estimated to be 3.7 x 10 -7 and 7.8 x 10 -7 Sv, respectively. (author)

  10. Activity ratios of {sup 137}Cs, {sup 90}Sr and {sup 239+240}Pu in environmental samples

    Energy Technology Data Exchange (ETDEWEB)

    Bossew, P. [European Commission - DG Joint Research Centre, Institute for Environment and Sustainability (IES), I-21020 Ispra (Vatican City State, Holy See,) (Italy)], E-mail: peter.bossew@jrc.it; Lettner, H. [Institute of Physics and Biophysics, University of Salzburg, Hellbrunner Strasse 34, A-5020 Salzburg (Austria)], E-mail: herbert.lettner@sbg.ac.at; Hubmer, A.; Erlinger, C.; Gastberger, M. [Institute of Physics and Biophysics, University of Salzburg, Hellbrunner Strasse 34, A-5020 Salzburg (Austria)

    2007-09-15

    Both global and Chernobyl fallout have resulted in environmental contamination with radionuclides such as {sup 137}Cs, {sup 90}Sr and {sup 239+240}Pu. In environmental samples, {sup 137}Cs and {sup 239+240}Pu can be divided into the contributions of either source, if also the isotopes {sup 134}Cs and {sup 238}Pu are measurable, based on the known isotopic ratios in global and Chernobyl fallout. No analogous method is available for {sup 90}Sr. The activity ratios of Sr to Cs and Pu, respectively, are known for the actual fallout mainly from air filter measurements; but due to the high mobility of Sr in the environment, compared to Cs and Pu, these ratios generally do not hold for the inventory many years after deposition. In this paper we suggest a method to identify the mean contributions of global and Chernobyl fallout to total Sr in soil, sediment and cryoconite samples from Alpine and pre-Alpine regions of Austria, based on a statistical evaluation of Sr/Cs/Pu radionuclide activity ratios. Results are given for Sr:Cs, Sr:Pu and Cs:Pu ratios. Comparison with fallout data shows a strong depletion of Sr against Cs and Pu.

  11. Distribution coefficients for 85Sr and 137Cs in Japanese agricultural soils and their correlations with soil properties

    International Nuclear Information System (INIS)

    Kamei-Ishikawa, N.; Uchida, S.; Tagami, K.

    2008-01-01

    In this work, soil-soil solution distribution coefficients (K d ) of Sr and Cs were obtained for 112 Japanese agricultural soil samples (50 paddy soil and 62 upland soil samples) using batch sorption test. The relationships between Sr- or Cs-K d values and soil properties were discussed. Furthermore, the amount of Cs fixed in soil was estimated for 22 selected soil samples using a sequential extraction method. Then, cross effects of some soil properties for Cs fixation were evaluated. (author)

  12. 137Cs Dan 90Sr Concentration In Several Vegetables From Lahat South Sumatra Province

    International Nuclear Information System (INIS)

    Emlinarti; Tutik-Indiyati

    2003-01-01

    Analysis of 137 Cs and 90 Sr in several vegetables, i.e beans, green peas, spinachs, gourd, nightshade, cabbages, carrots and potatoes, collected from Lahat. South Sumatra had been carried out. Analysis radiochemically were carried out, 137 Cs precipitated with ammmoniumphosphomolybdate. The samples were measured using the gamma spectrometer with the high purity germanium detector (HP-Ge). 90 Sr precipitated with fuming HNO 3 and measured using alpha/beta Low Background Counter system (LBC). Concentration of 137 Cs in the samples were varied from undetectable to (0.041 ± 0.015) Bq/kg and concentration of 90 Sr were varied from undetectable to (0.049 ± 0.017) Bq/kg. Compared with similar foodstuffs collected from several places in Lampung province, these results are relatively not different. (author)

  13. Cs 137 and Sr 90 content in the Kozloduy NPP environment; Soderzhanie 137Cs i 90Sr v obektakh okruzhayushchej sredy v rajone AEhS `Kozloduy`

    Energy Technology Data Exchange (ETDEWEB)

    Karaivanova, R; Totseva, R; Badulin, V; Zlatanova, R; Fajtondzhieva, K [National Centre of Radiobiology and Radiation Protection, Sofia (Bulgaria)

    1996-12-31

    The radioactivity status of soil and plant samples collected in the 12 km controlled zone surrounding Kozloduy has been investigated in the period 1990-1993. The average annual concentrations of Sr-90 and Cs-137 are compared to the values taken at 40 km distance. Cs-137 has in general higher concentrations in soil samples from the NPP close surroundings - e.g. 50-55 Bq/kg in 1992 versus 2-2.5 Bq/kg for Sr-90. Radionuclide concentrations in grass do not differ significantly from the data at 40 km distance. It is concluded that the average annual doses follow the radionuclide dynamics in the global fallout and the effect of Kozloduy operation can not be separated from the background radioactivity status. 4 refs., 21 figs.

  14. Internal contamination assessment, with regard to 90Sr, 134Cs, and 137Cs nuclei during nuclear accident

    International Nuclear Information System (INIS)

    Ayad, M.; Hanna, K.M.

    2000-01-01

    In case of nuclear reactor accident leading to the release of some radioactive isotopes in the plume, the sedimentation of its constituents on the ground causes surface contamination which consequently can be observed in the form of an internal contamination in the living biosphere. The migration of the radio nuclei from the soil to the plant root, stem, and the other edible parts is considered the main source for the contaminated foodstuffs used by the general public. In this work we have calculated the total accumulative internal dose for 9 0Sr, 1 34Cs, and 1 37Cs radio contaminants with regard to different public age groups (infant, child, and adult) due to an unexpected nuclear accident. In our calculations we have applied the protective measure inequality for the chosen standard group of foodstuffs, with respect to each age group of the public as well as the three indicated above radio nuclei. Our results indicated that the values of the calculated protective measures with regard to 9 0Sr, 1 37Cs, and 1 34Cs radio nuclei are increasing respectively for all age groups. In addition, we found that the ratio of the total protection measure values of all radio nuclei for different age groups still less than one which requires no intervention level procedures

  15. Retention of 137Cs and 90Sr by mineral sorbents surrounding vitrified nuclear waste

    International Nuclear Information System (INIS)

    Lyon, K.E.; Patterson, R.J.

    1985-01-01

    In June 1960, twenty-five 14-cm diameter hemispheres of vitrified nuclear waste (glass blocks) were buried in a shallow sand aquifer in the lower Perch Lake Basin, Chalk River Nuclear Laboratories, Ontario, Canada. Almost all leaching of the glass blocks occurred during the first 18 months of emplacement, and consequently the burial experiment approximated a single-injection source of 137 Cs and 90 Sr. After about 11 years, most of the 90 Sr that was released had been advected and dispersed from the site, whereas the bulk of the 137 Cs had travelled no more than 0.3 m from the blocks. Three piezometers were installed and five cores of sediment were collected at the glass block site in 1978. Mineralogically pure segregates of sand grains were prepared by hand and characterized using binocular, petrographic and scanning electron microscopy, X-ray diffraction, and energy-dispersive X-ray spectroscopy. A technique also was developed to measure very low levels of 137 Cs and 90 Sr by counting small (10-100 mg) sediment samples directly with a thin window, flow proportional counter. Results show that sand-sized grains of altered biotite (biotite-vermiculite), biotite, muscovite, hornblende and serictized feldspar are able to retain 137 Cs over a period of 18 years, and that grains of biotite-vermiculite, biotite and hematite-bearing feldspar (largely microline) can retain low levels of 90 Sr over the same period of time. The amounts of 137 Cs and 90 Sr sorbed by the mineral grains ranged from undetectable levels to approximately 380 and 35 becquerels/gram sediment, respectively. This report contains the complete series of mineral segregates ranked on a weight basis according to the amounts of retained 137 Cs and 90 Sr. Ground-water quality data indicate that none of the retention is the result of the precipitation of strontium or cesium minerals

  16. Sorption and migration characteristics of 137Cs and 90Sr in natural dispersed systems

    International Nuclear Information System (INIS)

    Lishtvan, I.I.; Brovka, G.P.; Dedyulya, I.V.; Rovdan, E.N.

    1996-01-01

    Sorption and migration characteristics of 137 Cs and 90 Sr have been determined in fen peat, Quarts sand, kaolin and bentonite. An electrolyte effect on the radio nuclides sorption and diffusion in the given systems has been studied. Presence of stable isotopes of cesium and strontium in the porous solution has been revealed to affect 137 Cs and 90 Sr distribution and diffusion indices permitting for the effective diffusion index to increase by two orders of magnitude. 137 Cs in the peat technical contamination resulting from the Chernobyl NPP accident has been found to be mainly in an exchange form and under steady state conditions up to 75% of 137 Cs can be transformed into water-soluble state for 8-12 months under effect of stable cesium chloride (0.2 (g-eq)/l). (authors). 4 tabs., 4 refs

  17. Modelling the distribution of 90Sr and 137Cs in the Mediterranean Sea (MTPII-MATER)

    International Nuclear Information System (INIS)

    Sanchez-Cabeza, J.A.; Ortega, M.; Fernandez, V.; Tintore, J.; Monaco, A.

    1999-01-01

    Within the frame of the MTPII-MATER project (MAST), the distribution of 90 Sr and 137 Cs in the Mediterranean Sea was modelled, as these radionuclides are useful tracers of water circulation. The Mediterranean Sea was divided into 81 boxes, corresponding to 21 regions, taking into account water mass circulation, bathymetry and data availability. Transfer rates were obtained from the MOM model run under MEDMEX conditions. The model was run with realistic inputs, which included weapons global fallout, Chernobyl 137 Cs, nuclear industry and river runoff. It was observed that existing data are scarce, especially in the eastern Mediterranean. In general, model predictions agreed well with observations, showing maximum concentrations in surface waters and maxima due to global fallout ( 137 Cs and 90 Sr) and to the Chernobyl accident ( 137 Cs only). (author)

  18. Environmental distribution of long-lived radionuclides /sup 90/Sr and /sup 137/Cs

    Energy Technology Data Exchange (ETDEWEB)

    Csupka, S [Krajska Hygienicka Stanica, Bratislava (Czechoslovakia)

    1977-01-01

    Between 1963 and 1974 the content was investigated of /sup 90/Sr and /sup 137/Cs in various parts of human environment. From food chains milk and dairy products, flour and flour products were chosen being the main sources of radioactivity produced by the above mentioned radionuclides to which the human population is exposed. In 1972 /sup 90/Sr and /sup 137/Cs in the daily intake of food were responsible for 60 to 70% of total radioactivity in milk and flour products. On a world scale radioactive fallout continues to be the primary source of radioactive contamination with the soil in which radionuclides are accumulated being the secondary source.

  19. Assessment of dietary of 90Sr and 137Cs by the population of the GDR

    International Nuclear Information System (INIS)

    Ziesak, H.; Kunert, M.; Kunert, J.

    1978-01-01

    Based on data pertaining to the per caput consumption of the most important classes of foodstuffs and their contents of 90 Sr and 137 Cs, calculations were made to find out the yearly ingestion of these fallout radionuclides by the adult population in 1975. The strong decline in values of ingestion to be noticed since 1964 is due to the falling 90 Sr and 137 Cs levels in most biomedia as well as to changes in nutritional habits and allows a sensible curtailment of the foodstuff monitoring programme for radionuclides to be made. (author)

  20. Mechanical environmental transport of actinides and ¹³⁷Cs from an arid radioactive waste disposal site.

    Science.gov (United States)

    Snow, Mathew S; Clark, Sue B; Morrison, Samuel S; Watrous, Matthew G; Olson, John E; Snyder, Darin C

    2015-10-01

    Aeolian and pluvial processes represent important mechanisms for the movement of actinides and fission products at the Earth's surface. Soil samples taken in the early 1970's near a Department of Energy radioactive waste disposal site (the Subsurface Disposal Area, SDA, located in southeastern Idaho) provide a case study for studying the mechanisms and characteristics of environmental actinide and (137)Cs transport in an arid environment. Multi-component mixing models suggest actinide contamination within 2.5 km of the SDA can be described by mixing between 2 distinct SDA end members and regional nuclear weapons fallout. The absence of chemical fractionation between (241)Am and (239+240)Pu with depth for samples beyond the northeastern corner and lack of (241)Am in-growth over time (due to (241)Pu decay) suggest mechanical transport and mixing of discrete contaminated particles under arid conditions. Occasional samples northeast of the SDA (the direction of the prevailing winds) contain anomalously high concentrations of Pu with (240)Pu/(239)Pu isotopic ratios statistically identical to those in the northeastern corner. Taken together, these data suggest flooding resulted in mechanical transport of contaminated particles into the area between the SDA and a flood containment dike in the northeastern corner, following which subsequent contamination spreading in the northeastern direction resulted from wind transport of discrete particles. Copyright © 2015 Elsevier Ltd. All rights reserved.

  1. Some characteristics 90Sr and 137Cs metabolism in newborn bank voles

    International Nuclear Information System (INIS)

    Bondar'kov, M.D.; Gashchak, S.P.; Goryanaya, Yu.A.; Chesser, R.K.

    2002-01-01

    There are reported research results of features of 90 Sr and 137 Cs accumulation and excretion in organism of newborn bank voles in first weeks of the life, on example of 5 litters. Pregnant females were captured in the Chornobyl zone and maintained at laboratory conditions on 'clean' food. Already now it can be said, that amount of 90 Sr and 137 Cs out-take from mother organism with newborn babies considerably higher, than in further with milk (in any case, in first week of lactation). Parameters of 137 Cs transfer from mother to generation are always higher, than 90 Sr one. Peculiarities of radionuclide accumulation in baby's organism are conditioned by chemical properties of the radionuclide. Therefore at conditions of 'depuration' of mother organism 137 Cs contents in babies increases at beginning, then after 30-40% exceeding of initial values it begins to decrease. Everything takes place in first week of life. 90 Sr contents grows over all suckling period long and only then it begins to decrease, if does not intake with food

  2. Transfer of Cs137 and Sr90 from contaminated soil to some crops in Syria

    International Nuclear Information System (INIS)

    Yassine, T.; Al-Oudat, M.; Othman, I.; Sharaneq, A.

    1998-07-01

    Transfer factors of Cs 137 and Sr 90 from contaminated soil to some common crops were investigated under field conditions for a period of three years. The results showed large variations in transfer factor values (expressed as Bq/g of dried material to Bq/g of soil) among crops. The highest values for both radionuclides were found in green vegetables up to 0.067 for 137 Cs and 3.78 for 90 Sr, whereas cereal grains had the lowest values. The transfer factor values of 90 Sr were generally much higher than that of 137 Cs for the same crop by factors ranged up to 263. The values for both radionuclides were found to be in the lower limits of that obtained in other areas. This was attributed to the effect of several parameters such as high ph, low organic matter and high exchangeable potassium and calcium in the soil. The transfer factor values of 137 Cs were decreased from the first year to the third year for most crops by factor up to 4, while this approach was not found for 90 Sr. (author)

  3. The transfer of {sup 137}Cs and {sup 90}Sr from feed to rabbits

    Energy Technology Data Exchange (ETDEWEB)

    Semioshkina, N. [GSF-Institut fuer Strahlenschutz, Ingolstaedter Landstr. 1, Postfach 1129, D-85788 Neuherberg (Germany)], E-mail: semi@gsf.de; Proehl, G. [GSF-Institut fuer Strahlenschutz, Ingolstaedter Landstr. 1, Postfach 1129, D-85788 Neuherberg (Germany); Savinkov, A. [The Scientific Research Agricultural Institute of the National Biotechnology Center, Ministry for Science and Higher Education of the Republic of Kazakhstan (SRAI), 480544 Gvardeiski (Kazakhstan); Voigt, G. [Agency' s Laboratories, Seibersdorf, IAEA, 1400-Vienna (Austria)

    2007-11-15

    Radiological assessment of the impact of nuclear weapons testing on the local population in the Semipalatinsk Test Site (STS) requires comprehensive site-specific information on radionuclide behaviour in the environment. However, information on radionuclide behaviour in the conditions of the STS is rather sparse and, in particular, there are no data in the literature on parameters of radionuclide transfer from feed to rabbit products which have been identified as contributors to internal dose to the inhabitants. The transfer of {sup 137}Cs and {sup 90}Sr to rabbit meat was studied under laboratory conditions in a controlled experiment with 32 locally bred rabbits maintained in the Kazakh Agricultural Research Institute. The equilibrium transfer coefficients for {sup 137}Cs and {sup 90}Sr from feed to rabbit meat were estimated to be 0.4 d kg{sup -1} and 0.15 d kg{sup -1}, respectively. The biological half-lives were estimated to be 0.1 d for {sup 137}Cs and 0.14 d for {sup 90}Sr. Whereas for {sup 137}Cs the distribution in the body is relatively homogeneous, there are large differences between the organs and tissues for {sup 90}Sr for which, as expected, the highest concentrations were found in bone.

  4. The transfer of 137Cs and 90Sr from feed to rabbits

    International Nuclear Information System (INIS)

    Semioshkina, N.; Proehl, G.; Savinkov, A.; Voigt, G.

    2007-01-01

    Radiological assessment of the impact of nuclear weapons testing on the local population in the Semipalatinsk Test Site (STS) requires comprehensive site-specific information on radionuclide behaviour in the environment. However, information on radionuclide behaviour in the conditions of the STS is rather sparse and, in particular, there are no data in the literature on parameters of radionuclide transfer from feed to rabbit products which have been identified as contributors to internal dose to the inhabitants. The transfer of 137 Cs and 90 Sr to rabbit meat was studied under laboratory conditions in a controlled experiment with 32 locally bred rabbits maintained in the Kazakh Agricultural Research Institute. The equilibrium transfer coefficients for 137 Cs and 90 Sr from feed to rabbit meat were estimated to be 0.4 d kg -1 and 0.15 d kg -1 , respectively. The biological half-lives were estimated to be 0.1 d for 137 Cs and 0.14 d for 90 Sr. Whereas for 137 Cs the distribution in the body is relatively homogeneous, there are large differences between the organs and tissues for 90 Sr for which, as expected, the highest concentrations were found in bone

  5. Blastomogenic effect of Cs137, Sr90 and Ca45 in single and chronic administration

    International Nuclear Information System (INIS)

    Zapol'skaya, N.A.; Fedorova, A.V.; Borisova, V.V.

    1978-01-01

    The blastomogenic actions of 137 Cs, 90 Sr, and 45 Ca were considered in experiments on white rats, and it was found that the site and type of tumor were determined by the organotropism of the radionuclide. With chronic administration of radionuclides, the tumor rate was low as compared to single-occasion administration

  6. Distribution of ^<90>Sr and ^<137>Cs in Annual Tree Rings of Japanese Cedar, Cryptomeria Japonica D.Don.

    OpenAIRE

    千木良, みどり; 斎藤, 裕子; 木村, 幹; MIDORI, CHIGIRA; YUKO, SAITO; KAN, KIMURA; 青山学院大学理工学部; 青山学院大学理工学部; 青山学院大学理工学部; Department of Chemistry, College of Science and Engineering, Aoyama Gakuin University; Department of Chemistry, College of Science and Engineering, Aoyama Gakuin University; Department of Chemistry, College of Science and Engineering, Aoyama Gakuin University

    1988-01-01

    The contents of ^Sr and ^Cs in two samples of Japanese cedar from Takao and Tsukui districts were determined in tree rings cut into segments representing steps of 5 years of growth. ^Sr in both cedar samples and ^Cs in the Tsukui cedar sample were determined after ashing and chemical isolation, while ^Cs in the Takao sample was directly determined from the sample ash. The distribution of ^Sr fallout in tree rings suggests that ^Sr had given a rather direct effect and showed no significant tra...

  7. Distribution of 90Sr and 137Cs in annual tree rings of Japanese cedar, Cryptomeria Japonica D. Don

    International Nuclear Information System (INIS)

    Chigira, Midori; Saito, Yuko; Kimura, Kan

    1988-01-01

    The contents of 90 Sr and 137 Cs in two samples of Japanese cedar from Takao and Tsukui districts were determined in tree rings cut into segments representing steps of 5 years of growth. 90 Sr in both cedar samples and 137 Cs in the Tsukui cedar sample were determined after ashing and chemical isolation, while 137 Cs in the Takao sample was directly determined from the sample ash. The distribution of 90 Sr fallout in tree rings suggests that 90 Sr had given a rather direct effect and showed no significant translocation from sapwood to heartwood, whereas 137 Cs tends to concentrate in heartwood irrespective of the effect of the fallout. Average contents of 90 Sr and 137 Cs were 22 and 9.4 pCi/kg in the Takao sample (9.61 kg air dried) and were 23 and 12 in the Tsukui (4.71 kg air dried) in 1982. (author)

  8. Depth migration of Chernobyl originated 137Cs and 90Sr in soils of Belarus

    International Nuclear Information System (INIS)

    Kagan, L.M.; Kadatsky, V.B.

    1996-01-01

    Depth migration of 137 Cs and 90 Sr was studied in soils of reference sites that have different environmental characteristics and are situated in all four radiochemical regions of Belarus. The parameters as used were: the fraction of the nuclide inventory below a depth of 2 cm; the fraction of the nuclide inventory below a depth of 5 cm; and the thickness of the top soil layer containing 90% of the nuclide inventory. Despite the apparent differences in the nuclide migration at various sites, some common tendencies were observed. During the first 3-5 years after the accident, the 90 Sr depth migration at several watershed and terrace sites did not exceed that of 137 Cs. About 5-15% of the nuclide inventories are below the depth of 5 cm, and 90% are contained in the top 3-7 cm soil layer. However, at the floodplain reference sites, a pronounced tendency for a higher migration rate of 90 Sr was revealed. Less than 5% of the 137 Cs inventory but about 5-30% of the 90 Sr inventory are below 5 cm, and the top soil layer containing 90% of the nuclide inventory is 1-2 cm thicker for 90 Sr. (Author)

  9. Determination of distribution ratio for 60Co, 85Sr and 134Cs in loess medium

    International Nuclear Information System (INIS)

    Tanaka, Tadao; Ogawa, Hiromichi; Zhentang Li; Hui Wang; Kamiyama, Hideo.

    1994-06-01

    Distribution ratio R for 60 Co, 85 Sr and 134 Cs between loess and ground water was measured by using 16 loess samples taken from the field test site of China Institute for Radiation Protection, in which the field test of radionuclide migration had been performed. The R of each radionuclide was taken nearly constant value among 16 samples. This revealed that the site can be regarded as uniform loess medium from the view point of sorption ability. The sorption ability between the three radionuclides was the order of 134 Cs > 60 Co >> 85 Sr. The 85 Sr was an available nuclide for examining the migration phenomena, because 85 Sr might easily migrate in the loess medium due to its low sorption ability. The results of parametric check suggested that it is necessary to select the valid temperature and pH for determining the R value. The sorption of Sr on the loess was dominated by reversible ion-exchange reaction, while that of Co and Cs was dominated by irreversible one. (author)

  10. Sr90 and Cs137 content in major types of food stuffs

    International Nuclear Information System (INIS)

    Knizhnikov, V.A.; Petukhova, Eh.V.

    1980-01-01

    Tables of 90 Sr and 137 Cs content in the major types of food stuffs in different regions of the USSR from 1963 to 1973, are presented. Maximum contamination is observed in 1963 and 1964. Variations of contamination of food stuffs depending upon fallout alterations during 1963-1964 are analyzed. The increased contamination of fish products, bread, deer meat and tea is observed in these years. The dependence of contamination of certain products on the area of their production is pointed out which makes possible a wide variation of results of investigations. It is established that the less contamination of food stuffs is observed in the areas with black soil. It is stated that 137 Cs contamination of food stuffs is several times higher than 90 Sr contamination, which is probably connected with a better 137 Cs uptake by vegetation from aerial fallouts

  11. Crystal structure and thermal expansion of CsCaI3:Eu and CsSrBr3:Eu scintillators

    Science.gov (United States)

    Loyd, Matthew; Lindsey, Adam; Patel, Maulik; Koschan, Merry; Melcher, Charles L.; Zhuravleva, Mariya

    2018-01-01

    The distorted-perovskite scintillator materials CsCaI3:Eu and CsSrBr3:Eu prepared as single crystals have shown promising potential for use in radiation detection applications requiring a high light yield and excellent energy resolution. We present a study using high temperature powder X-ray diffraction experiments to examine a deleterious high temperature phase transition. High temperature phases were identified through sequential diffraction pattern Rietveld refinement in GSAS II. We report the linear coefficients of thermal expansion for both high and low temperature phases of each compound. Thermal expansion for both compositions is greatest in the [0 0 1] direction. As a result, Bridgman growth utilizing a seed oriented with the [0 0 1] along the growth direction should be used to mitigate thermal stress.

  12. The content of K-40, Sr-90 and Cs-137 in milk in Croatia

    International Nuclear Information System (INIS)

    Cesar, D.; Maracic, M.; Marovic, M.

    1996-01-01

    Milk is one of the most important foodstuffs. The children's diet is based on milk and quality of milk has always been a subject of concern and continuous control. investigation of radioactivity in milk in Croatia has been started in 1960. The samples of milk were collected daily in the towns Osijek, Zadar and Zagreb. In monthly samples specific Sr-90 activities were determined by radiochemical separation, and Cs-137 and K-40 by gammaspectrometric analysis. The values obtained are shown in Figures 1 and 2. The ratio of Sr-90, Cs-137 and K-40 specific activities was calculated as well as the ratio of their maximum prmissible levels. By the division of these two ratios the ratio of their effectiveness was calculated. On basis of the obtained data the following conclusions can be drawn: 1. The level of Sr-90 in milk had been increasing by 1964. in the period that followed Sr-90 was exponentially decreasing which indicated that its content in milk originated mostly from nuclear weapon tests carried out in the period 1945 to 1962. 2. The content of Cs-137 in milk in Croatia has been exponentially decreasing since 1965 in spite of a great increase in 1986. This points to the fact that Cs-137 content in milk originated mostly from nuclear weapon tests in the period 1945 to 1962, and to a lesser degree from Chernobyl nuclear accident in 1986. 3. The content of K-40 in milk has not changed significantly over the investigated period, but its level was not the same at all sampling locations. 4. The ratio of the impact of investigated radionuclides on man obtained from the samples of milk in the territory of Croatia is: 90 Sr : 137 Cs : 40 K = 1 : 2 : 5. (author)

  13. Surface Decontamination Studies of Cs-137 and Sr-85 Using Polymer Gel

    International Nuclear Information System (INIS)

    Pham, L.; Nguyen, C.; Nguyen, L.

    2015-01-01

    Strippable polymer coating is one of the methods for effective surface decontamination to remove isotopes on the contaminated surface. This method is applying in nuclear facilities on the World. In this paper, we present the results obtained in our laboratory from product the polymer coating to apply to remove radioisotopes of "1"3"7Cs and "8"5Sr from surface of glass, stainless steel, mild steel, ceramic, PVC plastic. This polymer gel solution consist of water soluble polymer preferably polyvinyl alcohol (PVA), plasticizing agent (glycerine) and chelating agents, (citric acid) which can be sprayed or pasted on to contaminated surface. After some hours, these gel solutions was dried to form a strong thin film and it was easily peeled off from a contaminated surface with the radioactive isotopes and can be disposed off as radioactive solid waste. In this study infrared spectrophotometry technique was used to examine the interaction of the cesium and strontium ions with polyvinyl alcohol (PVA), polymer gel and the results of the study were also presented. The results showed that decontamination efficiency of "1"3"7Cs and "8"5Sr strongly depended on property, porosity and smoothness of the contaminated surface and obtained from 95-99% on glass and stainless steel, ceramic and PVC plastic surfaces. The decontamination efficiency also depended on activity and coating thickness. Optimization of film thickness is around 0.2 mm. Decontamination efficiency of Polymer gel were compared with Decongel 1101 (product from USA) on surfaces. IR spectra studies indicated that Cs and Sr ions interacted with PVA and citric acid in Polymer gel through cacboxyl (C = O) group. Polymer gel could remove of "1"3"7Cs and "8"5Sr better than PVA gel does because of citric acid, which can form chelating complex with Cs and Sr ion. (author)

  14. Development of Composite Adsorbents for LLW Treatment and Their Adsorption Properties for Cs and Sr - 13127

    Energy Technology Data Exchange (ETDEWEB)

    Susa, Shunsuke; Mimura, Hitoshi [Dept. of Quantum Science and Energy Engineering, Graduate School of Engineering, Tohoku University, Aramaki-Aza-Aoba 6-6-01-2, Sendai, 980-8579 (Japan); Ito, Yoshiyuki; Saito, Yasuo [Nuclear Science and Engineering Directorate, Japan Atomic Energy Agency, 2-4 Shirakata Shirone, Naka-gun, Ibaraki, 319-1195 (Japan)

    2013-07-01

    In this study, the composite adsorbents (KCoFC-NM (NM: natural mordenite), KCoFC-SG (SG: porous silica gel), AMP-SG and so on) were prepared by impregnation-precipitation methods. As for the distribution properties, the largest K{sub d,Cs} value of 3.8 x 10{sup 4} cm{sup 3}/g was obtained for KCoFC-SG (Davi.) composite. KCoFC-SG (NH, MB5D) and T-KCFC also had relatively large K{sub d,Cs} values above 1.0 x 10{sup 4} cm{sup 3}/g. The uptake rate of Cs{sup +} ions was examined by batch method. KCoFC-SG (NH, MB5D) and AMP-SG (Davi.) had relatively large uptake rate of Cs{sup +}, and the uptake attained equilibrium within 1 h. The maximum uptake capacity of Cs{sup +} ions was estimated to be above 0.5 mmol/g for KCoFC-NM and KCoFC-CP composites. KCoFC-X composite had a relatively large uptake capacity of Cs{sup +} ions (0.23 mmol/g > 0.17 mmol/g (T-KCFC)) and this composite also had a selectivity towards Sr{sup 2+} ions; KCoFC-X is effective adsorbent for both Cs{sup +} and Sr{sup 2+} ions. The largest value of K{sub d,Sr} was estimated to be 218 cm{sup 3}/g for titanic acid-PAN. Titanic acid-PAN had the largest uptake rate of Sr{sup 2+} ions, and the uptake attained equilibrium within 8 h. Adsorbability of other nuclides was further examined by batch method. All adsorbents had adsorbability for Rb{sup +} and RuNO{sup 3+} ions. KCoFC-SG (NH), KCoFC-CP and T-KCFC had higher selectivity towards Cs{sup +} than other adsorbents; these adsorbents had adsorbability to Cs{sup +} ions even in the presence of Ba{sup 2+}, Ca{sup 2+} and Mg{sup 2+} ions. The separation factor of K{sub d,Sr}/K{sub d,Ba} for titanic acid-PAN was about 1, indicating that the K{sub d,Sr} for titanic acid-PAN tends to decrease with Ba{sup 2+} concentration. As for the breakthrough properties, the largest 5 % breakpoint and 5 % breakthrough capacity of Cs{sup +} ions were estimated to be 47.1 cm{sup 3} and 0.07 mmol/g for the column of KCoFC-SG (NH), respectively. The order of 5 % breakthrough capacity

  15. The radiation chemistry of the Cs-7SB modifier used in Cs and Sr extraction

    International Nuclear Information System (INIS)

    Swancutt, Katy L.; Cullen, Thomas D.; Mezyk, Stephen P.; Elias, Gracy; Bauer, William F.; Peterman, Dean R.; Riddle, Catherine L.; Ball, R. Duane; Mincher, Bruce J.; Muller, James J.

    2011-01-01

    The compound 1-(2,2,3,3,-tetrafluoropropoxy)-3-(4-sec-butylphenoxy)-2-propanol, also called Cs-7SB, is used as a solvent modifier in formulations containing calixarenes and crown ethers for cesium and/or strontium extraction from nuclear waste solutions. The compound solvates complexes of both metals and concentration decreases result in lowered extraction efficiency for both. The use of Cs-7SB in nuclear solvent extraction ensures that it will be exposed to high radiation doses, and thus its radiation chemical robustness is a matter of interest in the design of extraction systems employing it. The behavior of the compound in irradiated solution, both in the presence and absence of a nitric acid aqueous phase was investigated here using steady state and pulsed radiolysis techniques. The rate constants for the aqueous reactions of Cs-7SB with H, OH, NO 3 and NO 2 radicals are reported. UPLC-UV-MS results were used to identify major products of the radiolysis of Cs-7SB in contact with nitric acid, and revealed the production of hydroxylated nitro-derivatives. Reaction mechanisms are proposed and it is concluded that the aryl ether configuration of this molecule makes it especially susceptible to nitration in the presence of radiolytically-produced nitrous acid. Fluoride yields are also given under various conditions.

  16. Migration and chemical extractability of 137Cs and 90Sr in Swedish long-term experimental pastures

    International Nuclear Information System (INIS)

    Forsberg, S.; Strandmark, M.

    1999-01-01

    Vertical migration and chemical extractability were studied on two experimental pastures, a sandy soil and a clay soil, contaminated with 137 Cs and 90 Sr in 1961. Migration was studied by measuring the total nuclide content in soil samples to 55 cm depth, chemical extractability by sequential extraction. Both 137 Cs and 90 Sr were found at all depths in both soils, and 90 Sr had moved deeper than 137 Cs. 137 Cs was mainly found in the upper 10 cm, and no difference was seen between clay and sandy soil, due to retention in the root mat of the sandy soil. 90 Sr had moved deeper in sandy than in clay soil, the reason being the higher exchange capacity of the clay soil. Sequential extractions showed that 90 Sr was much more extractable than 137 Cs. 96-98% of 137 Cs was found in the HNO 3 and residual fractions. 137 Cs was more extractable in the sandy soil than in clay, and in the sandy soil the extractability of 137 Cs increased slightly with depth. Regarding 90 Sr, 63-75% was found in the easily exchangeable fractions, the higher figure was in clay soil. A large proportion, 18-30%, was extracted in the reducible fraction, showing that availability of 90 Sr might increase under reducing conditions. (au)

  17. Transfer factors of 137Cs and 90Sr from soil to some trees in Syria

    International Nuclear Information System (INIS)

    Al-Oudat, M.; Al-Asfary, A. F.; Mukalati, H.; Hamwi, A.; Kanakri, S.

    2004-12-01

    The transfer factor of Cs 137 and 90 Sr from contaminated soil (Aridisol = Yermosol according to FAO - UNESCO) to some common trees (olive, apricot, grape, pine, apple and lemon) were investigated under field condition for 3 to 6 years. There were large variation in transfer factors values among tree species, and between different parts of tree. The values in fruits for 137 Cs were: 0.011 (highest) in Apricot, 0.0071 in olive, and 0.0025 in vine, and about 0.0012 in olive oil (lowest). The mean transfer factor of 137 Cs in the one year old leaves and stems, ranged between 0.011 and 0.0093 in lemon (highest) and 0.0016 and 0.0015 in pine (lowest). The transfer factor values of 90 Sr were much higher than that of 137 Cs, they were in fruits: 0.13 in apricot, 0.093 in olive, and 0.075 in vine and 0.0053 in olive oil. The transfer factors values of 90 Sr ranged in one year old leaves between 2.89 (apple) and 0.1 (pine), while they ranged in one year old stems between 1.91 (apricot) and 0.16 (pine). The transfer factor of both 137 Cs and 90 Sr decrease in most trees parts with time especially in the one year old leaves, due to aging effects. The transfer factor values of 137 Cs and 90 Sr were lower than that reported for other areas. This might be due to the physical and chemical properties of the soil, where the soil used had a loamy clay structure with high ph (7.8) and high CEC (25.9 meq/100g), exchangeable potassium (1.6 meq/100g) and calcium (14.9 meq/100g), further more, climatic condition in the area, like high light intensity, high temperature and low air humidity, can lead to decrease the uptake of both 137 Cs and 90 Sr. (Authors)

  18. Sequential separation of cs, ca and ba for 90sr assessment

    International Nuclear Information System (INIS)

    Dianu, M.; Bucur, C.

    2015-01-01

    A two-steps chemical treatment technique for strontium assessment from aqueous samples is described in this paper. The method was applied to simulated samples containing stable elements of Ni, Cs, Ca, Ba, Mn, Fe, Co and Eu. The transition elements (Ni, Mn, Fe, Co, Eu) were precipitated as hydroxides, followed by alkaline-earth metals separation (Ca, Ba) as carbonates. Finally, the Sr was purified by extraction chromatography using Triskem International Sr resin. The strength of Sr sorption in nitric acid increases with increasing acid concentration, and the optimal bonding strength is achieved in 8 M HNO3. The combination of successive precipitations with extraction chromatography for complete removal of other interferences from Sr matrix leads to good recovery and decontamination factor values. (authors)

  19. 90Sr and 137Cs in environmental samples from Dolon near the Semipalatinsk Nuclear Test Site.

    Science.gov (United States)

    Gastberger, M; Steinhäusler, F; Gerzabek, M H; Hubmer, A; Lettner, H

    2000-09-01

    The (90)Sr and (137)Cs activities of soil, plant, and milk samples from the village of Dolon, located close to the Semipalatinsk Nuclear Test Site in Kazakhstan, were determined. The areal deposition at the nine sampling sites is in the range of sites both nuclides mainly have remained in the top 6 cm of the soil profiles; at others they were partly transported into deeper soil layers since the deposition. For most of the samples the (90)Sr yield after destruction of the soil matrix is significantly higher than after extracting with 6 M HCl indicating that (90)Sr is partly associated with fused silicates. The low mean (90)Sr activity concentrations of vegetation samples (14 Bq kg(-1) dw) and milk samples (0.05 Bq kg(-1) fw) suggest that this has favorable consequences in terms of limiting its bioavailability.

  20. Specific 137Cs and 90Sr accumulation in living soil cover plants of forest cenoses

    International Nuclear Information System (INIS)

    Ermakova, O.O.; Kuz'mich, O.T.; Kazej, A.P.

    2000-01-01

    Observations of the radionuclide content in 38 species of living soil cover plants were carried out in Pinetum myrtillosum, pleuroziosum; Quercetum pteridiosum; Betuletum myrtillosum; Glutinoso-Alnetum filipendulosum, Glutinoso-Alnetum. Radiological monitoring for the 137 Cs and 90 Sr content in living cover plants of forest cenosis in Belarus allows 137 Cs and 90 Sr accumulation to be predicted for the plants of lower circles of forest cenosis. a obtained one can notice that the radionuclide accumulation intensity depends on the contamination density of the accumulation soil layer, forest growing conditions, species and first of all on the weather conditions of the year of observation. Unfavourable conditions (drought) lead to an increase in 137 Cs accumulation by a factor of 3-5 depending on the plant species. The maximum values was obtained in ferns which grow under all the controlled forest growing conditions. The species specific character of 137 Cs and 90 Sr accumulation is due to their ecological-physiological peculiarities. The relationship was found between the caesium-137 accumulation and macro element quantity in overground organs of living soil cover plants. (authors)

  1. Reactive transport of Sr, Cs and Tc through a column packed with fracture-filling material

    International Nuclear Information System (INIS)

    Cui, D.; Eriksen, T.

    1998-01-01

    The migration behaviour of the fission products 90 Sr, 137 Cs and 99 Tc in a granite fracture-groundwater system was studied in column experiments using crushed Stripa granite fracture-filling material (125-250 μm) as a sorbent. Based on breakthrough curves of Sr 2+ , Cs + , TcO 4 - and anthraquinonsulphonate, the distribution ratio K d (cm 3 /g) values for Sr 2+ and Cs + were estimated to be 1.5 and 2 respectively; non-sorbing behaviour of TcO 4 - under oxic conditions was observed. The diffusion of Sr 2+ in the material is shown to be a kinetic-controlling step in the desorption process that followed the initial leaching. Under reducing conditions, it was found that TcO 4 - was reduced to TcO 2 .nH 2 O(s) by the Fe(II)-containing fracture-filling material and Tc(IV) aq was rapidly sorbed by the material. This observation proves that the migration of technetium under reducing conditions in deep groundwater systems will not only be controlled by the solubility of TcO 2 . nH 2 O(s) and the speed of groundwater flow but also by the rapid sorption of Tc(IV) aq on all available mineral surfaces. (orig.)

  2. 137Cs and 90Sr distribution in edible mushrooms at the territory of the Lithuanian SSR

    International Nuclear Information System (INIS)

    Dauskurdis, S.I.; Tamulenajte, O.P.; Nedvetskajte, T.N.

    1989-01-01

    Results of studying 90 Sr and 137 Cs content in edible mushrooms in Lithuania before and after the Chernobyl accident (1984-1986) are presented. It is shown that after accident release in 1986 mushroom contamination with cesium isotopes increased about 4 times as compared to 1985 and 90 Sr activity preserved the same level. Radioisotope accumulation in mushrooms after the Chernobyl accident is studied depending on the mechanical composition of soil, pH and Ca quantity. It is ascertained that in carbonate, alkaline, reach with Ca and K soils 90 Sr and 137 Cs mobility is reduced and their absorption by mushroom is weakened. In light by mechanical composition (sandy), depleted by Ca soil 90 Sr arrival to mushrooms is 2.4 times higher than in soils with high Ca content. The quantity of water-soluble 90 Sr is maximal in soil with low pH and minimal content of exchange Ca. Radioactive contamination of mushrooms depends on the terrain relief and type of mushrooms. It is shown that radioactive contamination of mushrooms in 1986 did not exceede the admissible standard. 7 refs.; 4 figs.; 2 tabs

  3. Experimental studies of Cs, Sr, Ni, and Eu sorption on Na-illite and the modelling of Cs sorption

    International Nuclear Information System (INIS)

    Poinssot, C.; Baeyens, B.; Bradbury, M.H.

    1999-08-01

    A natural illite (illite du Puy) was purified and converted to the homo-ionic Na-form. The conditioned Na-illite was characterised in terms of its mineralogy, chemical inventory and physico-chemical properties. The structural formula was determined from energy dispersive spectroscopic analyses (SEM/TEM-EDS) and bulk chemistry measurements. A cation exchange capacity of 127 meq kg -1 was determined by the 22 Na isotope dilution method at neutral pH. The Na-CEC was also measured as a function of pH. The stability of Na-illite as a function of pH in the range between 3 and 6 was investigated. At low pH values partial dissolution of the illite occurs releasing the structural elements Al, Si, Mg, and K into solution. The presence of Ca and Sr in solution was interpreted as being due to desorption from cation exchange sites. All of these elements are also present at neutral pH but at considerably lower levels. Such effects cannot be avoided and must be considered in the interpretation of the sorption measurements. The main focus of the experimental work presented here is on the sorption behaviour of Cs, Sr, Ni and Eu on conditioned Na-illite as a function of NaClO 4 background electrolyte concentration (0.1 and 0.01 M), nuclide concentration and pH in the range between 3 and 11. Sorption edge data (R d versus pH) and sorption isotherms (quantity of nuclide sorbed versus equilibrium nuclide concentration) are presented for these four elements. Prior to beginning these experiments, sorption kinetics were measured. The broad based pool of sorption measurements generated from this work will provide the source data sets for subsequent modelling. So far only the Cs sorption measurements have been modelled. A two site cation exchange model was developed to describe the sorption of Cs over the whole range of experimental conditions. The two site types were termed 'frayed edge sites' (FES, high affinity/low capacity) and 'type II sites' (low affinity/high capacity). Selectivity

  4. 137Cs and 90Sr in the water of the ChNPP cooling pond

    Directory of Open Access Journals (Sweden)

    V. V. Kanivets

    2014-12-01

    Full Text Available Results of long-term observations on 137Cs and 90Sr concentration in water mass of the ChNPP Cooling Pond are presented. Drastic transformation of the intrinsic trend in changes with time of averaged radionuclides con-tent in water is clearly demonstrated alongside with the spatial heterogeneity of radioactive contamination of water body. The cycling character of seasonal changes of 137Cs activity concentration in water is being linked to hydrochemical, temperature and oxygen regimes of the Cooling Pond.

  5. Uncertainties in estimating the {sup 90}Sr and actinides inventory in SFR 1; Osaekerheter vid uppskattning av Sr-90 och aktinidinventariet i SFR 1

    Energy Technology Data Exchange (ETDEWEB)

    Ingemansson, Tor [ALARA Engineering AB, Skultuna (Sweden)

    2000-04-01

    SFR-1 is a facility for disposal of low and intermediate level radioactive waste. The uncertainty in estimation of the activity accumulated in different cleaning filters, originating in the Swedish BWR-, PWR-reactors and CLAB - the Central interim storage facility for spent nuclear fuel - has been analyzed to be 10 - 14%, depending on the methods used for measuring the activity at the power plants. Other waste or scrap contribute with approx. 1.5% of the total amount of actinides and {sup 90}Sr. The uncertainty in this fraction is about 20%. The uncertainties are surprisingly small, and explain the good agreement between estimates made with different methods.

  6. Effect of liming on the behaviour of 90Sr and 137Cs in a lake ecosystem

    International Nuclear Information System (INIS)

    Outola, Iisa; Rask, Martti

    2011-01-01

    Liming of lakes is considered one possible remedial action to reduce the accumulation of radionuclides into fish in the case of a radiological accident. These responses were tested in field conditions in a small acidified lake that was divided into two parts: one limed with CaCO 3 and the other half left as an unlimed control. The transfer of 90 Sr from water into fish decreased on average by 50% during the first year after liming. However, at the same time the 90 Sr concentration in water increased, reaching a maximum within 6 months after liming. Approximately 50% more 90 Sr was detected in water in the limed part of the lake than on control side during the first year. 90 Sr was most probably released from the sediment as the Ca concentration and pH of the water increased. As a result of these two processes, which counterbalanced each other (increased release of 90 Sr into water from sediment and decreased transfer of 90 Sr from water into fish), the 90 Sr concentration in fish did not notably differ between the limed and control sides of the lake. Liming may only be suitable as a remedial action if carried out immediately after a radiological accident, before significant amounts of radionuclides have been deposited in lake sediments. In the case of 137 Cs, the effect of liming was less pronounced. 137 Cs activity concentration in water increased in the first year by 20% and uptake by fish decreased by 20%. - Highlights: → Acidified lake was divided into two parts: one limed with CaCO 3 and the other half left as an unlimed control. → The transfer of 90 Sr from water into fish decreased by 50% during the first year after liming. → At the same time liming increased the 90 Sr concentration in the water by 50%. → The increased amount of 90 Sr in water is assumed to have originated from the lake sediments. → The 90 Sr concentration in fish remained relatively unchanged.

  7. Transfer of 226Ra, 85Sr and 137Cs from milk to milk products

    International Nuclear Information System (INIS)

    Al-Masri, M.S.; Nashawati, A.; Amin, Y.; Al-Akel, B.

    2006-01-01

    Transfer of 226 Ra, 85 Sr and 137 Cs from cow and sheep milk to various Syrian dairy products has been evaluated. Dairy products include Kashkivan cheese, braided cheese, Haloom cheese, Sircassian cheese, liquid cheese, native cheese, cottage, thick yogurt, butter and milk cream. The results showed that the percentage of 226 Ra, 85 Sr and 137 Cs transferred from cow milk to milk cream (P t = food processing retention factor x processing efficiency x 100%) has reached 32%, 16% and 7%, respectively. Butter and liquid cheese were found to have the lowest percentage of transferred 226 Ra, 85 Sr and 137 Cs. Most of the obtained P t values of the studied radionuclides in thick yogurt were relatively low in spite of the high processing efficiencies of thick yogurt. Moreover, the transfer, P t , of the studied radionuclides from cow milk to the prepared cheese was higher than those values determined for sheep milk. This is due to differences in chemical compositions of each type of milk. On the other hand, the treatment of Native cheese, most commonly consumed cheese in Syria, with different concentrations of NaCl solutions showed that 137 Cs was completely removed from cheese soaking in 5% NaCl solution (soaking time of 48 hours), while 40% of 226 Ra and 80% of 85 Sr were also decontaminated using 0-2.5% NaCl solutions and soaking time of 48 hours. Based on the obtained results, industrialization processes of the dairy products that resulted the removal of radionuclides have been identified. (author)

  8. Discrepancies in the half-lives of 90Sr, 137Cs and 252Cf

    International Nuclear Information System (INIS)

    Rajput, M.U.; Mac Mahon, T.D.

    1990-01-01

    Recent reports have pointed out that significant discrepancies exist in published half-life data for 90 Sr, 137 Cs and 252 Cr, amongst others. These discrepancies make the estimation of evaluated half-lives for these isotopes difficult and contentious. This paper reviews the current situation, takes into account recently available data and attempts to derive recommended half-lives and associated uncertainties for the three isotopes. 37 refs, 3 tabs

  9. 137 Cs and 90 Sr in marine samples from Brazilian southern coast

    International Nuclear Information System (INIS)

    Godoy, Jose Marcus; Carvalho, Zenildo L.; Pereira, Jose Carlos A.; Pereira, Wagner S.; Ferreira, Ana Cristina M.; Fernandes, Flavio C.; Danelon, Olga M.

    2000-01-01

    In this paper are presented the results related to monitoring program of Cs-137 and Sr-90 distribution in marine ecosystem from Brazilian southern coast. This program is performed together Instituto de Radioprotecao e Dosimetria (IRD/CNEN/MCT) and the Instituto de Estudos do Mar Almirante Paulo Moreira, aiming the evaluation of artificial radionuclide contents present in marine samples. The program, have started in experimental character in 1996 and became a routine program, carried out yearly

  10. {sup 90}SR and {sup 137}CS distribution in organisms of wild small mammals (Chernobyl zone)

    Energy Technology Data Exchange (ETDEWEB)

    Goryanaya, J.U.; Bondarkov, M.; Gaschak, S.; Maksimenko, A.; Barchuk, R.; Martynenko, V.; Shulga, A. [Chornobyl Center for Nuclear Safety, Radioactive Waste and Radioecology, International Radioecology Laboratory, Slavutych (Ukraine)

    2004-07-01

    The distribution of {sup 90}Sr and {sup 137}Cs content in tissues of small rodent mammals has been studied in detail. It was determined that for a vole Microtus the largest ratio values of {sup 137}Cs concentration in organs to one in muscles are in skin (2.02{+-}0.45) and kidneys (1.57{+-}0.29), in other tissues they are much lower. The comparison of {sup 137}Cs specific concentration in tissues with their size (mass index) has shown that the major portion of the total radionuclide concentration in the animal body is in the bone and muscle tissues aggregate (44.1 {+-} 2.8%) and in skin (24.8 {+-} 2.5%). The total content of {sup 137}Cs in a gastrointestinal tract is about 20-25%, but nevertheless, it may be assumed that it is strongly dependent on the radioactivity of food. Preliminary data show that other species of genus Microtus can have another pattern of distribution. A more detailed research was conducted for the bank vole (Clethrionomys glareolus), {sup 90}Sr and {sup 137}Cs contents in tissues were calculated. {sup 137}Cs distribution corresponds with the tissues portion in the animal's body mass (% of total content): the most in muscles 38.3, gastrointestinal tract 21.3, skin 16.7; the least in eyes 0.23, spleen 0.33, heart 0.74. The comparison of the activity concentration in each tissue with the average concentration of {sup 137}Cs in the whole body presented more evident differences between the tissues. The highest radionuclide concentration is in skin (1.48), in a slightly less degree in spleen (1.22) and eyes (1.20). The {sup 90}Sr distribution in the vole body is uneven up to 83.4% of the overall content is in bone tissues, in muscle -6.8, gastrointestinal tract - 4.2, skin - 3.9, in other tissues - 0.2-0.5%. In comparison with {sup 90}Sr average activity in the body: skeleton -10.9, eyes -1.3, spleen -1.02, and their values are much higher than in other tissues and organs. (author)

  11. Accumulation of /sup 90/Sr and /sup 137/Cs in lichens under experimental conditions

    Energy Technology Data Exchange (ETDEWEB)

    Nifontova, M G [AN SSSR, Sverdlovsk. Inst. Ehkologii Rastenij i Zhivotnykh

    1976-01-01

    A study was made of the accumulation from aqueous media of two long-lived radionuclides---/sup 90/Sr and /sup 137/Cs---by the thalluses of eight species of lichens of different ecological and morphological groups (soil bushy lichens and foliated forms; epiphytic bushy and foliated; epilytic foliated). Fhe efficiency of accumulation of radionuclides by the thalluses was determined from the accumulation coefficient (KN) (koehfitsient nakopleniya). There was a distinct difference in the radionuclide accumulation by the different species of lichens. Based on their radionuclide accumulation, the lichens were divided into three groups. It was shown that not only do different species of lichens differ in their accumulation of the same radionuclide, but also the thalluses of the same species are not the same in the sorption of different radionuclides. However, on an average, the bushy forms of lichens accumulated /sup 90/Sr and /sup 137/Cs more than the leafy types. The lichens studied may be arrangd according to their accumulation of /sup 90/Sr: epiphytes > soil types > epilytes, or their /sup 137/Cs accumulation: soil types > epilytes > epiphytes.

  12. Transfer factors of 137Cs and 9Sr from soil to trees in arid regions

    International Nuclear Information System (INIS)

    Al-Oudat, M.; Asfary, A.F.; Mukhalallti, H.; Al-Hamwi, A.; Kanakri, S.

    2006-01-01

    Transfer factors of 137 Cs and 9 Sr from contaminated soil (Aridisol) to olive, apricot trees and grape vines were determined under irrigated field conditions for four successive years. The transfer factors (calculated as Bq kg -1 dry plant material per Bq kg -1 dry soil) of both radionuclides varied among tree parts and were highest in olive and apricot fruits. However, the values for 9 Sr were much higher than those for 137 Cs in all plant parts. The geometric mean of the transfer factors in olives, apricots and grapes were 0.007, 0.095 and 0.0023 for 137 Cs and 0.093, 0.13 and 0.08 for 9 Sr, respectively, and were negligible in olive oil for both radionuclides. The transfer factors of both radionuclides were similar to, or in the lower limits of, those obtained in other areas of the world. This could be attributed to differences in soil characteristics: higher pH, lower organic matter, high clay content, and higher exchangeable potassium and calcium

  13. Vertical distribution of 90Sr and 137 Cs in uncultivated soil in three localities of central Bohemia

    International Nuclear Information System (INIS)

    Schlesingerova, E.; Hejnova, P.; Tecl, J.; Mirchi, R.; Setrna, L.; Macurova, L.

    2005-01-01

    The purpose of this work was study the vertical distribution of 90 Sr and 137 Cs in uncultivated soils. The radionuclide contents in different soil layers and the cumulative deposition of radionuclides at the study sites were to be established with a view to possible identification of their sources. The present paper investigated the vertical distribution of 90 Sr and 137 Cs in uncultivated soil samples in central Bohemia and inventory of these radionuclides at representative sampling sites. These data provide the information about the availability, movement and environmental behaviour of these important radionuclides in the study region. The cumulative deposition of 90 Sr at sites 1, 2 and 3 were found of 700, 1390 and 970 Bq/m 2 , respectively, The cumulative deposition of 137 Cs at sites 1, 2 and 3 were found of 260, 510 and 10000 Bq/m 2 , respectively. The obtained values of 9S r are about 47% lower than the value of UNSCEAR inventories, but our average value of 137 Cs (3590 Bq/m 2 ) agree with the cumulative deposition of 137 Cs from the atmospheric nuclear tests in northern 40 grad - 50 grad temperate zone according UNSCEAR inventories. The radioactive decay should have reduced the reported 90 Sr and 137 Cs inventories in the northern hemisphere to 2190 Bq/m 2 and 3580 Bq/m 2 , respectively. The concentration of 90 Sr and 137 Cs increased proportionally to the SOM content in soil, but the difference of the degree of correlation among 90 Sr and 137 CS could be explained by the fact that SOM held 137 Cs more strongly than 90 Sr. 137 Cs showed very low mobility in soil profiles in undisturbed soils, therefore, it was concentrated in the upper 10 cm of the soils. Although the concentration of 90 Sr increased with organic content through an anion exchange reaction, which is enhanced by SOM keeping high cationic exchange capacity, the retention of Sr was relatively weak in contrast to Cs. It is related with high mobility of Sr that is a member of group II in the

  14. Accumulation of Cs, Sr into leaves and grain of winter wheat under act of N, Zn, Li, Na

    International Nuclear Information System (INIS)

    Grodzinsky, D.; Tkatchuk, K.; Zhmurko, N.; Bogdan, T.; Guralchuk, Zh.

    1998-01-01

    The experiments were carried out on cv Lutencens 7 winter wheat grown on grey forest soil. In order to study the influence of nitrogen on Cs and Sr accumulation, a background of P60 K60 added in autumn different doses of nitrogen (30, 60, 120 kg/ha) were applied in spring. The influence of micronutrients on Cs and Sr accumulation was studied by adding 3 kg/ha Zn and 2 kg/ha Li to the soil under ploughing on background of N60 P60 K60. Besides the foliar application with 0.05% Na 2 SO 4 was carried out. Cation content (Cs, Sn, Zn, Li, Na) in soil and plant organs was determined by atomic absorption spectrophotometry. The Cs, Sr content in control plant leaves made up 15.0 and 21.0 mg per g of dry matter at the early stages of plant development. As the plants aged, the content of those elements in the leaves decreased strongly (3-4 times). At early stages of plant development, nitrogen caused an 8.9-11% increase in the Cs content of the leaves. At the stages of heading to grain filling, the Cs content increase was only observed at a high nitrogen dose, whereas low nitrogen doses had no effected on Cs accumulation in leaves. In should be noted that nitrogen (N60 and N120) decreased the Cs content in grain by 32-33%. As for the Sr content of grain, this was 3 to 4-fold less than that of Cs. Nitrogen had no effected on the Sr content of grain. Zn and Li addition to soil as well as foliar nutrition with Na had a different effect on the Cs and Sr content of winter wheat leaves and grain. Addition of Li decreased the Cs and Sr content of old leaves by 13% and 25% respectively. Addition of Zn and Na decreased the Sr content of old leaves but had no effect on the Cs content. Zn, Na and Li reduced the Sr content in grain also, viz. by 16,11 and 7% respectively. Thus the research has demonstrated the possibility of regulating Cs and Sr accumulation in the above-ground organs of winter wheat plants

  15. Concentrations of /sup 90/Sr and /sup 137/Cs rain and dry fallout, milk and service water in Aichi Prefecture

    Energy Technology Data Exchange (ETDEWEB)

    Ohnuma, Shoko; Kondou, Fumio; Chaya, Kunio (Aichi Prefectural Inst. of Public Health, Nagoya (Japan))

    1989-03-01

    The investigation by radioactivation analysis was carried out on the Sr-90 and Cs-137 concentrations in fallout, milk and source water and tap water from 1977 to 1987. The variation of the monthly and yearly amounts of Sr-90 and Cs-137 fallouts agreed well, and those have decreased for the last 11 years though affected by the nuclear experiments in China. The effect of the Chernobyl-4 accident on April 26, 1986 appeared conspicuously in the Cs-137 fallout, and the monthly fallout in May, 1986 was 3.50 mCi/km/sup 2/. As to the Sr-90 and Cs-137 concentrations in milk and service water, only the Cs-137 concentration in milk was correlated with the course for years before the Chernobyl-4 accident. The effect of the Chernobyl-4 accident was conspicuous in the Cs-137 concentration similarly to the case of fallout. In this case, in the measurement of service water after a half year, the data returned to the normal value, but in the case of milk, the decrease was slow. The method of investigation, the monthly and yearly fallout of Sr-90 and Cs-137, the Sr-90 and Cs-137 concentrations in milk and service water are reported. (K.I.).

  16. Separation of CsCl and SrCl_2 from a ternary CsCl-SrCl_2-LiCl via a zone refining process for waste salt minimization of pyroprocessing

    International Nuclear Information System (INIS)

    Shim, Moonsoo; Choi, Ho Gil; Yi, Kyung Woo; Hwang, Il Soon; Lee, Jong Hyeon

    2016-01-01

    The purification of LiCl salt mixture has traditionally been carried out by a melt crystallization process. To improve the throughput of zone refining, three heaters were installed in the zone refiner. The zone refining method was used to grow pure LiCl salt ingots from LiCl-CsCl-SrCl_2 salt mixture. The main investigated parameters were the heater speed and the number of passes. A change in the LiCl crystal grain size was observed according to the horizontal direction. From each zone refined salt ingot, samples were collected horizontally. To analyze the concentrations of Sr and Cs, an inductively coupled plasma optical emission spectrometer and inductively coupled plasma mass spectrometer were used, respectively. The experimental results show that Sr and Cs concentrations at the initial region of the ingot were low and reached their peak at the final freezing region of the salt ingot. Concentration results of zone refined salt were compared with theoretical results yielded by the proposed model to validate its predictions. The k_e_f_f of Sr and Cs were 0.13 and 0.11, respectively. The decontamination factors of Sr and Cs were 450 and 1650, respectively. - Highlights: • The LiCl-CsCl-SrCl_2 salt ingot was purified by zone refining technique to minimize waste salt. • The concentration distribution of Cs and Sr were analyzed by mass transfer equation. • The decontamination factors of Cs and Sr were 1600 and 450 respectively in case of 60% of recovery yield.

  17. Separation of CsCl and SrCl{sub 2} from a ternary CsCl-SrCl{sub 2}-LiCl via a zone refining process for waste salt minimization of pyroprocessing

    Energy Technology Data Exchange (ETDEWEB)

    Shim, Moonsoo [Graduate School of Energy Science and Technology, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Choi, Ho Gil; Yi, Kyung Woo; Hwang, Il Soon [Graduate School of Seoul National University, 1 Gwanak-ro, Gwanak-gu, Seoul 08826 (Korea, Republic of); Lee, Jong Hyeon, E-mail: jonglee@cnu.ac.kr [Graduate School of Energy Science and Technology, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Graduate School of Department of Advanced Materials Engineering, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of); Rapid Solidified Materials Research Center, Chungnam National University, 99 Daehak-ro, Yuseong-gu, Daejeon, 34134 (Korea, Republic of)

    2016-11-15

    The purification of LiCl salt mixture has traditionally been carried out by a melt crystallization process. To improve the throughput of zone refining, three heaters were installed in the zone refiner. The zone refining method was used to grow pure LiCl salt ingots from LiCl-CsCl-SrCl{sub 2} salt mixture. The main investigated parameters were the heater speed and the number of passes. A change in the LiCl crystal grain size was observed according to the horizontal direction. From each zone refined salt ingot, samples were collected horizontally. To analyze the concentrations of Sr and Cs, an inductively coupled plasma optical emission spectrometer and inductively coupled plasma mass spectrometer were used, respectively. The experimental results show that Sr and Cs concentrations at the initial region of the ingot were low and reached their peak at the final freezing region of the salt ingot. Concentration results of zone refined salt were compared with theoretical results yielded by the proposed model to validate its predictions. The k{sub eff} of Sr and Cs were 0.13 and 0.11, respectively. The decontamination factors of Sr and Cs were 450 and 1650, respectively. - Highlights: • The LiCl-CsCl-SrCl{sub 2} salt ingot was purified by zone refining technique to minimize waste salt. • The concentration distribution of Cs and Sr were analyzed by mass transfer equation. • The decontamination factors of Cs and Sr were 1600 and 450 respectively in case of 60% of recovery yield.

  18. Distribution of 90Sr and 137Cs in Arctic soil profiles polluted by heavy metals

    International Nuclear Information System (INIS)

    Puhakainen, M.; Heikkinen, T.; Steinnes, E.; Thorring, H.; Outola, I.

    2005-01-01

    Effects of industrial pollution on the behaviour of radionuclides in spruce forest ecosystems were studied along a gradient from of a copper-nickel smelter in Monchegorsk, NW Russia. A reference site was situated in Lapland, Finland, 152 km west of Monchegorsk. Most of the total 137 Cs activity in soil was in mineral (E and B) horizons, except at the reference site where the major part was still in the organic surface layer. Most of the total 90 Sr activity still remaining in the soil profile was found in the surface layer, but the relative amount decreased with increasing level of industrial pollution. Pollutants from the smelter clearly affected the chemical speciation of radionuclides. Smaller amounts of exchangeable radionuclides were present in the organic surface layer at the most polluted sites. The decline of 137 Cs with decreasing distance from the smelter correlated strongly with a similar depletion in exchangeable K and Mg. Total concentrations of 137 Cs and 90 Sr showed high correlations with exchangeable cations, particularly in the E and upper B horizon. A sudden change in behaviour of 137 Cs in the lower B horizon may be associated with changes in clay mineralogy along the soil profile caused by weathering

  19. Distribution of 127Cs and 90Sr in southern part of Pyajyanne lake and in its catchment area

    International Nuclear Information System (INIS)

    Saksen, R.; Rantavaara, A.; Yaakkola, T.

    1998-01-01

    Slight increase in 90 Sr content from river discharges was observed in the near-the-surface layers og the Asikkalanselk bay of the Pyajanne lake in the years directly following the Chernobyl accident; later it remained almost runchanged, whereas 137 Cs concentration is decreasing. 90 Sr was identified in the bottoms at greater depth than 137 Cs. Radionuclides transport by small rivers from water catchment zones to Asikkalanselsk was studied in 1995-1997. It is established that greater part of 137 Cs is leached into the surface waters from swamped areas. The swamped soils are also characterized by higher degree of 90 Sr washing out. The role of 137 Cs and 90 Sr surface discharges from catchment as compared to radionuclide exchange with other parts of the lake, containing greater water volumes

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

    Science.gov (United States)

    Korobova, E.

    2012-04-01

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

  1. Sr2+ and Cs+ ion exchange properties of KLn(PO3)4: Ln = Ce and Eu

    International Nuclear Information System (INIS)

    Samatha, B.; Achary, S.N.; Tyagi, A.K.; Ramkumar, Jayshree; Chandramouleeswaran, S.

    2014-01-01

    With the aim to study the potential of layered phosphates as ion exchangers two stoichiometric compositions as KLn(PO 3 ) 4 with Ln = Ce and Eu were prepared by solid state reaction and characterized by powder X-ray diffraction method. The Cs + and Sr 2+ exchange properties of both materials were investigated using standard solutions of Sr 2 + or Cs + in low acidic aqueous medium

  2. 137Cs and 90Sr in Milk from the Zagreb Region

    International Nuclear Information System (INIS)

    Franulovic, I.; Kolar, M.; Petrinec, B.

    2013-01-01

    The Radiation Protection Unit of the Institute for Medical Research and Occupational Health in Zagreb is currently carrying out a program of radioactivity measurements and monitoring of the human environment in Croatia. Among other radionuclides this includes radiostrontium and radiocaesium in milk, which is a very sensitive indicator of the presence of fission products in the environment. Milk is also a very important foodstuff in the dietary habits of the Croatian population and represents a major source of potential radioactive contamination. This paper presents the results of the monitoring of 137Cs and 90Sr activity concentrations in milk for the year 2011. Activity concentrations of 90Sr ranged from 26.9 Bqm -3 to 59.5 Bqm -3 with a mean activity concentration of 50.6 Bqm -3 . The mean activity concentration for 137Cs was 199 Bqm -3 with a range from 21.1 Bqm -3 to 1940 Bqm -3 . The effective doses received from milk consumption were estimated for the adult population of the Zagreb region. The effective dose received from 90Sr uptake by milk consumption was 110 nSv. During 11 months of the year 2011, with the exception of August, the effective dose received from 137Cs uptake was 37.3 nSv, while the dose for 137Cs in August was 163 nSv. The effective dose for August was higher than the effective dose for the remaining 11 months. Continuous control and monitoring of radioactivity in food and the environment are needed to protect the population from the negative effects of ionizing radiation.(author)

  3. Distribution of {sup 90} Sr and {sup 137} Cs in vertical soil sections of the Chernobyl exclusion zone.; Raspredelenie form nakhozhdeniya {sup 90} Sr i {sup 137} Cs po vertikal`nym pochvennym razrezam Zony otchuzhdeniya ChAEhS.

    Energy Technology Data Exchange (ETDEWEB)

    Bondarenko, G N; Kononenko, L.V. [AN Ukrainskoj SSR, Kiev (Ukraine). Inst. Geokhimii i Fiziki Mineralov

    1994-12-31

    Water-soluble, exchangeable and acid-soluble (IM HCI) forms of {sup 90} Sr and {sup 137} Cs were determined in 15 layer-by-layer (1 cm) samples of podzolis and peaty soils from the Chernobyl exclusion zone taken in 1991 and 1992. Positions of centers of {sup 137} Cs and {sup 90} Sr supply as well as their water-soluble and exchangeable forms were estimated. The data obtained testify to deceleration of vertical migration of {sup 137} Cs in soils till the early 90th. The conclusion is made on evolution of dominating mechanisms of vertical migration of radionuclides. It consists in a decrease of the lessivage significance.

  4. Bio-geochemical behavior of 90Sr, 137Cs and 60Co in tropical soil

    International Nuclear Information System (INIS)

    Wasserman, M.A.; Gonzales Viana, A.; Bartoly, F.; Carvalho Conti, C. de; Janvrot Vivone, R.; Perez, V.; Wasserman, J.C.

    2004-01-01

    One manner to assess the bio-geochemical behavior of radionuclides in soils is the integration of experimental methods results obtained in the laboratory with results obtained in field experiments. In this work was used an alternative sequential chemical extraction protocol to evaluate mobility of radionuclides as a function of some physico-chemical conditions operationally defined: Slightly acidic phase: CH 3 COOH + CH 3 COONa 1:1, pH 4.7, shacked at room temperature; Easily reducible phase: NH 2 OH.HCl (0.1 M), pH 2, shacked at room temperature;Oxidizable phase: H 2 O 2 (30%) + HNO 3 , pH 2, CH 3 COONH 4 (1 M);shacked at room temperature; Alkaline phase: NaOH (0.1 M), pH 12, shacked at room temperature; Resistant phase: Aqua regia heated to 50 deg C / 30 min. The results obtained experimentally indicate the vulnerability of some Brazilian soils due to the higher radionuclide transfer to plant. Although it seems clear that it is difficult to identify which soil property will determine a given TF, the results of geochemical partition for 137 Cs, 90 Sr and 60 Co obtained in slightly acidic phase were very consistent with the TF data for reference plants or with some of the soil properties recognized in the specialized literature as related with mechanisms of sorption of Cs (e.g. exchangeable K, organic matter and iron oxides content), Co (e.g. manganese oxide) and Sr (pH and exchangeable Ca). The 137 Cs distribution in soil showed that Fe oxides are the main sink for this element in all type of soil and 16 years after contamination the 137 Cs the TF remains almost the same in Goiania soil. The 60 Co distribution in soil showed that Mn oxides are the main sink for this element in all type of soils and in the Nitisol, 5 years after contamination, the 60 Co was not detected as bioavailable (in the slightly acidic phase) neither detected in plant or were detectable with values very close to the detection limit. In the Nitisol, it is possible that reduction in 137 Cs

  5. 137Cs and 90Sr IN lizards of Semipalatinsk test site.

    Science.gov (United States)

    Panitskiy, А V; Lukashenko, S N; Kadyrova, N Zh

    2017-01-01

    The paper provides research results of 137 Cs and 90 Sr radionuclides concentrations in bodies of Lacertidae family lizards, inhabiting different parts of Semipalatinsk Test Site, and the parameters of these radionuclides' transfer into lizards' bodies. It shows that high activity concentration of radionuclides in lizards' bodies can be noticed if they live directly at locally contaminated areas. Since the distance from contaminated spots exceeds home range of the studied animals, no increased values of radionuclides' activity were found in the animal bodies. At some individual radioactively contaminated spots, very high activity concentrations of 90 Sr radionuclide up to 7.8 × 10 5  Bq kg -1 were found in lizards. So under certain conditions, lizards can significantly contribute to radionuclides redistribution in the natural environment. Mean concentration ratios (CR) of radionuclides were as follows: 137 Cs-6.2 × 10 -3 , 90 Sr-1.1 × 10 -2 . Copyright © 2016 Elsevier Ltd. All rights reserved.

  6. The mobility of 137Cs and 90Sr in agricultural soils in the Ukraine, Belarus, and Russia, 1991

    International Nuclear Information System (INIS)

    Salbu, B.; Oughton, D.H.; Ratnikov, A.V.; Zhigareva, T.L.; Kruglov, S.V.; Petrov, K.V.; Grebenshakikova, N.V.; Firsakova, S.K.; Astasheva, N.P.; Loshchilov, N.A.

    1994-01-01

    Results are presented from studies concerning the behavior of the Chernobyl-derived radionuclides 137 Cs and 90 Sr in soil-plant agricultural systems in the Ukraine, Belarus, and Russia during 1991. The sites, representing ploughed and natural pastures, were located at varying distances between 50 and 650 km and varying directions from the Chernobyl reactor site. The 137 Cs activity concentrations in the upper 0-5 cm soil layer ranged from 25-1,000 kBq m -2 and were higher in natural pastures as compared to ploughed pastures. For 90 Sr, activity levels ranged from 1.4-40 kBq m -2 , and the highest 90 Sr deposition was observed in the Gomel Region, Belarus. The highest 90 Sr: 137 Cs ratio was also observed in the Gomel soils, i.e., 15% as compared to between 0.72 and 7.4% in the other soils. The mobility of radionuclides was studied by means of sequential extraction. For all soils, between 60 and 95% of the 137 Cs was found to be strongly bound to soil components. In the Russian and Ukrainian soils, between 40 and 98% of the 90 Sr was found in the easily extractable fractions, and the distribution of 137 Cs and 90 Sr followed that of the naturally occurring stable isotopes of cesium and strontium. However, in the Gomel soils, between 20 and 50% of the 90 Sr was easily extractable and the distribution of 90 Sr within the extraction fractions did not follow that observed for stable strontium. These results are though to reflect the association of 90 Sr with fuel particles deposited in the Gomel Region. The mobility of 90 Sr is expected to increase with time (as the particles weather) in these soils. 24 refs., 14 figs., 3 tabs

  7. The uptake of Cs and Sr from soil to radish (Raphanus sativus L.)- potential for phytoextraction and remediation of contaminated soils

    International Nuclear Information System (INIS)

    Wang, Dan; Wen, Fangping; Xu, Changhe; Tang, Yunlai; Luo, Xuegang

    2012-01-01

    The 133 Cs and 88 Sr uptake by plant Raphanus sativus L. was studied during cultivation in outdoor potted-soil. The distribution, accumulation of 133 Cs, 88 Sr and the antioxidant responses in plants were measured after 30 and 60 days of cultivation. The results showed that the uptake capacity of radish for 88 Sr was far higher than that for 133 Cs when the concentration of 88 Sr was as the same as that of 133 Cs in the soil (The concentration of 88 Sr or 133 Cs in the soil was from 2.5 mg kg −1 to 40 mg kg −1 ). The highest 88 Sr accumulation was 239.18 μg g −1 dw, otherwise, the highest 133 Cs accumulation was 151.74 μg g −1 dw (The concentration of 88 Sr in the soil was 40 mg kg −1 ), and the lowest 88 Sr accumulation was 131.03 μg g −1 dw, otherwise, the lowest 133 Cs accumulation was 12.85 μg g −1 dw (The concentration of 88 Sr in the soil is 5 mg kg −1 ). The 88 Sr and 133 Cs TF values were 1.16–1.72 and 0.24–0.60, respectively. There was little influence of high concentration of 88 Sr on the total biomass of plants, so the radish is one of the ideal phytoremediation plant for Sr polluted soils. The important physiological reasons that radish had good tolerance to 88 Sr stress were that the MDA content was higher under the 88 Sr stress than that under the 133 Cs stress, and the activities of POD and CAT were lower under the 88 Sr stress than that under 133 Cs stress. - Highlights: ► Radish is a kind of native plant with high biomass and fast growth. Its uptake capacity of radish for 88 Sr was far higher than that for 133 Cs when the concentration of 88 Sr was the same as that of 133 Cs in the soil. ► The TF values of radish for 88 Sr were 1.16–1.72. ► Radish is one of the ideal phytoremediation plant for Sr polluted soils. ► The important physiological reasons that radish had good tolerance toward 88 Sr stress were that the MDA content was higher under the 88 Sr stress than under the 133 Cs stress, and the activities of POD

  8. {sup 137}Cs and {sup 90}Sr in dairy and farm milk in Finnish Lapland 1960-2000

    Energy Technology Data Exchange (ETDEWEB)

    Kostiainen, E.; Rissanen, K. [STUK - Radiation and Nuclear Safety Authority, Research and Environmental Surveillance (Finland)

    2003-06-01

    The decrease rates of {sup 90}Sr and {sup 137}Cs in milk were studied in the years following the atmospheric nuclear weapon testings and after the Chernobyl accident in 1986. The highest {sup 90}Sr and {sup 137}Cs concentrations in the 1960's in Finnish milk were recorded in Lapland even though the deposition of {sup 90}Sr and {sup 137}Cs did not significantly differ between other localities in Finland, and they were not greater in northern Finland. This was mainly due to the high proportion of peat soils and nutrient deficiency of the pastures in Lapland. {sup 137}Cs deposition after the Chernobyl accident in 1986 in Lapland was less than 1 kBq m-2, and {sup 90}Sr deposition was so low that there was no detectable increase in the {sup 90}Sr concentration in milk. The ecological half-lives were estimated for the decrease in the concentrations of {sup 137}Cs and {sup 90}Sr after the end of nuclear weapon testings period and the Chernobyl fallout during short and longer time intervals. (orig.)

  9. Accumulation of 137Cs and 90Sr in wood and bark of various types of oak and black alder plantings

    International Nuclear Information System (INIS)

    Perevolotskij, A.N.; Bulavik, I.M.; Perevolotskaya, T.V.; Paskrobko, L.A.; Andrush, S.N.

    2008-01-01

    Results of the evaluation of the influence of types of habitat edaphic conditions on 137Cs and 90Sr transition coefficients and their accumulation by wood and bark of English oak (Quercus robur L.) and black alder (Alnus glutinosa (L.) Gaertn) were presented. There was observed the particular influence of edaphic conditions on 137Cs and 90Sr accumulation by wood and bark of English oak. Lowering of 137Cs transition coefficients for the studied elements of phytomass was noted in the conditions of soil fertility increasing. Influence of soil moistening on 137Cs transition into wood and bark of oak trees was stated only in wood-sorrel and glague types of forests. Differences in accumulation of 90Sr by wood and bark of English oak in the studied range of edaphotopes were not proved. There was not found any differences in accumulation of both radionuclides by black alder trees in the typical for them edaphic conditions

  10. The adsorption of Cs+, Sr2+ and Ni2+ on bitumen: a mechanistic model

    International Nuclear Information System (INIS)

    Loon, L.R. Van; Kopajtic, Z.

    1991-01-01

    The adsorption of radionuclides on the waste matrix is a positive effect and contributes to the retardation of released radionuclides migrating to the geo-and biosphere. For the safety assessment studies, it is important to know whether or not radionuclides do adsorb on the waste matrix. In the present work the adsorption of 134 Cs + , 85 Sr 2+ and 63 Ni 2+ on bitumen was studied as a function of the pH and ionic strength of the equilibrium solution. Bitumen emulsions with well defined surfaces were used. The surface of bitumen is negatively charged due to the deprotonation of weak acid carboxyl groups at the interface. The functional group density amounts to 1.37.10 18 groups/m 2 and their deprotonation behaviour can be well described by the 'Ionizable Surface Group' model. Cs + , Sr 2+ and Ni 2+ adsorb on the surface by three different processes, i.e. ion exchange, outer sphere complexation and inner sphere surface complexation respectively. The adsorption depends on the pH and the ionic strength of the contact solution. Under near field conditions, Cs + and Sr 2+ do not adsorb on the bitumen due to the competition with Na + , K + and Ca 2+ present in the cement pore water in contact with the bitumen. Ni 2+ adsorption can also be neglected because the formation of neutral and anionic hydroxo complexes in solution competes strongly with the adsorption reaction. Other hydrolysable radionuclides of interest are expected to behave similarly to Ni 2+ . The main conclusion of the study is that the adsorption of radionuclides under near field conditions is expected to be very low. Consequently, this process need not to be considered in safety assessment studies. (author) figs., tabs., 30 refs

  11. Accumulation of 137Cs and 90Sr from contaminated soil by three grass species inoculated with mycorrhizal fungi

    International Nuclear Information System (INIS)

    Entry, J.A.; Watrud, L.S.; Reeves, M.

    1999-01-01

    The use of plants to accumulate low level radioactive waste from soil, followed by incineration of plant material to concentrate radionuclides may prove to be a viable and economical method of remediating contaminated areas. We tested the influence of arbuscular mycorrhizae on 137 Cs and 90 Sr uptake by bahia grass (Paspalum notatum), johnson grass (Sorghum halpense) and switchgrass (Panicum virginatum) for the effectiveness on three different contaminated soil types. Exposure to 137 Cs or 90 Sr over the course of the experiment did not affect above ground biomass of the three grasses. The above ground biomass of bahia, johnson and switchgrass plants accumulated from 26.3 to 71.7% of the total amount of the 137 Cs and from 23.8 to 88.7% of the total amount of the 90 Sr added to the soil after three harvests. In each of the three grass species tested, plants inoculated with Glomus mosseae or Glomus intraradices had greater aboveground plant biomass, higher concentrations of 137 Cs or 90 Sr in plant tissue, % accumulation of 137 Cs or 90 Sr from soil and plant bioconcentration ratios at each harvest than those that did not receive mycorrhizal inoculation. Johnson grass had greater aboveground plant biomass, greater accumulation of 137 Cs or 90 Sr from soil and plant higher bioconcentration ratios with arbuscular mycorrhizal fungi than bahia grass and switchgrass. The greatest accumulation of 137 Cs and 90 Sr was observed in johnson grass inoculated with G. mosseae. Grasses can grow in wide geographical ranges that include a broad variety of edaphic conditions. The highly efficient removal of these radionuclides by these grass species after inoculation with arbuscular mycorrhizae supports the concept that remediation of radionuclide contaminated soils using mycorrhizal plants may present a viable strategy to remediate and reclaim sites contaminated with radionuclides

  12. Behaviour of fission products 90Sr, 137Cs and 144Ce in soil-plant system

    International Nuclear Information System (INIS)

    Zhu Yongyi; Qiu tongcai

    1988-11-01

    A small quantity of radioonuclides, such as fission products 90 Sr, 137 Cs and 144 Ce etc., generally may leak out from nuclear inductry system and may be disseminated on soul and plant cover. The accumulation and distribution of the radionuclides in spring wheat planted in the contaminated soil are described. The factors as nuclide chemical forms, soil agrochemical properties, growing stages of the plant and fertilizing etc., which affect the accumulation and the distribution were discussed. Possible approches were supposed to eliminate or clean the radionuclides from contaminated soil, which include planting adaptable herbage, applying some fertilizers and scraping regolith etc

  13. Aminoacids used as radioprotective substances against Cs137 and Sr90 mixtures

    International Nuclear Information System (INIS)

    Danetskaya, E.V.; Ramzaev, P.V.; Troitskaya, M.N.

    1978-01-01

    An experimental study on white rats into the radioprotective action of ten essential amino acids has that valine, arginine, and histidine all effect appreciably the life span and absorbed doses of the principal radionuclides, 137 Cs and 90 Sr. When these amino acids are fed to rats, the survival rate increases and hemopoiesis tends to return to normal more rapidly; the reproductive function is unaffected. The mechanism of radioprotective action of these amino acids has been studied inadequately, but they seem to have a role to play in the metabolism of sulfur-containing compounds. The remaining amino acids have no protective action

  14. Vertical migration of 85Sr, 137Cs and 131I in various arable and undisturbed soils

    International Nuclear Information System (INIS)

    Palagyi, S.; Palagyiova, J.

    2003-01-01

    The vertical migration of 85 Sr, 137 Cs and 131 I in some arable and undisturbed single-contaminated soils was studied by gamma-spectrometry measurements under lysimetric laboratory conditions during irrigation of the soil profiles with wet atmospheric precipitation for about one year, except 131 I. A new simple exponential compartment (box) model was derived, which makes it possible to calculate the migration rate constants and migration rates in the individual soil layers (vertical sections) as well as the total vertical migration rate constants and total vertical migration rates of radionuclides in the bulk soil horizon. The relaxation times of radionuclides in respective soil horizons can also be evaluated. (author)

  15. Volume I. Environmental effects on contents of Cs-137 and Sr-90 in milk. Volume II. Appendices

    International Nuclear Information System (INIS)

    1981-01-01

    Milk, animal fodders, soils, humans, livestock, and wildlife on or near 55 dairy farms in Utah were assayed for radionuclide content. Effects of soil chemistry, water supply, plant type, farming practices, geographic location, altitude, rainfall, and other ecological differences were sought by intensive analysis. Although many analyses have not been completed, several cause-effect relationships have been defined. Wet-lands yield more 137 Cs, 131 I, or 90 Sr to milk under like conditions of fallout intensity than dry-lands. In most cases, the station with the highest yield is also practicing wet grazing. 90 Sr and 137 Cs content of milk is enhanced by sandy soils. Increased altitude and higher rainfall lead to higher yields of 90 Sr and 137 Cs in milk. Levels of 137 Cs in milk increase from south to north, and Utah can be divided into several regions, each having a characteristic level of 90 Sr and 137 Cs in milk, meat, and fodders. Poor pastures (over-grazed to the extent that stem bases are eaten and much soil is exposed) yield more 137 Cs and 90 Sr than improved pastures. Feeding green chop alfalfa or putting the animals on the meadows causes marked but temporary increases in the 90 Sr and 137 Cs content of the milk. However, the annual yield for two stations of similar ecology in the same geographic area is essentially the same. Experimental details are presented in Volume I. The appendices in Volume II are made up primarily of the data compiled at the 78 stations

  16. Immobilisation of 137Cs and 90Sr in hot-pressed clinoptilolite

    International Nuclear Information System (INIS)

    Briggs, A.; Jones, D.V.C.; Cole, G.B.; Valentine, T.M.; Preston, R.F.; Hawes, R.W.M.; Fones, M.D.

    1984-07-01

    It is shown that clinoptilolites from Nevada and Mudhills, California, can be vitrified by hot-pressing at 1000 to 1050 deg C for 30 min under 23 MPa pressure in graphite dies, or for 10 min under 3.5 MPa pressure in stainless steel bellows-shaped containers. Activity measurements before and after hot-pressing show that the radionuclides 137 Cs and 90 Sr are retained almost completely during the process. The hot-pressed material is shown to be extremely resistant to leaching of the nuclides, either in Soxhlet or long-term static leach tests. Gamma-irradiation increases their leachability; that of 90 Sr more than that of 137 Cs, but even so, the leach rates of both remain very low. X-ray diffraction spectra taken before and after heat-treatment for 10 days at temperatures up to 1000 deg C show no deleterious effects, and hydrothermal treatments at temperatures up to 90 deg C for 100 days, even in the presence of sodium ions in solution, are shown not to cause any changes detectable by X-ray diffraction. (author)

  17. Interlaboratory comparison of the determination of 137Cs and 90Sr in water, food and soil

    International Nuclear Information System (INIS)

    Fuks, L.; Polkowska-Motrenko, H.; Merta, A.

    2006-01-01

    Reliable measurements of radioisotope concentrations are of primary importance for the laboratories dealing with radioactivity determinations. According to the Polish regulations, since 2002 it is obligatory to organize every two years national interlaboratory comparisons (ILC) on the determination of various radionuclides in food and environmental samples. First such ILC on the determination of 137 Cs and 90 Sr in water, food and soil was organized by the National Atomic Energy Agency of Poland in 2004 with the participation of fourteen laboratories from Polish research institutes and universities. The ILC was conducted by the Institute of Nuclear Chemistry and Technology. Two types of water (surface and potable; six samples), wheat flour and soil (four samples) were spiked with 137 Cs and 90 Sr. From the results obtained in all participating laboratories it can be concluded that the procedures of assigning value and preparation of homogeneous material have been done properly and the majority of the determinations remain in good agreement with the assigned values and with the results obtained by other laboratories. Such agreement means that the performance of the laboratories is good and also that the samples are equivalent

  18. Accumulation of 137Cs and 90Sr radionuclides by leguminous plants of various species and varieties

    International Nuclear Information System (INIS)

    Zhdanovich, V.P.; Podolyak, A.G.; Arastovich, T.V.; Demidovich, S.A.; Odintsova, L.E.; Ivashkova, I.I.; Polovkov, N.N.

    2005-01-01

    Decision of protein problem on territories contaminated with radionuclides as a result of the accident at the Chernobyl NPP is not possible without extension of lands under cultivation of leguminous plants (peas, lupine and soybean). All lupine varieties show high indices of radionuclides accumulation and are restrictedly acceptable for production on contaminated territories. The following varieties of yellow forage lupine are the most acceptable for cultivation on the contaminated territories: Zhemchug, Rannij, Adradzhenne, Mitan. Introduction of varieties with the low level of radionuclides accumulation (peas — Aist, Agat, Gomelskaya; soybean — Mageva, Pina, Severnaya zvezda) into agricultural production will make to possible to obtain agricultural products meeting the requirements of the “Republican permissible levels of 137Cs and 90Sr content in agricultural raw materials and forages” on arable lands with the higher density of radioactive contamination: 137Cs — 925—1110 kBq/m2 (25-30 Ci/km2) and 90Sr 15—18 kBq/m2 (0.40-0.50 Ci/km2)

  19. Determinants of radiological dose from Sr and Cs accumulated by tropical freshwater fish

    International Nuclear Information System (INIS)

    Twining, J.R.; Markich, S.J.; Ferris, J.M.

    1998-01-01

    Recent studies of the bioaccumulation of strontium and caesium by tropical freshwater fish were in some ways consistent with temperate data. For example, biodistribution of radionuclides and the influence of chemical analogues Ca and K were in general agreement with earlier data. However, in other matters there were systematic inconsistencies when compared with the standard IAEA models. These differences gave rise to transfer (concentration) factors for both Cs and Sr that were approximately an order of magnitude below the expected values based on temperate data (e.g. 13 and 0.7 compared with 440 and 4.7 respectively). Compatible results were found for a range of tropical species studied by different investigators. In this presentation, some of the factors believed to influence bioaccumulation, and hence radiological dose, in tropical environments are discussed in relation to the above findings. These factors include: water physico-chemistry, temperature, fish size and physiology, whether or not the data were acquired from field or laboratory studies, and how the studies were carried out. Critical group exposure pathways in tropical environments and the benefits and shortcomings of applying default temperate models of Cs and Sr accumulation by freshwater fish are also discussed. (author)

  20. Transfer factors of some selected radionuclides (radioactive Cs, Sr, Mn, Co and Zn) from soil to leaf vegetables

    International Nuclear Information System (INIS)

    Ban-nai, Tadaaki; Muramatsu, Yasuyuki; Yanagisawa, Kei

    1995-01-01

    Transfer factors of radionuclides from soil to leaf vegetables (cabbage, Chinese cabbage, komatsuna, spinach and lettuce) have been studied by radiotracer experiments using Andosol as a representative of Japanese soils. The transfer factors of radioactive Cs, Sr, Mn, Co and Zn for edible parts of vegetables (average of five vegetables) were 0.11, 0.24, 0.61, 0.05 and 0.52, respectively. These values should be used in safety assessment for Japanese agricultural environment. The transfer factors of Mn, Co and Zn for spinach were higher than those for the other vegetables. The transfer factors of Cs for different organs of the leaf vegetables were rather homogeneous. The transfer factors of Sr and Mn were higher for older (outer) leaves than younger (inner) ones. In contrast to Sr and Mn, transfer factors of Zn for younger leaves were higher than those for older ones. The distribution ratios of the elements between soil-solution and soil were in the order Sr>Mn>Cs>Co>Zn, whereas the distribution ratios of the elements between plant and soil-solution were in the order Zn>Cs>Mn>Co>Sr. These results indicate that the selectivity for Sr by plants from the soil-solution was low and that for Zn was very high. (author)

  1. Comparison of decontamination parameters for two rodents. {sup 90}SR and {sup 137}CS

    Energy Technology Data Exchange (ETDEWEB)

    Bondarkov, M.; Gaschak, S.; Goryanaya, J.U.; Maksimenko, A.; Barchuk, R.; Martynenko, V.; Shulga, A.; Chesser, R.; Rodgers, B. [Chornobyl Center for Nuclear Safety, Radioactive Waste and Radioecology, International Radioecology Laboratory, Slavutych (Ukraine)

    2004-07-01

    The rate of {sup 90}Sr and {sup 137}Cs content decrease in the whole body has been estimated for bank vole Clethrionomys glareolus and lab strain of mouse Mus musculus (Big Blue) over 50 and 180 days, respectively. Before the study the animals were naturally contaminated within the most contaminated area of the Chernobyl zone. The initial activity of the whole body ranged as follows: voles - 4-385 kBq for {sup 137}Cs, 0.9-7.7 kBq for {sup 90}Sr; mice - 0.62-1.19 and 0.64-2.20, respectively. Methods of beta and gamma spectrometry and a specially designed alive counting method were used in the study. The exponential decay model of the second order was applied to estimate parameters of the body decontamination from {sup 137}Cs. Both species have similar half-life periods of the fast-excreted fraction - 1.87-2.17d. However, a bank vole loses up to 96-97% of initial activity by the fast excreted fraction, while mice - only 67.4%. A slow excreted fraction of initially accumulated {sup 137}Cs has a half-life period of 55.3d and 9.6d in voles and mice, respectively. Thus, bank vole and domestic mouse have evident differences of radiocesium excretion, first of all at the early stage of decontamination. Some preliminary data for a yellow-necked mouse Apodemus flavicollis show similar parameters of decontamination as for a domestic mouse. The excretion of {sup 90}Sr was estimated using the exponential decay model of the first order. A mouse has much larger part of the excreted radionuclide - 87%, and a half-life period - 49.9d; a vole - 58% and 13.1d, respectively. The rest amount of radionuclides was considered as non-excreted over the study term. Thus, similar size representatives of two rodent taxa have different parameters of radionuclide excretion. The reason for this may be their specific physiology of accumulation and excretion. (author)

  2. Comparison of decontamination parameters for two rodents. 90SR and 137CS

    International Nuclear Information System (INIS)

    Bondarkov, M.; Gaschak, S.; Goryanaya, J.U.; Maksimenko, A.; Barchuk, R.; Martynenko, V.; Shulga, A.; Chesser, R.; Rodgers, B.

    2004-01-01

    The rate of 90 Sr and 137 Cs content decrease in the whole body has been estimated for bank vole Clethrionomys glareolus and lab strain of mouse Mus musculus (Big Blue) over 50 and 180 days, respectively. Before the study the animals were naturally contaminated within the most contaminated area of the Chernobyl zone. The initial activity of the whole body ranged as follows: voles - 4-385 kBq for 137 Cs, 0.9-7.7 kBq for 90 Sr; mice - 0.62-1.19 and 0.64-2.20, respectively. Methods of beta and gamma spectrometry and a specially designed alive counting method were used in the study. The exponential decay model of the second order was applied to estimate parameters of the body decontamination from 137 Cs. Both species have similar half-life periods of the fast-excreted fraction - 1.87-2.17d. However, a bank vole loses up to 96-97% of initial activity by the fast excreted fraction, while mice - only 67.4%. A slow excreted fraction of initially accumulated 137 Cs has a half-life period of 55.3d and 9.6d in voles and mice, respectively. Thus, bank vole and domestic mouse have evident differences of radiocesium excretion, first of all at the early stage of decontamination. Some preliminary data for a yellow-necked mouse Apodemus flavicollis show similar parameters of decontamination as for a domestic mouse. The excretion of 90 Sr was estimated using the exponential decay model of the first order. A mouse has much larger part of the excreted radionuclide - 87%, and a half-life period - 49.9d; a vole - 58% and 13.1d, respectively. The rest amount of radionuclides was considered as non-excreted over the study term. Thus, similar size representatives of two rodent taxa have different parameters of radionuclide excretion. The reason for this may be their specific physiology of accumulation and excretion. (author)

  3. Study of radioactive sr and Cs in soil and soil /plant system at Inshas region

    International Nuclear Information System (INIS)

    Eissa, H.S.M.

    2008-01-01

    The radioactive fallout is considered one of the most major environmental problems that threats public health. The work presented in this thesis is carried out to investigate the level of radioactivity in different environmental samples of soils and vegetations collected from different locations around the NRC at Inshas area and the area nearby (about 30 km radius). Six different locations: Inshas, Shebeen, Abu-Zaabal, Al-Oboor in addition to two sites in the nuclear research center (old reactor and protection department sites) were chosen for the collection of the soil and plant samples. Most typical egyptian soils (sandy, sandyloam, clayey)from three different places (Al-Oboor, Abu-Zaabal, and Shebeen El-Kanatter) were selected for the experiments carried out under laboratory conditions. The plants investigated were grass, old trees and wheat. Cs 137 and Sr 90 were chosen to represent the most important long-lived radionuclides considering the human health, since these nuclides can enter human body via food chain and increase the radiation burden for many years. The following points are considered in this work: 1- Natural radionuclides concentration in different environmental samples of soil and plant especially (grasses and leaves of old trees) were determined using high resolution gamma-spectroscopic system (hyper-pure germanium detector). 2-Two groups of elements have been determined directly in two plant samples from each location (one grass, and the other old trees) together with their corresponding soils.3- Transfer factors (often used to describe the uptake of the radioisotope from soil to plant)of the log-lived radionuclides 137 Cs and 90 from soil to the wheat plant have been studied by radiotracer experiments .4- The sorption behavior of Cs and Sr radionuclides by the different soil types was investigated kinetically using batch techniques.

  4. The selective removal of 90Sr and 137Cs from liquid low-level waste at Oak Ridge National Laboratory

    International Nuclear Information System (INIS)

    Bostick, D.T.; Arnold, W.D.; Burgess, M.W.; Taylor, P.A.; Kent, T.E.

    1995-01-01

    Methods are being developed for the selective removal of the two principal radioactive contaminants, 90 Sr and 137 Cs, from liquid low-level waste generated and/or stored at Oak Ridge National Laboratory. These methods are to be used in a future centralized treatment facility at ORNL. Removal of 90 Sr in the proposed treatment flashed is based on coprecipitation from strongly alkaline waste by adding stable strontium to the waste solution. Ferric sulfate, added with the stable strontium, improves the 90 Sr removal and aids in the flocculation of the strontium carbonate (SrCO 3 ) precipitate. After separation of the solids, the resultant supernate is adjusted to pH 8 for the cesium removal treatment. Upon pH adjustment, aluminum originally present in the untreated alkaline waste precipitates and sorbs an additional amount of 90 Sr. Cesium is removed from the neutralized waste by two sequential treatments with potassium cobalt hexacyanoferrate (KCCF) slurry formed by the addition of potassium ferrocyanide (K 4 Fe(CN) 6 ) and cobalt nitrate (Co(NO 3 ) 2 ) solutions. The cumulative decontamination factors (DFs) for 90 Sr and 137 Cs in benchscale studies are 4900 and 1 x 10 6 , respectively, if high speed centrifugation is used for the liquid/solid separations. Efforts are now underway to evaluate process-scale techniques to perform the liquid/solid separations required for removal of SrCO 3 and 137 Cs-bearing hexacyanoferrate solids from the treated waste solution

  5. Local-scale modelling of the releases of 137-Cs and 90-Sr from Fukushima NPP into the Pacific Ocean

    International Nuclear Information System (INIS)

    Raul, Perianez

    2013-01-01

    The dispersion of 137-Cs and 90-Sr released from Fukushima nuclear power plant to the sea after the March 11th 2011 tsunami has been studied using a numerical model. The 3D dispersion model consists of an advection/diffusion equation with terms describing uptake/release reactions between water and seabed sediments. The dispersion model has been fed with daily currents provided by JCOPE2 ocean model. Seabed sediment 137-Cs computed patterns have been compared with observations. The impact of tides and of atmospheric deposition on sediment contamination has been evaluated as well. First simulations carried out for Sr-90 are described. An evaluation of the amount of this radionuclide released to the sea has been made using a numerical model for the first time. Calculated vertical profiles of this radionuclide have been compared with measured ones. Finally, the variability in 90-Sr/137-Cs activity ratios has been analysed with the model

  6. New methodological approaches to the simultaneous measurement of the 90Sr and 137Cs activity in environmental samples

    Directory of Open Access Journals (Sweden)

    M. V. Zheltonozhska

    2012-12-01

    Full Text Available Nonradiochemical method of measurement of 90Sr and137Cs activity in environmental samples is proposed. This method is based on spectrometrical investigation of electrons accompanied the decay of the 90Sr and137Cs. Accounting for the contribution to the total activity of the samples from the zones with the density of the contamination 1 - 5 Кu/km2 the 40K electrons allowed to improve the accuracy of the measurements for the samples of small rodents up to 15 - 20 % (the ratio of A (137Cs/A (90Sr was from 2 to 100, for samples of soil up to 10 - 15 % (the change of activity in these samples was ten thousand times. The results of the spectrometric measurements were confirmed by the traditional radiochemical research.

  7. Inventory and vertical migration of {sup 90}Sr fallout and {sup 137}Cs/{sup 90}Sr ratio in Spanish mainland soils

    Energy Technology Data Exchange (ETDEWEB)

    Herranz, M. [Department Nuclear Engineering and Fluid Mechanics, University of the Basque, Country (UPV/EHU), Alda Urquijo s/n, E-48013 Bilbao (Spain); Romero, L.M. [CIEMAT, Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Av. Complutense 22, 28040 Madrid (Spain); Idoeta, R. [Department Nuclear Engineering and Fluid Mechanics, University of the Basque, Country (UPV/EHU), Alda Urquijo s/n, E-48013 Bilbao (Spain); Olondo, C., E-mail: kontxi.olondo@ehu.es [Department Nuclear Engineering and Fluid Mechanics, University of the Basque, Country (UPV/EHU), Alda Urquijo s/n, E-48013 Bilbao (Spain); Valino, F. [CIEMAT, Centro de Investigaciones Energeticas, Medioambientales y Tecnologicas, Av. Complutense 22, 28040 Madrid (Spain); Legarda, F. [Department Nuclear Engineering and Fluid Mechanics, University of the Basque, Country (UPV/EHU), Alda Urquijo s/n, E-48013 Bilbao (Spain)

    2011-11-15

    In this paper the inventory of {sup 90}Sr in 34 points distributed along the Spanish peninsular territory is presented. Obtained values range between 173 Bq/m{sup 2} and 2047 Bq/m{sup 2}. From these data set and those {sup 137}Cs data obtained in a previous work the {sup 137}Cs/{sup 90}Sr activity ratio has been established, laying this value between 0.9 and 3.6. Also the migration depth of both radionuclides has been analysed obtaining for {sup 137}Cs an average value 57% lower than that obtained for {sup 90}Sr. Additionally, this paper presents the results obtained in 11 sampling points in which the activity vertical profile has been measured. These profiles have been analysed to state the behaviour of strontium in soils and after, by using a convective-diffusive model, the parameters of the model which governs the vertical migration of {sup 90}Sr in the soil, v (apparent convection velocity) and D (apparent diffusion coefficient) have been evaluated. Mean values obtained are 0.20 cm/year and 3.67 cm{sup 2}/year, respectively. - Highlights: > Measured {sup 90}Sr activity in Spanish mainland, being within a range of [173, 2047] Bq/m{sup 2}, with a mean value of 793 Bq/m{sup 2}. > Compared the migration capacity of {sup 137}Cs and {sup 90}Sr in the same soils. > {sup 90}Sr shows a unique behaviour tendency in soil. > The parameters which govern the applied model have been obtained for the analysed profiles. > Analysed those parameters' values also reflects this unique tendency.

  8. Migration of 137Cs and 90Sr in undisturbed soil profiles under controlled and close-to-real conditions

    International Nuclear Information System (INIS)

    Forsberg, S.; Rosen, K.; Fernandez, V.; Juhan, H.

    2000-01-01

    Migration of 137 Cs and 90 Sr in undisturbed soil was studied in large lysimeters three and four years after contamination, as part of a larger European project studying radionuclide soil-plant interactions. The lysimeters were installed in greenhouses with climate control and contaminated with radionuclides in an aerosol mixture, simulating fallout from a nuclear accident. The soil types studied were loam, silt loam, sandy loam and loamy sand. The soils were sampled to 30-40 cm depth in 1997 and 1998. The total deposition of 137 Cs ranged from 24 to 45 MBq/m 2 , and of 90 Sr from 23 to 52 MBq/m 2 . It was shown that migration of 137 Cs was fastest in sandy loam, and of 90 Sr fastest in sandy loam and loam. The slowest migration of both nuclides was found in loamy sand. Retention within the upper 5 cm was 60% for both 137 Cs and 90 Sr in sandy loam, while in loamy sand it was 97 and 96%, respectively. In 1998, migration rates, calculated as radionuclide weighted median depth (migration centre) divided by time since deposition were 1.1 cm/year for both 137 Cs and 90 Sr in sandy loam, 0.8 and 1.0 cm/year, respectively, in loam, 0.6 and 0.8 cm/year in silt loam, and 0.4 and 0.6 cm/year for 137 Cs and 90 Sr, respectively, in loamy sand. A distinction is made between short-term migration, caused by events soon after deposition and less affected by soil type, and long-term migration, more affected by e.g. soil texture. Three to four years after deposition, effects of short-term migration is still dominant in the studied soils

  9. 90Sr and 137Cs migration from the Dnieper water to the agricultural plants of Southern Ukraine

    International Nuclear Information System (INIS)

    Polikarpov, G.; Kulebakina, L.

    1994-01-01

    In the Southern Ukraine, particularly in the Crimea, the Dnieper water is used for irrigation purposes. The aim of our radioecological investigations was to study the post-Chernobyl radionuclide transfer from the Dnieper water to the rice fields and their absorption by agricultural plants. The content of 90 Sr and 137 Cs was determined in the waters of the Dnieper River and canals, in the soil of rice fields, in the rice paddy fields and in lucerne and clover. 90 Sr was found to be the major radionuclide entering the rice fields. The dynamics of 90 Sr was observed in the lower Dnieper and the NCC in the period of 1986-1993. The 137 Cs contamination of rice fields is associated with atmospheric fallout occurred during April-May of 1986. The quantity of 137 Cs delivered to the Crimea with the Dnieper waters is 10-100 times less than that of 90S r. On the rice fields, radionuclides were accumulated by soils and plants. Three-years observations showed the increase of 90 Sr concentration in soils of the rice fields. The 90 Sr concentration in drains (after the rice fields) is less than before the rice fields. 137 Cs is washed out from the soils of the rice fields by irrigation water. Therefore the concentrations of 137 Cs and 90 Sr in soils under lucerne and clover are higher than in soils under rice. The concentration of these radionuclides are higher in paddy than in clover and lucerne. The potassium content in soils influences the 137 Cs accumulation by plants

  10. 137Cs and 90Sr root uptake by beans in soils with contrasting properties

    International Nuclear Information System (INIS)

    Sauras Yera, T.; Vallejo, R.; Waegeneers, N.; Madoz-Escande, C.

    1998-01-01

    Radionuclide soil to crop transfer was analysed in large undisturbed soil monoliths installed in lysimeters under controlled climatic conditions. Both the solid/liquid distribution coefficient K D (= [RN] in soil (Bq/kg)/[RN] in soil solution (Bq/l)) and the concentration factor CF (= (Bq/kg plant)/(Bq/l soil solution)) are affected by the concentration of K, Ca and Mg in soil solution. The 137 Cs concentration in soil solution varied from 400 Bq/l to 9 Bq/l in the various types of soil, the corresponding K D value ranged from 480 to 19000 l/kg. The concentration of potassium in the soil solution (m K ) varied from 25 mmol/l to 0.6 mmol/l. A negative linear relationship on the logarithmic scale was found between K D and the potassium status of the soil solution: high K levels brought about low K D 's and thus, promotion of 137 Cs in the soil solution. The plant concentration factor was also affected by the K concentration: high K contents in soil solution resulted in low CF's and vice versa. The interdependence was again linear in logarithmic coordinates. The 137 Cs root uptake crop reflected the specific scenario of each soil. The K D and CF values were also negatively related to the Ca+Mg concentration in the soil solution. Thus, K, Ca and Mg in the soil solution play an important role in the 137 Cs and 90 Sr root uptake and, in addition to the soil type and specific growing conditions, are important factors governing the transfer

  11. Evaluating 90Sr and 137Cs accumulation by structural elements of exclusion zone's vegetative communities of meadow and lea land

    International Nuclear Information System (INIS)

    Paskevich, S.A.; Petrov, M.F.

    2003-01-01

    Biogenic carry-over of 90 Sr and 137 Cs by structural elements of exclusion zone's meadows and lea land phytocenosis is considered. Quantitative parameters of radionuclide accumulation are evaluated in substrate and live biomass of communities growing under various ecological conditions. It was stated that accumulation levels for ground biomass of communities depends, at a significant rate, on landscape growing conditions. These values fluctuate within the range of around 100 times. For 90 Sr, significantly lower difference in carry-over values was observed totaling up to 5 times, although for single community, this radionuclide carry-over exceeds essentially 137 Cs carry-over

  12. Speciation of {sup 90}Sr and {sup 137}Cs in Techa river water

    Energy Technology Data Exchange (ETDEWEB)

    Osipov, D.; Andreev, S.; Pryakhin, E. [Urals Research Center for Radiation Medicine (Russian Federation); Teien, H.C. [Norwegian University of Life Sciences - UMB, Center of Excellence in Environmental Radioactivity - CERAD (Norway)

    2014-07-01

    The concentration and speciation of {sup 90}Sr and {sup 137}Cs were measured in the upper, middle and lower reaches of Techa River, South Ural, Russia in 2012 and 2013. To obtain information of the physical-chemical forms of the radionuclides (RN) in Techa River water, at site size fractionation of water was performed using filtration and ultrafiltration. Using both membrane filters (10 μm and 0.45 μm) and hollow fiber (10 kDa cutoff), following size fractionation were determined: - Particulate RN: size fraction 0.45-10 μm. Excluded by 0.45 μm membrane filter, but passing 10 μm membrane filter - Colloidal RN: size fraction 10 kDa - 0.45 μm. Excluded by hollow fibre of 10 kDa cutoff, but passing 0.45 μm membrane filter - Low molecular mass (LMM) RN: less than 10 kDa. Determined in ultra-filtrated water. Results demonstrated that the concentration of {sup 90}Sr in samples, passed through 10 μm membrane filter, is practically equal to its concentration in ultra-filtered water, both in spring and summer 2012 and 2013. This suggests that {sup 90}Sr is not associated with particulate or colloidal material in the river water, but mainly presents as LMM species, probably ions in a biologically available form. {sup 137}Cs was, however present in different size fractions and the distribution of size fractions depending upon location in river and time of sampling. In the upper part of Techa River {sup 137}Cs was mainly present as LMM species, about 70% and 100% in spring 2012 and 2013, respectively. The remaining part was present as particles larger than 0.45 μm. In the summer 2012, about 15% of the radionuclide was in LMM form and, consequently, almost equal quantities - 46% and 39% - were in colloidal and particulate forms, respectively. At station in the middle reach of Techa River, about 25% and 40% of {sup 137}Cs was present as LMM species, in spring 2012 and 2013, respectively. The remaining part was mainly present as colloidal species. At station in the lower

  13. Processing of radioactive waste solution with zeolites. I. Thermal transformation of Na, Cs and Sr type zeolites

    Energy Technology Data Exchange (ETDEWEB)

    Kanno, T; Mimura, H; Kitamura, T [Tohoku Univ., Sendai (Japan). Research Inst. of Mineral Dressing and Metallurgy

    1976-08-01

    Thermal transformation of Na, Cs and Sr type zeolites were studied by means of differential thermal analysis (DTA), thermogravimetric analysis (TGA) and X-ray powder diffraction. Synthetic zeolites A, X and Y, synthetic mordenite (Zeolon) and natural mordenite were used in this study. Na type zeolites of A and X recrystallized to Nepheline (NaAlSiO/sub 4/) above 1,000/sup 0/C, but the structures of zeolite Y and mordenite collapsed above about 900/sup 0/C and did not recrystallize until 1,200/sup 0/C. Cs type zeolites of A and X recrystallized to pollucite (CsAlSi/sub 2/O/sub 6/) above 1,000/sup 0/C and Cs type of zeolite Y recrystallized to it above 1,100/sup 0/C, but the structure of mordenite collapsed above 1,000/sup 0/C and did not recrystallize until 1,200/sup 0/C. On Sr type zeolites, zeolite A and X recrystallized to strontium aluminosilicate (SrAl/sub 2/Si/sub 2/O/sub 8/) above 1,100/sup 0/C and zeolite Y recrystallized to it above 1,200/sup 0/C, but the structure of mordenite collapsed above 1,000/sup 0/C. The results described above were supported by microscopic observation and the measurement of density. If this solidifications by calcination of zeolites are further studied, new informations concerning the fixation of Cs and Sr will be obtained.

  14. On-line ion chemistry for the AMS analysis of {sup 90}Sr and {sup 135,137}Cs

    Energy Technology Data Exchange (ETDEWEB)

    Eliades, J. [IsoTrace Laboratory, University of Toronto, 60 St. George St., Toronto, ON, M5S 1A7 (Canada); Zhao, X.-L. [Department of Physics, University of Ottawa, 150 Louis Pasteur, Ottawa, ON, K1N 6N5 (Canada); Litherland, A.E. [IsoTrace Laboratory, University of Toronto, 60 St. George St., Toronto, ON, M5S 1A7 (Canada); Kieser, W.E., E-mail: liam.kieser@utoronto.ca [Department of Physics, University of Ottawa, 150 Louis Pasteur, Ottawa, ON, K1N 6N5 (Canada)

    2013-01-15

    The analysis of {sup 90}Sr by AMS has so far required the use of very large tandem accelerators in order to separate the isobar {sup 90}Zr by the rate-of-energy-loss method. The analysis of {sup 135,137}Cs by AMS has never been attempted as the separation of the isobars {sup 135,137}Ba by the traditional method requires even higher energies, so that this approach would become prohibitively expensive for routine analysis. Following the successful demonstration of Cl{sup -}-S{sup -} separation by the Isobar Separator, the same apparatus was used to test the separation of other pairs of isobars. Surprisingly effective results were obtained with NO{sub 2} gas in the cases of SrF{sub 3}{sup -}-ZrF{sub 3}{sup -} and CsF{sub 2}{sup -}-BaF{sub 2}{sup -} separations. Reduction factors of {approx}4 Multiplication-Sign 10{sup -6} for ZrF{sub 3}{sup -}/SrF{sub 3}{sup -} and {approx}2 Multiplication-Sign 10{sup -5} for BaF{sub 2}{sup -}/CsF{sub 2}{sup -} were measured. SrF{sub 3}{sup -} and CsF{sub 2}{sup -} are both super-halogen anions and are preferentially produced in the ion source rather than ZrF{sub 3}{sup -} and BaF{sub 2}{sup -} when using the PbF{sub 2} matrix-assisted method. Reduction factors for ion source production with such targets of {approx}3 Multiplication-Sign 10{sup -5} for ZrF{sub 3}{sup -}-SrF{sub 3}{sup -} and {approx}5 Multiplication-Sign 10{sup -4} for BaF{sub 2}{sup -}-CsF{sub 2}{sup -} were found. The combined methods would suggest a theoretical detection sensitivity for {sup 90}Sr/Sr {approx}6 Multiplication-Sign 10{sup -16}, {sup 135}Cs/Cs {approx}7 Multiplication-Sign 10{sup -15} and {sup 137}Cs/Cs {approx}1 Multiplication-Sign 10{sup -14}, assuming 10 ppm Zr and Ba contamination in the AMS targets. In addition to the earlier Cl{sup -}-S{sup -} separation work, these measurements further illustrate the potential of on-line ion chemical methods for broadening the analytical scope of small AMS systems.

  15. Relationships between properties of Hanford area soils and the availability of 134Cs and 85Sr for uptake by cheatgrass and tumbleweed

    International Nuclear Information System (INIS)

    Cataldo, D.A.; Routson, R.C.; Paine, D.; G.

    1978-10-01

    The relationships between plant root absorption mechanisms and basic soil parameters which effect the concentration of Sr and Cs, and analog ions in soil solution are reviewed. Based on these relationships, studies were undertaken to determine the relative availability of Cs and Sr for uptake by plants grown on Hanford area soils, and the feasibility of developing a predictive relationship between readily measurable soil parameters and plant availability of Cs and Sr. Concentration ratios were determined for cheatgrass and tumbleweed grown on Hanford area soils representing a range in properties (Burbank, Ritzville, Lickskillet, Rupert and Warden). Concentration ratios ranged from 0.0078 to 0.066 and 3.5 to 16 for 134 Cs and 85 Sr, respectively. Soils were analyzed for physical properties, mineralogy, extractable cations and extractable 134 Cs and 85 Sr. Simple correlation analyses showed Cs and Sr uptake in cheatgrass and Sr uptake by tumbleweed to be related to cation exchange capacity, and extractable Sr, Ba and Mg. However, in the case of Cs, this correlation may be coincidental since these divalent cations are not chemical analogs of Cs. Uptake of Cs by tumbleweed showed weak correlations with extractable and exchangeable K. Factor analysis and principle components analysis did not assist in further quantitation of the relationships between plant uptake and soil parameters

  16. Sorption of Sr and Cs on rocks and minerals. Pt. 1

    International Nuclear Information System (INIS)

    Torstenfelt, B.; Andersson, K.; Allard, B.

    1981-09-01

    The sorption of Sr 90 and Cs 137 on some common Swedish rocks (granite, gneiss, and diabase) and eleven different major rock-forming minerals (quartz, orthoclase, apatite, fluorite, biotite, muscovite, hematite, magnetite, hornblende, calcite, and serpentine) has been studied, using a batch technique. A comparison with the retention obtained in column experiments has been made. The water phase in all experiments has been an artificial groundwater with a composition corresponding to Swedish natural deep groundwaters. The influence of parameters, such as pH (4-11), contact time (1 day-6 months), nuclide concentration (normally 10 -7 M, variations up to 0.1 M has been made), liquid to solid ratio, particle size (three fractions between 0.045 and 0.500 mm) has been studied. An attempt to predict the distribution coefficient for rocks, using known data for the rock-forming minerals gave too low values in all cases. (Auth.)

  17. Ecological half-lives of 9Sr and 137Cs in terrestrial and aquatic ecosystems

    International Nuclear Information System (INIS)

    Proehl, G.; Ehlken, S.; Fiedler, I.; Kirchner, G.; Klemt, E.; Zibold, G.

    2006-01-01

    This paper describes the long-term behaviour of 9 Sr and 137 Cs in foods, feeds and a variety of environmental media. The long-term behaviour is quantified by means of the ecological half-life which integrates all processes that cause a decrease of activity in a given medium such as leaching, fixation and erosion. A large number of long-term time series of concentrations of radiocaesium and radiostrontium in these media have been identified and re-evaluated using a standardised statistical procedure to establish reference data sets of ecological half-lives. By example of undisturbed soils and marine water bodies it is shown that the ecological half-life concept is questionable if the distribution of the radionuclide of interest within the medium studied is non-uniform and if mixing and transport processes within this medium, therefore, are of considerable importance during the time period of observation

  18. Solvent extraction of Sr2+ and Cs+ based on hydrophobic protic ionic liquids

    International Nuclear Information System (INIS)

    Luo, Huimin; Yu, Miao; Dai, Sheng

    2007-01-01

    A series of new hydrophobic and protic alkylammonium ionic liquids with bis(trifluoromethylsulfonyl) imide or bis(perfluoroethylsulfonyl)imide as conjugated anions was synthesized in a one-pot reaction with a high yield. In essence our synthesis method involves the combination of neutralization and metathesis reactions. Some of these hydrophobic and protic ionic liquids were liquids at room temperature and therefore investigated as new extraction media for separation of Sr 2+ and Cs + from aqueous solutions. An excellent extraction efficiency was found for some of these ionic liquids using dicyclohexano-18-crown-6 and calix[4]arene-bis(tert-octylbenzo-crown-6) as extractants. The observed enhancement in the extraction efficiency can be attributed to the greater hydrophilicity of the cations of the protic ionic liquids. The application of the protic ionic liquids as new solvent systems for solvent extraction opens up a new avenue in searching for simple and efficient ionic liquids for tailored separation processes. (orig.)

  19. Retention of 60Co, 85Sr and 137Cs on inorganic ion exchangers

    International Nuclear Information System (INIS)

    Dozol, J.F.; Eymard, S.

    1983-11-01

    The aim of the study is the treatment of radioactive wastes produced in plutonium fuel fabrication or in spent fuel reprocessing by inorganic ion exchangers for ultimate storage. This rapport, gives the distribution coefficients of 60 Co, 85 Sr, 137 Cs (in sodium nitrate medium at different concentration of sodium: .23g/l, 1 g/l, 10 g/l) obtained with different inorganic exchangers: titanium oxyde, sodium titanate, sodium zirconate, sodium niobate, sodium tantalate, titanium phosphate, zirconium phosphate, ammonium phosphotungstate in zirconium phosphate, polyantimonic acid amorphous aluminosilicate and several zeolites (ZBS 15 from OXYMIN, ZEOLON 400, ZEOLON 500, ZEOLON 900 from Norton, IE 96, A 51, 13 X from Union Carbide) [fr

  20. Mobility of Cs137 and Sr90 in organic soils and its control

    International Nuclear Information System (INIS)

    Rovdan, E.

    2002-01-01

    In the management of the radionuclide contaminated areas and application of a countermeasure strategy for reduction of both the external and internal doses to the population it is extremely important to know the environmental mechanisms governing the behaviour of radionuclides in soil ecosystems. The purpose of work is to investigate by means of laboratory, field experiments and mathematical modelling the mechanisms and dynamics of radionuclide transfer in the organic soil to propose measures for control their mobility. The Chernobyl radionuclides behaviour was studied for ameliorated peat-mire soil (peat deposit Pogonyanskoye, 21 km off the ChNPP). To control the mobility of radionuclides in soils the characteristics of the migration and sorption of Cs 137 and Sr 90 in sedge peat, quartz sand, bentonite, kaolin, sapropel as well as the electrolytes impact upon the radionuclide behaviour have been experimentally investigated

  1. Modification of the 137Cs, 90Sr, and 60Co transfer to wheat plantlets by NH4+ fertilizers.

    Science.gov (United States)

    Guillén, J; Muñoz-Muñoz, G; Baeza, A; Salas, A; Mocanu, N

    2017-03-01

    Inorganic fertilizers are used as agricultural countermeasures intended to inhibit the soil to plant transfer of radionuclides after a radioactive fallout. Two NH 4 + fertilizers, diammonium phosphate (DAP) and NPK, were applied to soil contaminated with a mixture of radionuclides to analyze whether they modify the transfer of 137 Cs, 90 Sr, and 60 Co and stable elements (K, Na, Ca, and Mg) to wheat plantlets grown under controlled laboratory conditions. DAP introduced NH 4 + in the soil, which can increase 137 Cs transfer, while NPK also introduced K + , which can decrease it. The application of DAP increased the accumulation of 137 Cs in wheat plantlets with increasing application rate, so did the 137 Cs/K in plantlets. Regarding the NPK application, the 137 Cs increased in all treatments, but at maximum rate, the available K introduced by the fertilizer was probably able to partially satisfy the nutritional requirements of the wheat plantlet and the 137 Cs decreased relative to the recommended rate. The 137 Cs/K ratio in plantlet decreased with increasing NPK rates. The transfer of 90 Sr increased with increasing DAP rate and only at the maximum NPK rate. The 60 Co transfer only increased at the maximum application rates for DAP and NPK. These modifications should be considered when using these fertilizers as agricultural countermeasures.

  2. Studies on the radioactive contamination due to nuclear detonations VI. Theoretical analysis of the radioactive contamination due to Sr90 and Cs137

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    In view of the considerably different values of the fallout rate and the cumulative deposition of Sr 90 and Cs 137 reported from different parts of Japan, the author attempted to estimate the ranges of the fallout rate and of the cumulative deposition of Sr 90 and Cs 137 for different parts of Japan based upon the theoretical consideration

  3. Influence of cultivar specificity on Cs 137 and Sr 90 accumulation in green part and seeds of soya plants

    International Nuclear Information System (INIS)

    Gutseva, G.Z.; Goloveshkin, V.V.

    2008-01-01

    As a result of investigation carried out with soya sorts zoned in Belarus on soddy-podsolic sandy soils contaminated as a result of Chernobyl accident with Cs 137 and Sr 90 a high sort selectivity in accumulation of the radionuclides is established. (authors)

  4. Biotechnological potential of Azolla filiculoides for biosorption of Cs and Sr: Application of micro-PIXE for measurement of biosorption.

    Science.gov (United States)

    Ghorbanzadeh Mashkani, Saeid; Tajer Mohammad Ghazvini, Parisa

    2009-03-01

    The presence of Cs and Sr in culture medium of Azolla filiculoides caused about 27.4% and 46.3% inhibition of biomass growth, respectively, in comparison to A. filiculoides control weight which had not metals. Biosorption batch experiments were conducted to determine the Cs and Sr binding ability of native biomass and chemically modified biosorbents derived from Azolla namely ferrocyanide Azolla sorbents type 1 and type 2 (FAS1 and FAS2) and hydrogen peroxide Azolla sorbent (HAS). The best Cs and Sr removal results were obtained when A. filiculoides was treated by 2M MgCl(2) and 30ml H(2)O(2) 8mM at pH 7 for 12h and it was then washed by NaOH solution at pH 10.5 for 6h. Pretreatment of Azolla have been suggested to modify the surface characteristics which could improve biosorption process. The binding of Cs and Sr on the cell wall of Azolla was studied with micro-PIXE and FT-IR.

  5. Methods of determination of the dynamics of mobile form of Cs 137 and Sr 90 in soils within Chernobyl catastrophe

    International Nuclear Information System (INIS)

    Osetskaya, V.V.

    2002-01-01

    In this paper the impact of the most significant mechanisms of migration of radionuclides are considered: diffusion of free and absorbed ions, migration colloid atoms transmission etc. on the dynamics of mobile forms of Cs 137 and Sr 90 in soils

  6. Transfer Factor of Radioactive Cs and Sr from Egyptian Soils to Roots and Leafs of Wheat Plant

    International Nuclear Information System (INIS)

    Abu Khadra, S.A.; Abdel Fattah, A.T.; Eissa, H.S.; Abdel Sabour, M.F.

    2009-01-01

    Transfer factors (TFs) of long lived radionuclide such as 137 Cs and 90 Sr from three different Egyptian soils type to wheat plant have been studied by radiotracer experiments. Most typical Egyptian soils (sandy, sandy loam and clayey) from three different locations (Al -Oboor, Abu- Zaabal and Shebeen cities) were selected for the experiments carried out under outdoor conditions. The plant selected was wheat because the high consumption of wheat in Egypt. In the present study radioactive strontium and caesium uptake from different types of soil was investigated .These radionuclide showed a considerable difference in their distribution within the plant .The results showed that soil type influences the transfer factors. Sandy soil resulted in the highest transfer factor for both (Cs and Sr) from soil to wheat. TFs for leafs were higher than those for roots in case of 90 Sr (for all types of soil). However, TFs of ( 137 Cs) for roots were higher than those for leafs for all soils. Grains of the wheat showed the lowest transfer factor for the Cs and Sr (for all types of soil)

  7. Crystal Growth and Scintillation Properties of Eu2+ doped Cs4CaI6 and Cs4SrI6

    Science.gov (United States)

    Stand, L.; Zhuravleva, M.; Chakoumakos, B.; Johnson, J.; Loyd, M.; Wu, Y.; Koschan, M.; Melcher, C. L.

    2018-03-01

    In this work we present the crystal growth and scintillation properties of two new ternarymetal halide scintillators activated with divalent europium, Cs4CaI6 and Cs4SrI6. Single crystals of each compound were grown in evacuated quartz ampoules via the vertical Bridgman technique using a two-zone transparent furnace. Single crystal X-ray diffraction experiments showed that both crystals have a trigonal (R-3c) structure, with a density of 3.99 g/cm3 and 4.03 g/cm3. The radioluminescence and photoluminescence measurements showed typical luminescence properties due to the 5d-4f radiative transitions in Eu2+. At this early stage of development Cs4SrI6:Eu and Cs4CaI6:Eu have shown very promising scintillation properties, with light yields and energy resolutions of 62,300 ph/MeV and 3.3%, and 51,800 photons/MeV and 3.6% at 662 keV, respectively.

  8. Evolution of 137Cs and 90Sr content of the main foodstuff in Bucharest area after the Chernobyl accident

    International Nuclear Information System (INIS)

    Toader, M.; Vasilache, R.A.

    1997-01-01

    Soon after the Chernobyl accident, the radioactive cloud, carrying the nuclides released into the atmosphere, reached Romania and, due to the rainy weather, an important fallout occurred over the Romanian territory. The most important contaminants for Romania were I 131 , Cs 134 , Cs 137 and Sr 90 . As in many other countries, in the first days, I 131 had the main contribution to the irradiation dose released to the population. After its decay, and the decay of other short-lived radionuclides, Cs 137 and Sr 90 remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. To assess the radioactive burden of foods, a long term, large scale survey was initiated at the National Institute of Hygiene and Public Health (INISP). These results were then used to assess the doses committed to cesium and strontium intake and the excedentary cancer risk for the population from Bucharest area

  9. Interconnection between precipitation density, soil contamination levels and 90Sr and 137Cs content in food stuffs

    International Nuclear Information System (INIS)

    Knizhnikov, V.A.; Petukhova, Eh.V.

    1980-01-01

    Presented are the data dynamically characterizing the density of radioactive fallout, contamination of soil and the main kinds of food stuffs with 137 Cs and 90 Sr. It is shown that 90 Sr contamination of bakery products in the country within the whole period of observation is in direct dependence on the density of atmospheric fallouts as a whole in the northern hemisphere. In the reverse, 90 Sr potato contamination primarily correlates with nuclide content in the soil. The dependence between milk contamination and fallout density has an intermediate character as compared with the above types of food stuffs. The same is true for 137 Cs, but a clear tendency to a faster decrease in the level of food stuffs contamination is observed. The importance of the soil way in food stuffs contamination and peculiarities of nuclide migration in food stuffs from various types of soil are considered

  10. Separation and immobilization of Sr and Cs contained in acidic media by using inorganic ion-exchangers. Literature survey

    Energy Technology Data Exchange (ETDEWEB)

    Yamagishi, Isao [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-07-01

    The present study deals with the survey of inorganic ion-exchangers suitable for separation and immobilization of Sr and Cs contained in acidic high-level liquid waste. The stabilities of published waste forms and their preparation processes were evaluated from the standpoint of conversion of exchangers containing Sr and Cs into appropriate waste forms. The essential results are below. (1) For separation and immobilization of Cs, crystalline silicotitanate seems to be the most promising exchanger. Insoluble ferrocyanides and phosphates are not suitable for immobilization without additives. Mordenite is inexpensive and commercially available but it would dissolve in highly acidic media. (2) For selective separation of Sr, there is no promising exchanger up to now. It is necessary either to modify separation condition or to synthesize a novel exchanger. (3) Soluble salts, glasses and ceramics are proposed as a storage or disposal form of separated Sr and Cs. Ceramics sintered by hot-pressing are favorable waste forms of inorganic ion-exchangers but their leachabilities and thermal conductivities are largely influenced by qualities of products. Crystallinity of a sintered exchanger depends on its composition. Exchanges of low Cs contents are often converted into amorphous materials whose chemical stabilities depend on solubilities of components of exchangers. (4) A new exchanger to be synthesized is crystalline and selective toward Sr and Cs. One meq/g is enough for Sr and Cs capacities, which are restricted by thermal and transmutation effects. Composition of the exchanger should be selected from the point of a scenario of separation and disposal. The solubilities of SiO{sub 2}, TiO{sub 2}, ZrO{sub 2}, Nb{sub 2}O{sub 5} and Ta{sub 2}O{sub 5} are low in acidic media and those of Al{sub 2}O{sub 3}, TiO{sub 2} and ZrO{sub 2}, in disposal circumstances. (5) Future works are optimization of separation scheme including development of exchangers, simplification of

  11. Determination of 137Cs and 90sr in Human Food and Effective Dose Assessment due to Food Consumption in the Environment of Region Uzice

    International Nuclear Information System (INIS)

    Arsic, V.; Bogojevic, S.; Eremic-Savkovic, M.; Ilic, J.; Javorina, Lj.; Tanaskovic, I.

    2013-01-01

    This paper provides the data on activity measurements of 137Cs and 90Sr in the foodstuff characteristic for the nutrition of the population: vegetables, fruit, meat, crops, dairy products and milk in 2007, 2008 and 2011 in the environment of region Užice. This region was the most contaminated region of Serbia after the Chernobyl accident. The 137Cs activity concentrations were determined by gamma-spectrometry while 90Sr was determined after radiochemistry separations, using αβ proportional counter. Based on the presented results of the 137Cs and 90Sr activity concentration measurements, the effective doses received by the population through food intake were estimated. The annual effective doses due to 137Cs and 90Sr activity in the human food were 2.00 μSv (for 137Cs) and 1.32 μSv (for 90Sr) in 2007, 1.02 μSv (for 137Cs) and 0.45 μSv (for 90Sr) in 2008, 1.25 μSv (for 137Cs) and 1.07 μSv (for 90Sr) in 2011. They were well below recommended individual annual dose limit.(author)

  12. Microsphere zeolite materials derived from coal fly ash cenospheres as precursors to mineral-like aluminosilicate hosts for 135,137Cs and 90Sr

    International Nuclear Information System (INIS)

    Vereshchagina, Tatiana A.; Vereshchagin, Sergei N.; Shishkina, Nina N.; Vasilieva, Nataly G.; Solovyov, Leonid A.; Anshits, Alexander G.

    2013-01-01

    Hollow microsphere zeolite materials with a bilayered zeolite/glass crystalline shell bearing NaP1 zeolite were synthesized by the hydrothermal treatment of coal fly ash cenospheres (Si/Al = 2.7) in an alkaline medium. Cs + and/or Sr 2+ forms of zeolitized cenospheres with the different Cs + and/or Sr 2+ loading were prepared by the ion exchange from nitrate solutions. The resulted (Cs,Na)P1, (Sr,Na)P1 and (Cs,Sr,Na)P1 bearing microsphere zeolites were converted to glass ceramics by heating at 900–1000 °C. The differential scanning calorimetry and quantitative phase analysis were used to monitor the solid-phase transformation of the initial and ion exchanged zeolite materials. It was established that the final solidified forms of Cs + and/or Sr 2+ are glass–crystalline ceramic materials based on pollucite–nepheline, Sr-feldspar–nepheline and Sr-feldspar–pollucite composites including ∼60 wt.% of the major host phases (pollucite, Sr-feldspar) and 10–20 wt.% of glass. The 137 Cs leaching rate of 4.1 × 10 −7 g cm −2 day −1 was determined for the pollucite glass–ceramic according to Russian State Standard (GOST) No. 52126 P-2003 (7 day, 25 °C, distilled water)

  13. Influence of humic acid on migration of 60Co, 85Sr and 137Cs in coastal sandy soil

    International Nuclear Information System (INIS)

    Tanaka, Tadao; Ni Shiwei.

    1993-10-01

    Sorption and migration experiments were performed by both batch and column methods, to study influence of humic acid complexing on the mobility of 60 Co, 85 Sr and 137 Cs in a coastal sandy soil. The study focuses on a correlation between molecular-weight of dissolved humic acid and ability of the complexing with the radionuclides in liquid phase. Dissolved humic acid was complexed with 60 Co and 85 Sr. The interaction ability of 60 Co was independent of molecular-weight of humic acid, while that of 85 Sr depended on. The mobility of 60 Co increased under the condition with coexistence of humic acid as well as its sorption ratio decreased. The distribution profile of molecular-weight of 60 Co was kept at a constant in the solution before and after the sorption experiment, due to completing the sorption and complexation equilibrium. The mobility of 85 Sr increased under the condition with coexistence of humic acid, in spite of the sorption ratio of 85 Sr was not affected by the coexistence. Such contradiction was caused by different kinetics between the batch and column methods. The sorption ability and mobility of 137 Cs were not affected by the coexistence of the humic acid. (author)

  14. Vertical migration of 85Sr, 137Cs and 131I in various arable and undisturbed soils

    International Nuclear Information System (INIS)

    Palagyi, S.; Palagyiova, J.

    2002-01-01

    Vertical migration of 85 Sr, 137 Cs and 131 I in some arable and undisturbed single-contaminated soils was studied by gamma-spectrometry measurements in lysimetric laboratory conditions applying irrigation of the soil profiles with wet atmospheric precipitation for about one year (except radioiodine). A new simple exponential compartment (box) model was derived, allowing us to calculate the migration rate constants and migration rates in the individual soil layers (vertical sections) as well as the total vertical migration rate constants and total vertical migration rates of radionuclides in the bulk soil horizon. The data from the time dependence of the depth activity distribution (radionuclide concentration along the vertical soil profile) were used to test the model. The migration rate constants and migration rates were found to be affected by the contaminating radionuclides as well as by the site, type and depth of the soil. The relaxation times of the radionuclides in the soil horizons were calculated. The effects on the rate parameters of the permanent grass cover and the zeolite applied onto the arable soil surfaces were also investigated

  15. Determination of 137Cs, 90Sr, 40K radionuclides in food grain and commercial food grain products

    International Nuclear Information System (INIS)

    Solecki, J.; Kruk, M.

    2011-01-01

    Following up transfer of strontium from soil to plants requires determination of isotope in the surface layer of soil and a chosen plant. The most endangered food products are plants including commonly grown grain, which constitutes a basic feeding component for both people and animals. Indeed large amounts of 137 Cs, 90 Sr get into organisms of people and animals with the food, therefore determination of radioactivity of elements in food products and animal fodder is very essential. Choice of proper diet allows to limit the level of human organism denaturation. The aim of this paper was to study relocation of 90 Sr, 137 Cs, 40 K isotopes from soil to grain and then from grain to food products. There were investigated soil, wheat, barley, groats, flour, macaroni and breakfast flakes. Based on the obtained results there were calculated effective weighted doses [nSv] from consumption of 1 kg of a product for different age groups. (author)

  16. Determination of Sr, Ba, Rb, and Cs in biological reference materials using a radiochemical NAA group separation procedure

    International Nuclear Information System (INIS)

    Mizera, J.; Randa, Z.

    2008-01-01

    Strontium, barium, rubidium, and cesium in selected, predominantly biological, reference materials (NIST 1515, 1547, 1549, 1566a, 1571, 1577b, 2704, CTA-OTL-1, and Bowen's Kale) were determined using neutron activation analysis (NAA) in two different analytical modes - instrumental NAA with epithermal neutrons (ENAA), and NAA with radiochemical group separation of Sr-Ba and Rb-Cs (RNAA). The ENAA mode was based on long-term (5 h) irradiation of samples in a Cd shielding. The RNAA procedure was based on long-term (20 h) irradiation of samples, their decomposition / dissolution by alkaline-oxidative fusion, and precipitation of Sr and Ba sulfates, and sorption of Rb and Cs onto ammonium phosphomolybdate (APM). Both methods provided element contents in the analyzed reference materials consistent with certified and/or literature values. (author)

  17. Screening of plant species for comparative uptake abilities of radioactive Co, Rb, Sr and Cs from soil

    International Nuclear Information System (INIS)

    Gouthu, S.; Arie, T.; Ambe, S.; Yamaguchi, I.

    1997-01-01

    In case of radioactive fallout, persistence of long lived nuclides in soil and subsequent transfer into the food chain through plants over a long period is the key factor. The possibility of 'phytoremediation'is suggested to reduce the radionuclides in soil. To exploit the natural potential of some plants in absorbing or accumulating certain radionuclides and depleting the soil radioactivity, thirty-two plant species were tested under laboratory conditions for their comparative ability in taking up radioactive Rb, Co, Sr and Cs. Broccoli and tomato for Co; tomato, chard, sunflower and cucumber for Rb; cucumber, sunflower and turnip (Kyona) for Sr; and tomato, chard and cucumber for Cs were found to be effective compared to other species tested. (author)

  18. Screening of plant species for comparative uptake abilities of radioactive Co, Rb, Sr and Cs from soil

    Energy Technology Data Exchange (ETDEWEB)

    Gouthu, S; Arie, T; Ambe, S; Yamaguchi, I [Institute of Physical and Chemical Research, Wako, Saitama (Japan)

    1997-08-01

    In case of radioactive fallout, persistence of long lived nuclides in soil and subsequent transfer into the food chain through plants over a long period is the key factor. The possibility of `phytoremediation`is suggested to reduce the radionuclides in soil. To exploit the natural potential of some plants in absorbing or accumulating certain radionuclides and depleting the soil radioactivity, thirty-two plant species were tested under laboratory conditions for their comparative ability in taking up radioactive Rb, Co, Sr and Cs. Broccoli and tomato for Co; tomato, chard, sunflower and cucumber for Rb; cucumber, sunflower and turnip (Kyona) for Sr; and tomato, chard and cucumber for Cs were found to be effective compared to other species tested. (author). 13 refs.

  19. Long-term monitoring and analysis of 90Sr and 137Cs concentrations in rice, wheat and soils in Japan from 1959 to 2000

    International Nuclear Information System (INIS)

    Komamura, M.; Tsumura, A.; Yamaguchi, N.; Fujiwara, H.; Kihou, N.; Kodaira, K.

    2006-01-01

    Atmospheric nuclear tests in the 1950s and thereafter had showered radioactive fallout throughout Japan. Therefore, radioactive contamination of crops cultivated in Japan was concerned. We continued to monitor concentrations of 90Sr and 137Cs in rice, wheat and soils collected annually from sixteen national and prefectural experimental farms for forty-two years, from 1959 to 2000. In 1963, when the largest annual precipitation of radioactive fallout was observed, 90Sr and 137Cs concentration in rice and wheat reached at their maximum; 0.27 Bq/kg for 90Sr and 4.2 Bq/kg for 137Cs in polished rice and 12 Bq/kg for 90Sr and 44 Bq/kg for 137Cs in wheat grain. The concentration of 90Sr and 137Cs in the plowed layer of paddy and upland soils reached maximum from 1963 to 1966. After 1966, concentrations of 90Sr and 137Cs in polished rice, wheat grain, and soils were gradually decreased although there were some minor fluctuations. The Chernobyl nuclear power plant accident in 1986 caused contamination of wheat grain by 137Cs up to 6.0 Bq/kg. However, the concentration of 137Cs in wheat grain decreased to its normal level in the following year. There was no evidence for the polished rice contamination in Japan that could be ascribed to the accident at Chernobyl. Based on the analyses of the data above, we made several interesting findings as follows: a) The accumulated amounts of 90Sr and 137Cs in fallout during cultivation period were highly correlated with those concentrations in husked rice, polished rice and wheat grain. The estimate equations derived from the correlations were accurate enough for quick prediction of contamination level of polished rice and wheat grain based on 90Sr and 137Cs contents in fallout in case of contingencies. b) The sensitive response of 90Sr and 137Cs in polished rice and wheat grain to concentrations of fallout suggested that direct absorption of 90Sr and 137Cs from radioactive fallout deposited on plant body played important role. In 1963

  20. The volumes of accumulation of Cs-137 and Sr-90 per species and variety of agricultural plants

    International Nuclear Information System (INIS)

    Bogdevich, I.M.; Shmigelskaya, I.D.; Efimova, I.A.; Putyatin, Yu.V.

    2001-01-01

    The accumulation of radionuclides in various species and varieties of agricultural plants on the same conditions of soil contaminated by radionuclides and agrochemical exponents can differ hundred times. The differences in accumulation of Cs-137 and Sr-90 are less -up to 3-4 times. The article grades the basic plants cultivated on contaminated soils per volume of Cs-137 and Sr-90 as well as per crop yield. It is possible to recommend selecting the species and varieties of agricultural plants having minimal capabilities of accumulation as a simple economically justified way of reducing the contamination of agricultural produce in general. The solving of problems connected with agriculture on the contaminated territory occupies one of the leading places in the complex of actions on the consequences of Chernobyl disaster liquidation. The researches revealed that 70% of collective dose is formed by the radionuclides receipt into a human organism with food. Eventually radionuclides contents in agricultural production reduce. This process is more expressed for Cs-137 caused by protective actions realization as well as gradually fixing of Cs-137 in soils due to natural factors of decay and fixation. Sr-90 mobility and its availability to plants is not reduced, even tends to increase. Biological features of plants reveal in their different ability to absorb nutritional elements from soil. Because of that radionuclides availability and amount of their including in food chains essentially depend on the level of contra actions applied, natural conditions (soil types, granulometric structure, humidifying mode, agrochemical conditions) and features of crops. The action of Cs-137 and Sr-90 in the system soil-plant has a range of distinctive features. At same density of soil contamination Sr-90 penetration into plants much higher than Cs-137 one. The cause is in difference of radionuclides contents forms in soils. Cs-137 is strongly fixed in soil, but Sr-90 is in exchange form

  1. Diffusion of Na(I), Cs(I), Sr(II) and Eu(III) in smectite rich natural clay.

    Science.gov (United States)

    Kasar, Sharayu; Kumar, Sumit; Bajpai, R K; Tomar, B S

    2016-01-01

    Diffusion of Na(I), Cs(I), Sr(II) and Eu(III) in smectite rich natural clay, proposed as a backfill material in the Indian geological repository, was studied using the out-diffusion method. Radiotracers (22)Na, (137)Cs, (85)Sr and (154)Eu were used; the first three are carrier-free enabling experimental work at sub-micromolar metal ion concentration, and Eu(III) tracer (154)Eu was used at sub millimolar concentration. An out-diffusion methodology, wherein a thin planar source of radioactivity placed between two clay columns diffuses out, was used to obtain the apparent diffusion coefficient (Da) values. This methodology enabled determination of diffusion coefficient even for strongly sorbing (154)Eu. Da values for (22)Na, (137)Cs, (85)Sr and (154)Eu were 2.35 (±0.14) × 10(-11), 2.65 (±0.09) × 10(-12), 3.32 (±0.15) × 10(-11) and 1.23 (±0.15) × 10(-13) m(2) s(-1), respectively. Da values were found to be in fair agreement with literature data reported for similar mineralogical sediments. Sorption of radionuclides on the clay was also determined in the present study and differences in Da values were rationalized on the basis of sorption data. Distribution ratios (Kd) for Cs(I) and Eu(III) were higher than that for Sr(II), which in turn was higher than that for Na(I). Copyright © 2015 Elsevier Ltd. All rights reserved.

  2. A pilot study on the transfer of {sup 137}Cs and {sup 9}Sr to horse milk and meat

    Energy Technology Data Exchange (ETDEWEB)

    Semioshkina, N. [GSF-Institut fuer Strahlenschutz, Postfach 1129, D-85788 Neuherberg (Germany)]. E-mail: semi@gsf.de; Voigt, G. [Agency' s Laboratories - Seibersdorf, IAEA, 1400-Vienna (Austria)]. E-mail: g.voigt@iaea.org; Fesenko, S. [Agency' s Laboratories - Seibersdorf, IAEA, 1400-Vienna (Austria)]. E-mail: s.fesenko@iaea.org; Savinkov, A. [Scientific Research Agricultural Institute of the National Biotechnology Center, Ministry for Science and Higher Education of the Republic of Kazakhstan (SRAI), 480544 Gvardeiski (Kazakhstan)]. E-mail: chebotar@srai.kz; Mukusheva, M. [National Nuclear Centre of Republic of Kazakhstan, Kurchatov 490021 (Kazakhstan)]. E-mail: mukusheva@nnc.kz

    2006-07-01

    The radiological assessment of the impact of nuclear weapon's testing on the Semipalatinsk Test Site (STS) on the local population requires comprehensive site-specific information on radionuclide behaviour in the environment. However, information on radionuclide behaviour in the conditions of the STS is rather sparse and, in particular, there are no data in the literature on parameters of radionuclide transfer from feed to horse products proofed to be important contributors to the internal dose to the local population. The transfer of {sup 137}Cs and {sup 9}Sr to horse milk and meat was studied under laboratory and field conditions: in controlled experiment with three lactating horses maintained in the Kazakh Agricultural Research Institute, and in field measurements of horse products taken from horses grazing at the Semipalatinsk Test Site. The equilibrium transfer factors from feed to horse milk and meat were estimated to be 0.012 d l{sup -1} and 0.035 d kg{sup -1} for {sup 137}Cs and 0.0022 d l{sup -1} and 0.003 d kg{sup -1} for {sup 9}Sr, respectively. The biological half-lives were approximated by a sum of two exponentials amounting to 3 (85%) and 15 (15%) days for {sup 137}Cs and 3.5 (70%) and 100 (30%) days for {sup 9}Sr. The highest {sup 137}Cs transfer has been found to be to spleen, followed by lung, heart, muscles, kidneys, intestine, and finally skin and bones. For {sup 9}Sr, the maximum activity concentration was observed in bones; contamination of other tissues is rather uniform except for liver and intestine with a factor of about 2 higher than muscles.

  3. A pilot study on the transfer of 137Cs and 9Sr to horse milk and meat

    International Nuclear Information System (INIS)

    Semioshkina, N.; Voigt, G.; Fesenko, S.; Savinkov, A.; Mukusheva, M.

    2006-01-01

    The radiological assessment of the impact of nuclear weapon's testing on the Semipalatinsk Test Site (STS) on the local population requires comprehensive site-specific information on radionuclide behaviour in the environment. However, information on radionuclide behaviour in the conditions of the STS is rather sparse and, in particular, there are no data in the literature on parameters of radionuclide transfer from feed to horse products proofed to be important contributors to the internal dose to the local population. The transfer of 137 Cs and 9 Sr to horse milk and meat was studied under laboratory and field conditions: in controlled experiment with three lactating horses maintained in the Kazakh Agricultural Research Institute, and in field measurements of horse products taken from horses grazing at the Semipalatinsk Test Site. The equilibrium transfer factors from feed to horse milk and meat were estimated to be 0.012 d l -1 and 0.035 d kg -1 for 137 Cs and 0.0022 d l -1 and 0.003 d kg -1 for 9 Sr, respectively. The biological half-lives were approximated by a sum of two exponentials amounting to 3 (85%) and 15 (15%) days for 137 Cs and 3.5 (70%) and 100 (30%) days for 9 Sr. The highest 137 Cs transfer has been found to be to spleen, followed by lung, heart, muscles, kidneys, intestine, and finally skin and bones. For 9 Sr, the maximum activity concentration was observed in bones; contamination of other tissues is rather uniform except for liver and intestine with a factor of about 2 higher than muscles

  4. A pilot study on the transfer of 137Cs and 90Sr to horse milk and meat.

    Science.gov (United States)

    Semioshkina, N; Voigt, G; Fesenko, S; Savinkov, A; Mukusheva, M

    2006-01-01

    The radiological assessment of the impact of nuclear weapon's testing on the Semipalatinsk Test Site (STS) on the local population requires comprehensive site-specific information on radionuclide behaviour in the environment. However, information on radionuclide behaviour in the conditions of the STS is rather sparse and, in particular, there are no data in the literature on parameters of radionuclide transfer from feed to horse products proofed to be important contributors to the internal dose to the local population. The transfer of 137Cs and 90Sr to horse milk and meat was studied under laboratory and field conditions: in controlled experiment with three lactating horses maintained in the Kazakh Agricultural Research Institute, and in field measurements of horse products taken from horses grazing at the Semipalatinsk Test Site. The equilibrium transfer factors from feed to horse milk and meat were estimated to be 0.012 dl(-1) and 0.035 dkg(-1) for (137)Cs and 0.0022 dl(-1) and 0.003 dkg(-1) for (90)Sr, respectively. The biological half-lives were approximated by a sum of two exponentials amounting to 3 (85%) and 15 (15%) days for 137Cs and 3.5 (70%) and 100 (30%) days for 90Sr. The highest 137Cs transfer has been found to be to spleen, followed by lung, heart, muscles, kidneys, intestine, and finally skin and bones. For90Sr, the maximum activity concentration was observed in bones; contamination of other tissues is rather uniform except for liver and intestine with a factor of about 2 higher than muscles.

  5. Comparative analysis of species-based specificity in Sr 90 and Cs 137 accumulation demonstrated by ligneous plant forest communities

    International Nuclear Information System (INIS)

    Martinovich, B.S.; Vlasov, V.K.; Sak, M.M.; Golushko, R.M.; Afmogenov, A.M.; Kirykhin, O.V.

    2004-01-01

    The authors provided field-proven study of Sr 90 and Cs 137 absorption activity demonstrated by Pinus silvestris L.; Piceae abies (L.) Roth.; Quercus rubra L.; Acer platanoides L.; Betula pendula Roth.; Tilia cordata Mill, under identical habitat conditions. The above plants were examined after 5-year growth period on radionuclide-contaminated soil. To a great extent, such parameters as radionuclide accumulation in experimental plants and accumulation activity were determined by the plants' bio-ecological properties. (Authors)

  6. The dynamics of Cs-137 and Sr-90 pollution of surface water systems of Belarus of Chernobyl origin

    Energy Technology Data Exchange (ETDEWEB)

    Datskevich, P.O.; Dolgov, V.M.; Golikov, Yu.N.; Zemskov, V.N.; Komissarov, F.D.; Khvaley, O.D.

    1995-12-31

    The Belarus water ecosystems have been the object of investigation concerning currents and reservoirs affected by the Chernobyl APS catastrophe. The radio monitoring of samples of water systems components was implemented with the use of modern methods of radiochemistry and ionizing radiations registration. The factual material of water ecosystems sites observation presented its analysis is done and the regularities, tendencies and anomalies are revealed in the Cs-137 and Sr-90 distribution, transport and accumulation for water components.

  7. Hydrothermal preparation of zeolite Li-A and ion exchange properties of Cs and Sr in salt waste

    International Nuclear Information System (INIS)

    Lee, S. H.; Kim, J. G.; Lee, J. H.; Kim, J. H.

    2005-01-01

    An advanced spent fuel management process that were based on Li reduction of the oxide spent fuel to a metallic form will generate a LiCl waste. Zeolite A has been reported as a promising immobilization medium for waste salt with CsCl and SrCl 2 . However, Sodium is accumulated as an ionic form (Na + -ion) in molten salt during ion exchange step between Na + -ion in zeolite A and Li + -ion in the molten salt. Therefore, zeolite Na-A need to be replaced by the Li-type zeolite for recycling the salt waste by removing the Cs and Sr ions. In this study, the hydrothermal preparation of zeolite Li-A was performed in 350ml pressure vessel by P. Norby method. The preparation characteristics of zeolite Li-A was investigated. And the ion exchange properties of Cs and Sr in molten LiCl salt were investigated under the condition of 923K using zeolite 4A and prepared zeolite Li-A

  8. Test of 134Cs, 85,89Sr leaching rate in a resemble vitrifiable cement waste form

    International Nuclear Information System (INIS)

    Lin Meiqiong; Wei Feng; Yin Qi; Fan Xianhua; Xu Shengli; Li Yongde

    2003-01-01

    A novel material--resemble vitrifiable cement for conditioning low and mediate level radioactive waste has been developed. Waste form has been characterized for their physical and chemical performance, phase composition. The cement formulation has been patented. In this experiment the cement is mixed with simulated wastes spiked with 134 Cs and 85,89 Sr by 5 min at least. The Ratio of the waste to the cement is 0.45-0.55. The mixture is packed into cylindrical molds which has the same dimension of diameter and height . The grouts are cured for a period of 28 d in a room temperature curing chamber at an atmospheric pressure. The cured waste form is then completely immersed into deionized water. According to standard GB7023-86, leaching rate of 134 Cs and 85,89 Sr are measured. The result shows that the leaching rate of the species 134 Cs and 85,89 Sr is to be on the order 10 -4 and 10 -5 on the 42 d immersion, respectively and is better than that of commercial cement

  9. New aluminium-rich alkali slag matrix with clay minerals for immobilizing simulated radioactive Sr and Cs waste

    International Nuclear Information System (INIS)

    Qian Guangren; Sun, Darren Delai; Tay, Joo Hwa

    2001-01-01

    A new aluminium-rich alkali-activated slag matrix (M-AAS) with clay absorbents has been developed for immobilization of simulated radioactive Sr or Cs waste by introducing metakaolin, natural zeolite and NaOH-treated attapulgite clay minerals into alkali-activated slag matrix (AAS). The results revealed that the additions of metakaolin and clay absorbents into the cementitious matrixes would greatly enhance the distribution ratio, R d , of selective adsorption whether the matrix was OPC matrix or AAS matrix. The new immobilizing matrix M-AAS not only exhibited the strongest selective adsorption for both Sr and Cs ions, but also was characterized by lower porosity and small pore diameter so that it exhibited the lowest leaching rate. Hydration product analyses also demonstrated that (Na+Al)-substituted C-S-H(I) and self-generated zeolite were major hydration products in the M-AAS matrix, which provided this new immobilizing matrix with better selective adsorption on Sr and Cs and lower leaching rate

  10. Inter comparison of 90Sr and 137Cs contents in biologic samples and natural U in soil samples

    International Nuclear Information System (INIS)

    Liu Jianfen; Zeng Guangjian; Lu Xuequan

    2001-01-01

    The results of the 90 Sr and 137 Cs contents in biologic samples and the natural U in soil samples obtained in a joint effort by fourteen environmental radiation laboratories in the Chinese environmental protection system were analyzed and compared. Two kinds of biologic samples and one kind of soil samples were used for inter comparison. Of which, one kind of biologic samples (biologic powder samples) and the soil samples came from the IAEA samples were environmental and the reference values were known. The another kind of biologic samples were environmental tea-leaf that were taken from a tea garden near Hangzhou. The mean values obtained by all the joined laboratories was used as the reference. The inter comparison results were expressed in terms of the deviation from the reference value. It was found that the deviation of the 90 Sr and 137 Cs contents of biologic powder samples ranged from -15.4% to 26.5% and -15.0% to 0.4%, respectively. The deviation of the natural U content ranged from -25.5% to 7.3% for the soil samples. For the tea-leaf, the 90 Sr deviation was -22.7% to 19.1%, and the 137 Cs data had a relative large scatter with a ratio of the maximum and the minimum values being about 7. It was pointed out that the analysis results offered by different laboratories might have involved system errors

  11. 90Sr and 137Cs contamination of wheat produced in Japan. Survey and analysis during the years 1959 through 1995 including the Chernobyl accident

    International Nuclear Information System (INIS)

    Komamura, Misako; Tsumura, Akito; Kihou, Nobuharu; Kodaira, Kiyoshi

    2002-01-01

    This paper attempts to discuss the influences of global-scale radioactive fallout on wheat produced in Japan. For this purpose, a set of wheat samples was collected annually from sixteen National and Prefectural Experimental Farms during the years from 1959 to 1995. According to the graph presenting year-to-year variations in the nationwide averages of 90 Sr and 137 Cs contents (mBq/kg) in wheat kernels, the sharp peak was first marked in 1963 with 12300 for 90 Sr and 43600 for 137 Cs. In 1966, however, the nuclide contents dropped drastically to 2360 for 90 Sr and 2870 for 137 Cs respectively. In the years following, both nuclides continued to decrease slowly although there were minor fluctuations. It is noticeable that low-level 137 Cs contamination was caused in Japan's wheat in 1981, the year after the nuclear testing in China. It is also noticeable that 137 Cs contents in wheat kernels increased to 5960 in 1986 when the Chernobyl nuclear power plant accident happened, although it dropped back to its normal level of 40 in the year after. The following are also discussed in this paper: Year to year variations in the ratio of 90 Sr to 137 Cs contents in wheat kernels and wheat flour. Regional differences in 90 Sr and 137 Cs contents in wheat kernels. Comparison of 90 Sr and 137 Cs contents in wheat kernels and unpolished rice. Direct and indirect pathways of 90 Sr and 137 Cs that contaminate wheat. Influence of the Chernobyl power plant accident. Suggestions about the ways of estimating the level of 137 Cs contamination in case of nuclear accidents, if any. (author)

  12. Assessment of 90Sr and 137Cs activity concentration in human tissues in Hungary following the Chernobyl accident

    International Nuclear Information System (INIS)

    Turai, I.; Sztanyik, B.L.

    1997-01-01

    Artificial radioisotope contamination of tissue samples of Hungarian citizens has been regularly monitored by our Institute since 1978. 90 Sr concentration of both extracted deciduous teeth and rib samples showed a slight but permanent tendency to decrease since then. 137 Cs content in the body of Hungarian individuals was monitored by whole body counter from the mid of 60s for about a decade while it became lower of the minimum detection limit (MDL). It could again be detected by in vivo measurements in May 1986, however, the 137 Cs content of human beings in Hungary fell below the detection limit within two years. Thus, the monitoring could only be continued by in vitro measuring of the 137 Cs activity concentration in human soft tissue samples

  13. Management of the Cs/Sr Capsule Project at the Hanford Site. Technology Readiness Assessment Report

    Energy Technology Data Exchange (ETDEWEB)

    None, None

    2018-01-01

    The Federal Project Director (FPD) for the U.S. Department of Energy (DOE), Richland Operations Office (RL) Waste Management and D&D Division (WMD) requested a Technology Readiness Assessment (TRA) for the Management of the Cesium/Strontium Capsule Storage Project (MCSCP) at the Waste Encapsulation and Storage Facility (WESF) on the Hanford Site in Washington State. The MCSCP CD-1 TRA was performed by a team selected in collaboration between the Office of Environmental Management (EM) Chief Engineer (EM-3.3) and RL, WMD FPD. The TRA Team included subject matter and technical experts having experience in cask storage, process engineering, and system design who were independent of the MCSCP, and the team was led by the Director of Operations and Processes from the EM Chief Engineer's Office (EM-3.32). Movement of the Cs/Sr capsules to dry storage, based on information from the conceptual design, involves (1) capsule packaging, (2) capsule transfer, and (3) capsule storage. The project has developed a conceptual process, described in 30059-R-02, "NAC Conceptual Design Report for the Management of the Cesium and Strontium Capsules Project", which identifies the five major activities in the process to complete the transfer from storage pool to pad-mounted cask storage. The process, shown schematically in Figure 1, is comprised of the following process steps: (1) loading capsules into the UCS; (2) UCS processing; (3) UCS insertion into the TSC Basket; (4) cask transport from WESF to CSA and (5) extended storage at the CSA.

  14. Procedure for independently estimating blanks and uncertainties for measured values of 90Sr and 137Cs concentrations in the Atlantic Ocean

    International Nuclear Information System (INIS)

    Kupferman, S.L.; Livingston, H.D.

    1979-01-01

    A procedure has been developed for independently estimating blanks and measurement uncertainties for measured values of 90 Sr and 137 CS concentrations in the Atlantic Ocean. The procedure depends on delineation of a region in the Atlantic Ocean which has never contained measurable quantities of these fission products. Such a region is defined. A simple model, with supporting data, is used to show that reported 137 Cs inventories in deep ocean sediments could have accumulated without ever raising concentrations of 137 Cs in this tracer-free volume above minimum detectable limits. Several examples are presented to show that the use of the procedure results in a substantial improvement in the quality of 90 Sr and 137 Cs data. The method is applicable to any laboratory that has determined 9 πSr and 137 Cs concentrations in samples collected from within the tracer-free volume. 10 refs

  15. Studies on the radioactive contamination due to nuclear detonations VI. Theoretical analysis of the radioactive contamination due to Sr{sup 90} and Cs{sup 137}

    Energy Technology Data Exchange (ETDEWEB)

    Nishiwaki, Yasushi [Nuclear Reactor Laboratory, Tokyo Institute of Technology, Tokyo (Japan); Nuclear Reactor Laboratoroy, Kinki University, Fuse City, Osaka Precture (Japan)

    1961-11-25

    In view of the considerably different values of the fallout rate and the cumulative deposition of Sr{sup 90} and Cs{sup 137} reported from different parts of Japan, the author attempted to estimate the ranges of the fallout rate and of the cumulative deposition of Sr{sup 90} and Cs{sup 137} for different parts of Japan based upon the theoretical consideration.

  16. Radioactive pollution of the Chernobyl cooling pond bottom sediments. II. Distribution of 137Cs, 241Am, 90Sr in a solid phase

    Directory of Open Access Journals (Sweden)

    L. S. Pirnach

    2011-12-01

    Full Text Available The second part of complex research of the Chernobyl cooling pond bottom sediments are presented Data about vertical distribution of radioactive pollution 137Cs, 241Am, 90Sr in a solid phase of sediments are received. Distribution coefficients 137Cs and 90Sr, selectivity coefficients of their exchange with similar cations and physical-chemical forms are defined. Results of research of radionuclide chemical recovery from the sediment samples are analyzed.

  17. Transfer factor of (90)Sr and (137)Cs to lettuce and winter wheat at different growth stage applications.

    Science.gov (United States)

    Al Attar, Lina; Al-Oudat, Mohammad; Safia, Bassam; Ghani, Basem Abdul

    2015-12-01

    The effect of clay soil contamination time on the transfer factors (Fvs) of (137)Cs and (90)Sr was investigated in four different growth stages of winter wheat and lettuce crops. The experiment was performed in an open field using lysimeters. The Fvs were the ratio of the activity concentrations of the radionuclides in crops to those in soil, both as dry weight (Bq kg(-1)). Significant difference of log-Fvs was evaluated using one-way Analysis of Variance (ANOVA). Basically, Fvs of (90)Sr were higher than those of (137)Cs, despite of the application stage or crop' variety. Higher Fvs for both radionuclides were observed for lettuce in comparison to winter wheat. Fvs of (90)Sr showed comparable trends for both crops with enhanced Fvs obtained when contamination occurred in early stages, i.e. 1.20 for lettuce and 0.88 and 0.02 for winter wheat, straw and grains, respectively. Despite the fluctuation noted in the pattern of Fvs for (137)Cs, soil contaminated at the second stage gave the highest Fvs for lettuce and grains, with geometric means of 0.21 and 0.01, respectively. However, wheat-straw showed remarkable increase in Fv for the latest contamination (ripening stage), about 0.06. It could be concluded that soil contamination at early growth stages would represent high radiological risk for the scenarios studied with an exception to (137)Cs in winter wheat-straw which reflected greater hazard at the latest application. Copyright © 2015 Elsevier Ltd. All rights reserved.

  18. Measurements of {sup 137}Cs and {sup 90}Sr in Swedish consumption milk between 1991 1996; Maetningar av {sup 137}Cs och {sup 90}Sr i konsumtionsmjoelk mellan 1991 och 1996

    Energy Technology Data Exchange (ETDEWEB)

    Moere, H

    1997-04-01

    The sources for the radioactivity are the nuclear weapons tests and the Chernobyl accident in 1986. Milk is sampled and measured as an important indicator of the Chernobyl load of radionuclides that cows can metabolize and that will ultimately give a dose to humans. Milk was responsible for 13-19% of the total intake of {sup 137}Cs from foodstuffs for the average person in 1994. Our milk measurement program covered 90% of all produced consumption milk in Sweden in 1995. Milk samples are taken every second month from the dairies. {sup 90}Sr is only measured on pooled yearly samples from some dairies; these dairies covered 50% of the total production of consumption milk in Sweden in 1995. The mean value per year of {sup 137}Cs for the whole country has decreased from 0.52 to 0.26 Bq/l between 1991 and 1996, which corresponds to a committed effective dose equivalent for humans of 1.1-0.50 microSv for {sup 137}Cs. For {sup 90}Sr during the 1991-1996 period the country-wide mean varied between 0.08 and 0.06 Bq/l, resulting in a committed effective dose equivalent of 0.4-0.3 microSv. 7 refs.

  19. Coprecipitation of trace amounts of 137Cs and 85Sr with [Na(18-Crown-6]BPh4 from neutral and alkaline solutions

    International Nuclear Information System (INIS)

    Kulyukhin, S.A.; Konovalova, N.A.; Rumer, I.A.; Kamenskaya, A.N.; Mikheev, N.B.

    2005-01-01

    Coprecipitation of 137 Cs and 85 Sr with [Na(18-crown-6]BPh 4 solid phase from aqueous, aqueous-ethanolic, and alkaline solutions is studied. 137 C s and 85 Sr co-crystallize with [Na(18-crown-6]BPh 4 from aqueous and aqueous-ethanolic solutions. The cocrystallization coefficients D of 137 Cs and 85 Sr from aqueous solutions are 2.6 ± 0.5 and 3.3 ± 0.3, respectively. For aqueous-ethanolic solutions, the corresponding values are 4.4 ± 0.5 and 3.4 ± 0.4. In the alkaline solutions (0.1 and 1 M NaOH), 54-74% of 137 Cs and 37-51% of 85 Sr pass into the [Na(18-crown-6)]BPh 4 solid phase, depending on the crown ether concentration in the system [ru

  20. The estimation of daily intake and organ content of Ca, Cs, I, K, Sr, Th and U in Indian population

    International Nuclear Information System (INIS)

    Jaiswal, D.D.; Dang, H.S.; Pullat, V.R.; Parameswaran, M.

    2000-01-01

    The analytical methods involving both instrumental and radiochemical neutron activation analysis (INAA and RNAA) were standardised and applied for the determination of the elements: Ca, Cs, I, K, Sr, Th and U in various kinds of biological samples. The results of the analysis of six Standard Reference Materials (NIST-USA) received from IAEA, namely, Bone Meal, Oyester Tissue, Muscle Powder, Total Diet I and II and Pine Needles are reported. The results obtained are in good agreement with the average values of those reported from six laboratories. The results of the analysis of skeletal muscle samples for the trace elements Cs and K, individual food components which form major essential components of Indian diet and a few cooked total diets are also reported for the above named seven elements. (author)

  1. Plutonium, americium, 90Sr and 137Cs in bones of red fox (Vulpes vulpes) from Eastern Poland

    International Nuclear Information System (INIS)

    Mietelski, J.W.; Tomankiewicz, E.; Gaca, P.; Blazej, S.; Kitowski, I.

    2008-01-01

    90 Sr, 238,239+240 Pu, 241 Am and 137 Cs activity concentrations are presented in the jaw bones of red fox (Vulpes vulpes) from eastern Poland. The short description of the applied radiochemical method is presented. Activity concentrations for 90 Sr ranged between 2.2±0.7 and 41.4±4.7 Bq/kg (aw = ash weight). Average results for plutonium and americium are on the level of 10 mBq/kg (aw). No clear relationship was observed among the radionuclide concentrations. The samples analyzed do not show elevated contamination levels when compared with results of bones of small animals (rodent or insectivorous mammals) determined previously, so no accumulation of bone seeking isotopes on higher step of food-chain is concluded. (author)

  2. Intake of 90Sr, 137Cs, 144Ce, 106Ru by fresh water organisms with food and water

    International Nuclear Information System (INIS)

    Marciulioniene, D.P.; Dusauskiene-Duz, R.F.; Polikarpov, G.G.

    1978-01-01

    Investigations of the water basins of various areas of Lithuania were carried out in 1973-1975. The investigations were performed to determine the role of food and water in accumulation of 90 Sr, 137 Cs, 144 Ce, 106 --Ru under experimental conditions by fresh water organisms (molluscs, larvae, insects, fishes) as well as 90 Sr in mollusc and fish organisms under natural conditions. It was found that the intake of the above radionuclides in fresh water organisms with radioactive food was less active and in smaller quantities than that with water. The accumulation levels of the radionuclides in fresh water organisms resulted from the radioactive food, depended on the physical and chemical state of the radionuclides and on the concentration of isotopic and nonisotopic carriers in water, food and in the very organism. Dependence of the accumulation coefficient (AC) of different radionuclides in fresh water organisms on the AC value in food as well as on the diet type was not determined

  3. Accumulation and transfer of 137Cs and 90Sr in the plants of the forest ecosystem near the Ignalina Nuclear Power Plant

    International Nuclear Information System (INIS)

    Lukšienė, B.; Marčiulionienė, D.; Gudelienė, I.; Schönhofer, F.

    2013-01-01

    The radioecological state of the forest ecosystem in the vicinity of the Ignalina Power Plant prior to decommissioning was analysed with specific emphasis on 137 Cs and 90 Sr activity concentrations in plant species growing in two reference sampling sites (Tilze and Grikiniskes). In the period of 1996–2008 the mean contamination of plants with 137 Cs was from 45 to 119 Bq/kg and with 90 Sr – from 3 to 42 Bq/kg. Measured 137 Cs TF values for soil-root transfer mainly ranged between 1.0–1.4, except for Calamagrostis arundinacea which had a TF value of 0.1. On average, the 137 Cs TF value from root to shoot was 1.7 fold higher than for soil to root transfer. 90 Sr TF values (soil-root) were in the range of 1.2–1.8 but for Calluna vulgaris it was 0.2. The mean root to shoot TF value for 90 Sr was 7.7 fold higher. These results indicate the higher 90 Sr bioavailability than that of 137 Cs in the forested area. The Grikiniskes reference site is located nearby the Ignalina NPP, specifically the heated water outlet channel, which results in altered microclimatic conditions. These specific microclimatic conditions result in relationships between 137 Cs TF (soil-root) values and pH, moisture and organic matter content in the soil at Grikiniskes which appear to be different to those at the Tilze reference sampling site. - Highlights: ► The state of the forest ecosystem prior to decommissioning of the NPP was analysed. ► Results indicate the higher 90 Sr bioavailability than that of 137 Cs. ► Contribution of 137 Cs of different origin in plants was calculated.

  4. {sup 137}Cs and {sup 90}Sr behaviour in contaminated soils of the Chernobyl area; Etude du comportement du {sup 137}Cs et du {sup 90}Sr dans les sols contamines de la region de Tchernobyl

    Energy Technology Data Exchange (ETDEWEB)

    Gri, N. [CEA/Fontenay-aux-Roses, Inst. de Protection et de Surete Nucleaire (IPSN), 92 (France)]|[Paris-11 Univ., 91 - Orsay (France)

    2000-07-01

    The improvement of the understanding of the mechanisms which generate radionuclides retention in soils are of main importance for radioactivity transport models, especially for long time assessments. In this context, the objectives of this thesis were to identify the mechanisms responsible for {sup 137}Cs and {sup 90}Sr behaviour in non cultivated soils and to quantify their influence. We studied radiocaesium and radiostrontium availability in different soils of the Chernobyl area (chernozem, sand, gley, peat), whose contamination took several physico-chemical forms (fuel particles, condensed forms, mixed deposits). The migration profiles obtained by gamma spectrometry and liquid scintillation show that the majority of the activity is contained in the ten first centimeters of soil, except for one site. The profiles are varied and don't allow to classify the radionuclides availability according to the pedology or to the contamination type. A selective extraction protocol applied on several soil layers has been adopted as an indirect approach. Although radionuclides availability is increasing with depth, the selective extraction protocol shows that a non negligible fraction of activity remain not mobile. {sup 137}Cs is associated to interstratified clay minerals in a non reversible way and {sup 90}Sr is strongly bound to fuel particles. The existence of these retention mechanisms calls into question the use of the K{sub d} distribution coefficient in transport models because they disabled reversibility and instantaneous desorption notions. (author)

  5. Determination of 90Sr, 137Cs and (239+240)Pu in waters with use of preliminary concentration

    International Nuclear Information System (INIS)

    Stepanov, V.M.; Kazachevskij, I.V.; Knatova, M.K.; Knyazev, B.B.; Lukashenko, S.N.; Solodukhin, V. P.; Khazhekber, S.; Gabdulin, R.M.

    2002-01-01

    A method for the simultaneous determination of artificial radionuclides ( 90 Sr, 137 Cs and (239+240) Pu) in water samples is described. The following preconcentration steps are used: co-precipitation of cesium on copper ferrocyanide; co-precipitation of plutonium on iron hydroxide; and precipitation of strontium in the carbonate form. The chemical yield is determined by using the tracers: 88 Y, 85 Sr, 134 Cs and 236 Pu or 242 Pu. The method was applied to the determination of artificial radionuclides in water sources at nuclear test sites - the former Semipalatinsk nuclear test site and the 'Azgir' and 'Lira' test sites. The volume of water samples was 0.5 - 30.0 l, and the mineralization ranged from 0.1g/l to 100 g/l. The determination limits were: < 1 mBq/l for cesium-137; 0.02 mBq/l for plutonium-(239+240); and 1.5 mBq/l for strontium-90. The chemical yield was 60 - 90%

  6. Uptake and Loss Kinetics of 57Co, 85Sr and 134Cs on Blood Cockle Anadara granosa

    International Nuclear Information System (INIS)

    Srisuksawad, K; Prasertchiewchan, N.; Tungkitjanukij, S.; Pakkong, P.

    2005-02-01

    Adult blood cockle (A. granosa) were exposed in the laboratory to 57 Co, 85 Sr, and 134 Cs in seawater at average +- s.e. stable activities of 0.725+-0.010 Bq/ml, 0.917+-0.066 Bq/ml and 1.37+-0.105 Bq/ml, respectively. The study aims to determine key contaminant bioaccumulation, retention and loss parameters for bio-indicator organisms used in assessment of the impact of the effluent discharge from nuclear and non-nuclear facilities on coastal area. Natural coastal water conditions in dry season with a salinity of 30 ppt, at 30οC and p H 8.1+-0.1 of the study area (Bang Pa Kong river basin) were simulated as far as practicable. 19 d uptake of radiotracers showed that blood cockle did not accumulate 134 Cs and 85 Sr but considerably accumulated 57 Co. Non-linear regression model fitting of a 1-compartment exponential uptake model derived overall weight concentration factors for the whole cockle at saturation of 687.6+-6.23 ml/g for 57 Co. 22 d loss experiment showed that 57 Co is tightly bounded in blood cockle and 63.2+-15.2% retained in the whole body. Loss of 57 Co displayed 2-compartment loss kinetic. The calculated half time for the short and long components of loss model was estimated 1.4 dand 41 d, respectively

  7. A comparison between predicted and observed levels of 137Cs and 90Sr in the Baltic Sea

    International Nuclear Information System (INIS)

    Nielsen, S.P.

    1997-01-01

    A model based on compartmental analysis has been developed to simulate the dispersion of radionuclides in the Baltic Sea. The model is intended for the prediction of annual average concentrations of radionuclides in the marine environment. The quality of the model predictions has been investigated by comparing predicted levels of 137 Cs and 90 Sr in water, top sediment and biota with observed levels covering the period 1960-1992. The sources of radioactivity into the Baltic region that have been considered are fallout from atmospheric nuclear weapons testing, fallout from the Chernobyl accident, liquid discharges to sea from the European reprocessing plants, and discharges from nuclear installations located in the Baltic Sea area. The predicted water concentrations are in good agreement with the observations for both radionuclides; the mean predictive accuracy of the model is close to unity. For the top sediment and biota concentrations the agreement is less favourable. The predicted water inventory data compare well with the observed data for the two radionuclides. The inventories of 137 Cs and 90 Sr in the Baltic Sea in 1994 have been estimated at 3200 TBq and 370 TBq, respectively. (author)

  8. Plutonium, {sup 137}Cs and {sup 90}Sr in selected invertebrates from some areas around Chernobyl nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Mietelski, Jerzy W., E-mail: jerzy.mietelski@ifj.edu.p [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Maksimova, Svetlana, E-mail: soilzool@biobel.bas-net.b [Institute of Zoology, National Academy of Sciences, Akademicheskaya 27, 220072 Minsk (Belarus); Szwalko, Przemyslaw [Institute of Systematics and Evolution of Animals, Polish Academy of Sciences, Slawkowska 17, 31-016 Krakow (Poland); Wnuk, Katarzyna [Holycross Cancer Center, Department on Nuclear Medicine, Artwinskiego 3, 25-734 Kielce (Poland); Zagrodzki, Pawel [Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Department of Food Chemistry and Nutrition, Medical College, Jagiellonian University, Medyczna 9, 30-688 Krakow (Poland); Blazej, Sylwia; Gaca, Pawel; Tomankiewicz, Ewa [The Henryk Niewodniczanski Institute of Nuclear Physics, Polish Academy of Sciences, Radzikowskiego 152, 31-342 Krakow (Poland); Orlov, Olexandr, E-mail: station@zt.ukrpack.ne [Poleskiy Branch of Ukrainian Scientific Research Institute of Forestry and Agro-Forest-Amelioration, Prospect Mira 38, Zhytomyr 10004 (Ukraine)

    2010-06-15

    Results are presented for {sup 137}Cs, {sup 90}Sr and plutonium activity concentrations in more than 20 samples of terrestrial invertebrates, including species of beetles, ants, spiders and millipedes, collected in the highly contaminated area of the Chernobyl exclusion zone. The majority of samples were collected in Belarus, with some also collected in the Ukraine. Three other samples were collected in an area of lower contamination. Results show that seven samples exceed an activity concentration of 100 kBq/kg (ash weight - a.w.) for {sup 137}Cs. The maximum activity concentration for this isotope was 1.52 +- 0.08 MBq/kg (a.w.) determined in ants (Formica cynerea). Seven results for {sup 90}Sr exceeded 100 kBq/kg (a.w.), mostly for millipedes. Relatively high plutonium activity concentrations were found in some ants and earth-boring dung beetles. Analyses of activity ratios showed differences in transfer of radionuclides between species. To reveal the correlation structure of the multivariate data set, the Partial Least-Squares method (PLS) was used. Results of the PLS model suggest that high radiocesium activity concentrations in animal bodies can be expected mainly for relatively small creatures living on the litter surface. In contrast, high strontium activity concentrations can be expected for creatures which conduct their lives within litter, having mixed trophic habits and a moderate lifespan. No clear conclusions could be made for plutonium.

  9. Early prediction of 90Sr and 137Cs content in edible parts of crops and selection of plants with high uptake ability

    International Nuclear Information System (INIS)

    Zhao Wenhu; Xu Shiming; Hou Lanxin; Shang Zhaorong

    1995-10-01

    The uptake characteristics to 90 Sr and 137 Cs of nine kinds of crops, including spring wheat, rice, soybean, vegetables etc., were studied from seedling to maturity. The change of 90 Sr content per unit of dry weight can be classified into two types--the 90 Sr content kept in the same level during the whole growing season and kept increasing with the growing period until it came to the maximum point at the time of maturity. 90 Sr and 137 Cs in the aerial part of plants were mainly distributed in leaves, but the amounts in seeds and fruits were less. The content of 90 Sr decreased but the content of 137 Cs increased from young to old leaves. So it could be concluded that early prediction of the radioactive content of edible parts according to the content of young leaves was possible. Selection of 169 species in 18 families of plants with high uptake ability of 90 Sr and 137 Cs, which grow in Qinshan region near a nuclear power plant and in Beijing region, is also reported. (8 refs., 6 figs., 16 tabs.)

  10. Quantifying sediment sources in a lowland agricultural catchment pond using {sup 137}Cs activities and radiogenic {sup 87}Sr/{sup 86}Sr ratios

    Energy Technology Data Exchange (ETDEWEB)

    Le Gall, Marion; Evrard, Olivier [Laboratoire des Sciences et de l' Environnement, UMR 8212 (CEA/CNRS/UVSQ), Université Paris-Saclay, Domaine du CNRS, Avenue de la Terrasse, 91198 Gif-sur-Yvette Cedex (France); Foucher, Anthony [E.A 6293, Laboratoire GéoHydrosystèmes Continentaux (GéHCO), Université F. Rabelais de Tours, Faculté des Sciences et Techniques, Parc de Grandmont, 37200 Tours (France); Laceby, J. Patrick [Laboratoire des Sciences et de l' Environnement, UMR 8212 (CEA/CNRS/UVSQ), Université Paris-Saclay, Domaine du CNRS, Avenue de la Terrasse, 91198 Gif-sur-Yvette Cedex (France); Salvador-Blanes, Sébastien [E.A 6293, Laboratoire GéoHydrosystèmes Continentaux (GéHCO), Université F. Rabelais de Tours, Faculté des Sciences et Techniques, Parc de Grandmont, 37200 Tours (France); Thil, François; Dapoigny, Arnaud; Lefèvre, Irène [Laboratoire des Sciences et de l' Environnement, UMR 8212 (CEA/CNRS/UVSQ), Université Paris-Saclay, Domaine du CNRS, Avenue de la Terrasse, 91198 Gif-sur-Yvette Cedex (France); Cerdan, Olivier [Département Risques et Prévention, Bureau de Recherches Géologiques et Minières, 3 avenue Claude Guillemin, 45060 Orléans (France); and others

    2016-10-01

    Soil erosion often supplies high sediment loads to rivers, degrading water quality and contributing to the siltation of reservoirs and lowland river channels. These impacts are exacerbated in agricultural catchments where modifications in land management and agricultural practices were shown to accelerate sediment supply. In this study, sediment sources were identified with a novel tracing approach combining cesium ({sup 137}Cs) and strontium isotopes ({sup 87}Sr/{sup 86}Sr) in the Louroux pond, at the outlet of a lowland cultivated catchment (24 km{sup 2}, Loire River basin, France) representative of drained agricultural areas of Northwestern Europe. Surface soil (n = 36) and subsurface channel bank (n = 17) samples were collected to characterize potential sources. Deposited sediment (n = 41) was sampled across the entire surface of the pond to examine spatial variation in sediment deposits. In addition, a 1.10 m sediment core was sampled in the middle of the pond to reconstruct source variations throughout time. {sup 137}Cs was used to discriminate between surface and subsurface sources, whereas {sup 87}Sr/{sup 86}Sr ratios discriminated between lithological sources. A distribution modeling approach quantified the relative contribution of these sources to the sampled sediment. Results indicate that surface sources contributed to the majority of pond (μ 82%, σ 1%) and core (μ 88%, σ 2%) sediment with elevated subsurface contributions modeled near specific sites close to the banks of the Louroux pond. Contributions of the lithological sources were well mixed in surface sediment across the pond (i.e., carbonate sediment contribution, μ 48%, σ 1% and non-carbonate sediment contribution, μ 52%, σ 3%) although there were significant variations of these source contributions modeled for the sediment core between 1955 and 2013. These fluctuations reflect both the progressive implementation of land consolidation schemes in the catchment and the eutrophication of

  11. Phytoremediation modelling - phytoextraction of 137Cs, 133Ba, and 90Sr from liquid media and artificially contaminated soil

    International Nuclear Information System (INIS)

    Smrcek, S.; Masnerova, G.

    2002-01-01

    The phytoremediation model based on experiments with plants cultivated in vitro in media supplemented with radionuclide salts was investigated. The plant species Brassica napus, Sinapis alba, Helianthus annuus, Zea mays and Pisum sativum were cultivated on the Murashige-Skoog basal salt mixture enriched with salts of 137 Cs, 133 Ba, and 90 Sr in aseptic conditions. The time-dependent radioactivity decrease in the medium was determined using LSC, and the phytoextraction curves were plotted. Radioactivity in the plant roots and shoots was measured and the efficiency of phytoextraction and the distribution between the roots and shoots as a measure of radionuclide transport in the plant tissues were calculated for each of the plants used. Cultivation experiments were also performed on artificially contaminated soil. Seeds of the plants were placed into contaminated soil and cultivated for 2 months in conditions similar to those of the in vitro experiments. The extracted radioactivity and distribution between roots and shoots were determined. The in vitro experiments simulated extraction of the radionuclide salt from solution analogously to real extraction from the soil solution, while the processes occurring in the rhizosphere were eliminated. The phytoextraction efficiency in terms of the percentage of the starting radioactivity ranged from 12 to 31 % for 90 Sr, 8 to 24% for 137 Cs, and 12 to 17 % for 133 Ba in a cultivation cycle. The root/shoot radioactivity ratios demonstrate that the plant species used may be suitable for real phytoremediation. The experiments in which the plants were cultivated from seeds in artificial contaminated substrate showed that the ability of roots to extract radionuclide salts from their environment remains unchanged. The relative efficiency values were lower than for the extraction from solutions (3 to 11.5 % for 90 Sr, 1.5 to 4 % for 137 Cs, and 1 to 6.2 %, for 133 Ba), but in this process, the equilibrium between the soil particles

  12. Sequential determination of natural ({sup 232}Th, {sup 238}U) and anthropogenic ({sup 137}Cs, {sup 90}Sr, {sup 241}Am, {sup 239+240}Pu) radionuclides in environmental matrix

    Energy Technology Data Exchange (ETDEWEB)

    Michel, H.; Levent, D.; Barci, V.; Barci-Funel, G.; Hurel, C. [Laboratoire de Radiochimie, Sciences Analytiques et Environnement (LRSAE), Universite de Nice Sophia-Antipolis 06108 Nice Cedex (France)

    2008-07-01

    A new sequential method for the determination of both natural (U, Th) and anthropogenic (Sr, Cs, Pu, Am) radionuclides has been developed for application to soil and sediment samples. The procedure was optimised using a reference sediment (IAEA-368) and reference soils (IAEA-375 and IAEA-326). Reference materials were first digested using acids (leaching), 'total' acids on hot plate, and acids in microwave in order to compare the different digestion technique. Then, the separation and purification were made by anion exchange resin and selective extraction chromatography: Transuranic (TRU) and Strontium (SR) resins. Natural and anthropogenic alpha radionuclides were separated by Uranium and Tetravalent Actinide (UTEVA) resin, considering different acid elution medium. Finally, alpha and gamma semiconductor spectrometer and liquid scintillation spectrometer were used to measure radionuclide activities. The results obtained for strontium-90, cesium-137, thorium-232, uranium- 238, plutonium-239+240 and americium-241 isotopes by the proposed method for the reference materials provided excellent agreement with the recommended values and good chemical recoveries. (authors)

  13. Soil-plant transfer of Cs-137 and Sr-90 in digestate amended agricultural soils- a lysimeter scale experiment

    Science.gov (United States)

    Mehmood, Khalid; Berns, Anne E.; Pütz, Thomas; Burauel, Peter; Vereecken, Harry; Zoriy, Myroslav; Flucht, Reinhold; Opitz, Thorsten; Hofmann, Diana

    2014-05-01

    Radiocesium and radiostrontium are among the most problematic soil contaminants following nuclear fallout due to their long half-lives and high fission yields. Their chemical resemblance to potassium, ammonium and calcium facilitates their plant uptake and thus enhances their chance to reach humans through the food-chain dramatically. The plant uptake of both radionuclides is affected by the type of soil, the amount of organic matter and the concentration of competitive ions. In the present lysimeter scale experiment, soil-plant transfer of Cs-137 and Sr-90 was investigated in an agricultural silty soil amended with digestate, a residue from a biogas plant. The liquid fraction of the digestate, liquor, was used to have higher nutrient competition. Digestate application was done in accordance with the field practice with an application rate of 34 Mg/ha and mixing it in top 5 cm soil, yielding a final concentration of 38 g digestate/Kg soil. The top 5 cm soil of the non-amended reference soil was also submitted to the same mixing procedure to account for the physical disturbance of the top soil layer. Six months after the amendment of the soil, the soil contamination was done with water-soluble chloride salts of both radionuclides, resulting in a contamination density of 66 MBq/m2 for Cs-137 and 18 MBq/m2 for Sr-90 in separate experiments. Our results show that digestate application led to a detectable difference in soil-plant transfer of the investigated radionuclides, effect was more pronounced for Cs-137. A clear difference was observed in plant uptake of different plants. Pest plants displayed higher uptake of both radionuclides compared to wheat. Furthermore, lower activity values were recorded in ears compared to stems for both radionuclides.

  14. Determination of environmental levels of 239240Pu, 241Am, 137Cs, and 90Sr in large volume sea water samples

    International Nuclear Information System (INIS)

    Sutton, D.C.; Calderon, G.; Rosa, W.

    1976-06-01

    A method is reported for the determination of environmental levels of 239 240 Pu and 241 Am in approximately 60-liter size samples of seawater. 137 Cs and 90 Sr were also separated and determined from the same samples. The samples were collected at the sea surface and at various depths in the oceans through the facilities of the Woods Hole Oceanographic Institution. Plutonium and americium were separated from the seawater by iron hydroxide scavenging then treated with a mixture of nitric, hydrochloric, and perchloric acids. A series of anion exchange separations were used to remove interferences and purify plutonium and americium; then each was electroplated on platinum disks and measured by solid state alpha particle spectrometry. The overall chemical yields averaged 62 +- 9 and 69 +- 14 percent for 236 Pu, and 243 Am tracers, respectively. Following the iron hydroxide scavenge of the transuranics, cesium was removed from the acidified seawater matrix by adsorption onto ammonium phosphomolybdate. Cesium carrier and 137 Cs isolation was effected by ion exchange and precipitations were made using chloroplatinic acid. The samples were weighed to determine overall chemical yield then beta counted. Cesium recoveries averaged 75 +- 5 percent. After cesium was removed from the seawater matrix, the samples were neutralized with sodium hydroxide and ammonium carbonate was added to precipitate 85 Sr tracer and the mixed alkaline earth carbonates. Strontium was separated as the nitrate and scavenged by chromate and hydroxide precipitations. Yttrium-90 was allowed to build up for two weeks, then milked and precipitated as the oxalate, weighed, and beta counted. The overall chemical yields of 85 Sr tracer averaged 84 +- 16 percent. The recovery of the yttrium oxalate precipitates averaged 96 +- 3 percent

  15. Studies of radioactivity of vegetables: determination of transfer factors 85Sr and 134Cs in some vegetables

    International Nuclear Information System (INIS)

    Oncsik, M.B.

    1999-01-01

    The radioisotope uptake of potato and culinary dry bean was studied in field experiments on meadow soil enriched with vermiculite and humanite by artificial soil contamination. The isotope uptake from the soil was characterized by a transfer factor (TF). Based on the results of the potato experiment it was found that the TF value characterizing the 134 Cs contamination of the crop, changed between 1.31 - 0.77*10 -4 m 2 (kg dry matter) -1 on high humus content soil (treated with humanite) and on soil treated with vermiculite, while it was 22-45 % higher in plants grown on the radioactive control plots. lt was 1.69*10 -4 m 2 (kg dry matter)2 -1 in average. The TF values of 85 Sr uptake of potato are several times higher than those of experiments treated by isotope 134 Cs. The TF values fluctuated between 5.30-7.33*10 -4 m 2 (kg dry matter) -1 in soils treated with the additives, while on the plots with radioactive contamination it was 8.42*10 -4 m 2 (kg dry matter) -1 . Based on the results of 134 Cs studies of edible part of dry bean, it could be stated that after the soil contamination the TF value was 0.99*10 -4 m 2 (kg dry matter) -1 in average. According to the activity results of the experiments there was significant difference between the contamination of the plant parts. Refs. 6 (author)

  16. Long-term post-Chernobyl 90Sr and 137Cs profiles as the indicators of the large scale vertical water mixing in the Black Sea

    International Nuclear Information System (INIS)

    Egorov, V.N.; Stokozov, N.A.; Mirzoyeva, N.Y.

    2002-01-01

    The radioactive and chemical pollutions, eutrophic elements come to the surface water layer of the Black Sea from the territory of 22 countries. The self-purification of the surface water layer essentially depends from the vertical water mixing. The atmospheric fallout in the May 1986 after Chernobyl NPP accident were main source of the 137 Cs input in the Black Sea. The 90 Sr input to the Black Sea was caused by atmospheric fallout as well as the Dnieper River and Danube River runoff during of consequent years. 90 Sr and 137 Cs are conservative elements in a marine environment and could be used as tracers of the hydrological processes, including vertical water mixing. The aim of our investigations was an assessment of the large-scale vertical water exchange in the Black Sea on base of analysis time-series 90 Sr and 137 Cs vertical profiles

  17. Stocks of 90Sr and 137Cs in biomass of birds in the territory of Chernobyl zone and size of radionuclide export with birds outside

    International Nuclear Information System (INIS)

    Gashchak, S.P.; Bondar'kov, M.D.; Maklyuk, Yu.A.; Maksimenko, A.M.; Martynenko, V.I.; Chizhevskij, I.V.

    2009-01-01

    The contamination of birds varies in wide range, with an activity concentration of 90 Sr and 137 Cs differed by 2-4 orders, and on the whole the Chernobyl zone - to 5 orders of magnitude. The maximum values contamination of birds amounted to hundreds of Bq/g in the central plots of the zone. It is noted that by reducing the biological availability of radionuclides from soil transfer factor 90 Sr decreased 4,05 times, and 137 Cs - in 11,0 times compared with the results of evaluations of the first years. The activity concentration of 90 Sr and 137 Cs in the body of birds decreased in 1,6 - 7,0 and 7,9 - 29,2 times respectively.

  18. The transfer of 137Cs and 90Sr to dairy cattle fed fresh herbage collected 3.5 km from the Chernobyl nuclear power plant

    International Nuclear Information System (INIS)

    Beresford, N.A.; Gashchak, S.; Lasarev, N; Arkhipov, A.; Chyorny, Y.; Astasheva, N.; Arkhipov, N.; Mayes, R.W.; Howard, B.J.; Baglay, G.; Loginova, L.; Burov, N.

    2000-01-01

    A study conducted during summer 1993 to determine the bioavailability and transfer of 137 Cs and 90 Sr to dairy cattle from herbage collected from a pasture contaminated by particulate fallout is described. The study pasture was located 3.5 km from the Chernobyl nuclear power plant. The true absorption coefficient (A t ) determined for 137 Cs (0.23) was considerably lower than previous estimates for radiocaesium incorporated into vegetation by root uptake. It is likely that the low dry matter digestibility of the diet and the potential presence of 137 Cs associated with adherent soil-associated fuel particles contributed to this low bioavailability. The A t value determined for 90 Sr (0.27) did not indicate a reduced bioavailability. It is suggested that the current and previous calcium status of the animals was the controlling influence on the transfer of 90 Sr from the diet to milk

  19. Recent advances in the development of a cobalt dicarbollide based solvent extraction process for the separation of Cs and Sr from spent fuel

    International Nuclear Information System (INIS)

    Law, Jack D.; Todd, Terry A.; Peterman, D.R.; Herbst, R.S.; Tillotson, R.D.

    2004-01-01

    As part of the Advanced Fuel Cycle Initiative (AFCI), a chlorinated cobalt dicarbollide (CCD)/polyethylene glycol (PEG) based solvent extraction process is being developed for the separation of Cs and Sr from leached spent light water reactor (LWR) fuel. The separation of Cs and Sr would significantly reduce the short-term heat generation of spent nuclear fuel requiring geological disposal. Recent advances in the development of a CCD/PEG process will be presented. The data presented will include acid dependency data, results of batch contact testing using simulant feeds traced with 137 Cs, 90 Sr and 241 Am as well as results of testing to evaluate extractant composition. The impacts of other separation process in an advanced aqueous separation flow sheet on the effectiveness of the CCD/PEG process will be detailed. (authors)

  20. Studies on the transfer of Cs, Sr, Co, Mn and Zn from soil to plants and from medium to mushrooms by using radiotracer

    International Nuclear Information System (INIS)

    Ban-nai, Tadaaki; Muramatsu, Yasuyuki; Yoshida, Satoshi; Yanagisawa, Kei

    1996-01-01

    Radiotracer experiments were carried out to study radionuclide uptake by plants and mushrooms. Transfer factors of radionuclides from soil to leaf vegetables (cabbage, Chinese cabbage, komatsuna, spinach and lettuce) have been determined by radiotracers. The transfer factors of radioactive Cs, Sr, Mn, Co and Zn for edible parts of vegetables were 0.11, 0.24, 0.61, 0.05 and 0.52, respectively. The transfer factors of Mn, Co and Zn for spinach were higher than those for the other vegetables. The transfer factors of Cs for different organs of the leaf vegetables were rather homogeneous. The transfer factors of Sr and Mn were higher for older (outer) leaves than younger (inner) ones. In contrast to Sr and Mn, transfer factors of Zn for younger leaves were higher than those for older ones. In order to study radionuclide uptake by mushrooms, cultivation experiments in flasks were carried out using radiotracers, 137 Cs, 85 Sr, 60 Co, 54 Mn and 65 Zn. Four mushroom species Hebeloma vinosophyllum, Flammulina velutipes, Agrocybe cylindracea and Coprinus phlyctidosporus were used. In addition, Medicago sativa was also tested. Mushrooms tended to accumulate Cs, although there was a large difference between mushroom species. The concentration ratio had the highest value of 21 for Cs in vinosophyllum. The value was much higher than that in the plant sample. The present findings agreed with our previous observations in which Hebeloma species collected in forests contained large amount of 137 Cs. The effects of stable elements in the medium on the accumulations were investigated. The concentration ratios of Cs, Sr and Co were not influenced highly by coexisting stable elements in the medium. However, the ratio of Mn decreased as the amount of coexisting stable elements in the medium was increased. (J.P.N.)

  1. Effects of 137Cs and 90Sr on structure and functional aspects of the microflora in agricultural used soils

    International Nuclear Information System (INIS)

    Niedree, Bastian

    2013-01-01

    At long sight 137 Cs and 90 Sr are the main radionuclides responsible for the contamination of agricultural soils due to core melts in nuclear power plants such as Chernobyl or Fukushima. Once deposited on the soil surface, the two radionuclides remain in the upper soil layer for several decades. In the upper soil layer the highest microbial activity can be found, due to high organic matter contents, warm temperatures and gas exchange with the atmosphere. Hence, in contaminated soils microorganisms in upper soil layers (e.g. the plow layer on agricultural fields) are exceedingly exposed to radioactivity. However, no data are available how radioactive contaminations with 137 Cs or 90 Sr in a realistic order of magnitude affect the microbial community and its functions in soils. This dissertation discusses the effects of radioactive contaminations on the microbial community structure and some of its functions in soils. Therefore, typical agricultural soils, an Orthic Luvisol from field site Merzenhausen and a Gleyic Cambisol from field site Kaldenkirchen-Huelst were artificially contaminated with various concentrations of 137 Cs and 90 Sr and partly applied with radiolabeled substrates and incubated in soil microcosms under controlled laboratory conditions. The lower radionuclide concentrations corresponded to the contaminations in the Chernobyl exclusion zone, the higher concentrations were up to 50-fold that of the maximum occurring hotspots ( 137 Cs) in this zone. In three experiments the effects of the ionizing radiation on the bacterial and the fungal community structure (16S and 18S rDNA DGGE), the degradation of 14 C-labeled wheat straw or uniformly ring-labeled 2,4-dichlorophenoxyacetic acid, the development of the fungal biomass (ergosterol quantification) and the chemical composition of the soil organic matter ( 13 C CP/MAS NMR) were investigated. In half of the microcosms the soils were autoclaved and reinoculated with native soil, with intention to

  2. The radiological exposure of man from ingestion of Cs-137 and Sr-90 in seafood from the Baltic Sea. Pilot project: Marina-Balt

    Energy Technology Data Exchange (ETDEWEB)

    Nielsen, S.P. [Risoe National Lab., Roskilde (Denmark); Oehlenschlaeger, M. [National Institute of Radiation Hygiene, Broenshoej (Denmark); Karlberg, O. [Swedish Radiation Protection Institute, Stockholm (Sweden)

    1995-04-01

    This report describes a limited radiological assessment of the collective doses to man from the intake of seafood from the Baltic Sea contaminated with the radionuclides Cs-137 and Sr-90. Information on fisheries statistics is presented. The most important source terms to radioactive contamination of Cs-137 and Sr-90 in the Baltic Sea are identified and quantified. A compartment model for the dispersion of radionuclides in European coastal waters including the Baltic Sea is described and tested by comparing model predictions with observations. Collective doses are calculated with the model for each of the source-term categories. (au) (11 tabs., 28 ills., 17 refs.).

  3. The radiological exposure of man from ingestion of Cs-137 and Sr-90 in seafood from the Baltic Sea. Pilot project: Marina-Balt

    International Nuclear Information System (INIS)

    Nielsen, S.P.; Oehlenschlaeger, M.; Karlberg, O.

    1995-04-01

    This report describes a limited radiological assessment of the collective doses to man from the intake of seafood from the Baltic Sea contaminated with the radionuclides Cs-137 and Sr-90. Information on fisheries statistics is presented. The most important source terms to radioactive contamination of Cs-137 and Sr-90 in the Baltic Sea are identified and quantified. A compartment model for the dispersion of radionuclides in European coastal waters including the Baltic Sea is described and tested by comparing model predictions with observations. Collective doses are calculated with the model for each of the source-term categories. (au) (11 tabs., 28 ills., 17 refs.)

  4. The fate of long - lived radionuclides 137Cs and 90Sr in the Black Sea after Chernobyl NPP accident: results of twenty - year observations

    International Nuclear Information System (INIS)

    Stokozov, N. A.; Egorov, V. N.; Polikarpov, G. G.; Mirzoeva, N. Y.; Gulin, S. B.

    2006-01-01

    The presentation summarizes studies of 1 37Cs and 9 0Sr pollution of the Black Sea Basin carried out by Institute of Biology of the Southern Seas during 1986-2005 following the Chernobyl NPP accident. Its goal was to assess inflows of 1 37Cs and 9 0Sr from the Dnieper and the Danube Rivers, outflow through the Bosphorus Strait, inventories in bottom sediments and temporary evolution of 1 37Cs and 9 0Sr inventories in the Black Sea water column. Besides, the temporary evolution of 1 37Cs and 9 0Sr profiles in the Black Sea deep-water basin was used to estimations of a large-scale vertical water mixing. It has been estimated that the atmospheric fall outs during the first days of May 1986 have deposited 1.7-2.4 PBq of 1 37Cs on the Black Sea surface (nearly 2% of total 1 37Cs release in the environment). Therefore, 1 37Cs inventory in the 0-50 m layer have increased by a factor of 6-10 and the total 1 37Cs inventory in the whole basin have increased at least by a factor of 2 in comparison with the pre-Chernobyl value - 1.4+/-0.3 PBq. 1 37Cs input from the Danube and the Dnieper Rivers was insignificant in comparison with short-term atmospheric fall outs. The results of observations and mathematical modelling are testified that in the surface layers 0-50 and 0-200 m of the Black Sea deep-water basin in 1986-2000 an exponential decreases of the 1 37Cs inventories with an effective half-lifes of 5-6 years and 9-13 years, respectively, have been observed. The process of vertical water mixing has been observed mainly in the 0-200 m layer. The contribution of Chernobyl-origin 9 0Sr from atmospheric fallout was estimated around in 0.1-0.3 PBq. Pre-accident 9 0Sr level nearly 20 Bq m - 3 was reached by 1988. At the same time, an active input of 9 0Sr from the Dnieper and Danube Rivers has been observed. The total amount of 9 0Sr delivered by the two rivers into the Black Sea was estimated to be nearly 0.1 PBq in the 1986-1995. Under conditions of insignificant river input

  5. Coefficients of leaf-fruit translocation for 60Co, 90Sr and 137Cs in bean plant (Phaseolus vulgaris)

    International Nuclear Information System (INIS)

    Macacini, Jose Flavio

    2000-01-01

    Due to the increasing use of nuclear fission for the generation of electrical energy, the safety aspects of power plants must be minutely appraised. In case of an accident, with liberation of radioactive material into the atmosphere, knowledge about the behavior of plant species when in contact with radionuclides is indispensable. An important route through which agricultural products are contaminated by radionuclides is leaf-fruit translocation. This phenomenon can be evaluated by simulating a fallout contamination in a controlled atmosphere using as a tracer man-made radionuclides. In order to quantity the leaf-fruit translocation coefficients for 60 Co, 90 Sr and 137 Cs in the common bean (Phaseolus vulgaris), variety black diamond, an experiment was carried out in a greenhouse with completely randomized blocks design with six treatments and four blocks. A mixture of these three radionuclides was prepared and used to determine their translocation coefficients. The bean plants were contaminated inside a device especially designed to avoid environmental contamination. In each treatment four vases were sprinkled and one was used to estimate the initial activity of the other three vases. High-resolution gamma-ray spectrometry was used for 60 Co and 137 Cs activity determinations and chemical separation followed by beta counting of 90 Y was used for 90 Sr determinations. The number of treatments was reduced from six to four sprayings corresponding to 30, 45, 60 and 75 days after planting. This reduction was due to the attack of common and gold mosaic viroses. Symptoms were observed on the diseased bean plants 50 days after planting. It was possible, however, to verify a functional dependence between instant of tracer application and the level of physiological development of the bean plant. It was verified that the temporal relationship values for leaf-fruit translocation were similar for 60 Co and 137 Cs. For the 90 Sr, the translocation was below 2,5 mBq kg -1 /Bq

  6. sup(239/240)Pu, 137Cs, 90Sr, and 40K in different types of honey

    International Nuclear Information System (INIS)

    Bunzl, K.; Kracke, W.

    1981-01-01

    Information on the concentration of radionuclides in honey is of interest because this foodstuff consumed worldwide could be a source of radionuclides to man. Besides that, honey is used as a bioindicator for several radionuclides because the bees forage for nectar, pollen or honeydew over a large area of landscape. In this connection, it is of special interest to know when, and, if so, to what extent the concentrations of radionuclides in the honey depend on the type of honey sampled by the bees. For this reason, we determined sup(239/240)Pu, 137 Cs, 90 Sr and 40 K in three important types of honey produced in the F.R.G., namely in honey from flowers, from honeydew and from heather. The data obtained in this way was used also to investigate whether significant correlations exist between these radionuclides in the various honey samples. (author)

  7. Influence of soil fungi (basidiomycetes) on the migration of Cs 134 + 137 and Sr 90 in coniferous forest soils

    International Nuclear Information System (INIS)

    Roemmelt, R.; Hiersche, L.; Schaller, G.; Wirth, E.

    1990-01-01

    During the first three years after the Chernobyl event high Cs 134 + 137 activities in fruitbodies of basidiomycetes have been measured. A decline of activities with time has not yet been observed. The activities are considerably higher compared to agricultural products from the same area. In order to study the movement of radiocesium in coniferous forest sites, the activities in soil, fungi, and plants have been measured. Based on these results a model to describe the cesium cycling in coniferous forest ecosystems is proposed with special emphasis on the influence of soil fungi and plants on the migration of cesium. As measurements of Sr 90 in forest ecosystems are rare this nuclide has been included in the investigations. (author)

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

    International Nuclear Information System (INIS)

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

    1995-01-01

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

  9. To the predicted calculations of Cs-137 and Sr-90 migration in soil in the frame of the compartment model

    International Nuclear Information System (INIS)

    Knat'ko, B.A.; Skomorokhov, A.G.

    1994-01-01

    The method of calculation of migration of radionuclides in soil according to compartment model and based on analitical solution of the system of differential equations of the model is proposed. Calculations of the content of radionuclides in the soil layer for Cs-137 and Sr-90 for four types of soil for the periods of 0, 21, 34,46 and 73 months are carried out. Calculations were done for three upper soil layers 0-2.5, 2.5-5, 5.0-15.0 cm, which give the main contribution into transport of radionuclides into plants on meadows and pastures. Such method increases precision of calculations of cesium-137 and strontium-90 migration in comparison with the prosedure, which uses the system of finite difference equations. 6 refs., 1 fig

  10. Uncertainty analysis of 137Cs and 90Sr activity in borehole water from a waste disposal site

    International Nuclear Information System (INIS)

    Dafauti, Sunita; Pulhani, Vandana; Datta, D.; Hegde, A.G.

    2005-01-01

    Uncertainty quantification (UQ) is the quantitative characterization and use of uncertainty in experimental applications. There are two distinct types of uncertainty variability which can be quantified in principle using classical probability theory and lack of knowledge which requires more than classical probability theory for its quantification. Fuzzy set theory was applied to quantify the second type of uncertainty associated with the measurement of activity due to 137 Cs and 90 Sr present in bore-well water samples from a waste disposal site. The upper and lower limits of concentration were computed and it may be concluded from the analysis that the alpha cut technique of fuzzy set theory is a good nonprecise estimator of these types of bounds. (author)

  11. Accumulation and transfer of 137Cs and 90Sr in the plants of the forest ecosystem near the Ignalina Nuclear Power Plant.

    Science.gov (United States)

    Lukšienė, B; Marčiulionienė, D; Gudelienė, I; Schönhofer, F

    2013-02-01

    The radioecological state of the forest ecosystem in the vicinity of the Ignalina Power Plant prior to decommissioning was analysed with specific emphasis on (137)Cs and (90)Sr activity concentrations in plant species growing in two reference sampling sites (Tilze and Grikiniskes). In the period of 1996-2008 the mean contamination of plants with (137)Cs was from 45 to 119 Bq/kg and with (90)Sr - from 3 to 42 Bq/kg. Measured (137)Cs TF values for soil-root transfer mainly ranged between 1.0-1.4, except for Calamagrostis arundinacea which had a TF value of 0.1. On average, the (137)Cs TF value from root to shoot was 1.7 fold higher than for soil to root transfer. (90)Sr TF values (soil-root) were in the range of 1.2-1.8 but for Calluna vulgaris it was 0.2. The mean root to shoot TF value for (90)Sr was 7.7 fold higher. These results indicate the higher (90)Sr bioavailability than that of (137)Cs in the forested area. The Grikiniskes reference site is located nearby the Ignalina NPP, specifically the heated water outlet channel, which results in altered microclimatic conditions. These specific microclimatic conditions result in relationships between (137)Cs TF (soil-root) values and pH, moisture and organic matter content in the soil at Grikiniskes which appear to be different to those at the Tilze reference sampling site. Copyright © 2012 Elsevier Ltd. All rights reserved.

  12. 90Sr and 137Cs in the Black Sea after the Chernobyl NPP accident: inventories, balance and tracer applications

    International Nuclear Information System (INIS)

    Egorov, V.N.; Povinec, P.P.; Polikarpov, G.G.; Stokozov, N.A.; Gulin, S.B.; Kulebakina, L.G.; Osvath, I.

    1999-01-01

    The paper summarizes studies of the distributions of 90 Sr and 137 Cs in the water and sediments of the Black Sea carried out during a 10-year period following the 1986 accident at the Chernobyl Nuclear Power Plant. Its goal is to assess the temporal evolution of radionuclide inventories and balances and to evaluate the mixing of water masses and the sedimentation processes using man-made radionuclides as tracers. Using mathematical models and field data, mixing time-scales of 5, 16 and 24 years have been estimated, respectively, for the water layers of depths 0-50, 0-100 and 0-200 m. For the Central Basin the ventilation time of the lower pycnocline is estimated at 15-25 years. 137 Cs has been used to date shelf and deep-basin sediments, providing the history of chemical and radioactive pollution and of eutrophication during the past 50 years. (Copyright (c) 1999 Elsevier Science B.V., Amsterdam. All rights reserved.)

  13. Actinides and fission products partitioning from high level liquid waste

    International Nuclear Information System (INIS)

    Yamaura, Mitiko

    1999-01-01

    The presence of small amount of mixed actinides and long-lived heat generators fission products as 137 Cs and 90 Sr are the major problems for safety handling and disposal of high level nuclear wastes. In this work, actinides and fission products partitioning process, as an alternative process for waste treatment is proposed. First of all, ammonium phosphotungstate (PWA), a selective inorganic exchanger for cesium separation was chosen and a new procedure for synthesizing PWA into the organic resin was developed. An strong anionic resin loaded with tungstate or phosphotungstate anion enables the precipitation of PWA directly in the resinous structure by adding the ammonium nitrate in acid medium (R-PWA). Parameters as W/P ratio, pH, reactants, temperature and aging were studied. The R-PWA obtained by using phosphotungstate solution prepared with W/P=9.6, 9 hours digestion time at 94-106 deg C and 4 to 5 months aging time showed the best capacity for cesium retention. On the other hand, Sr separation was performed by technique of extraction chromatography, using DH18C6 impregnated on XAD7 resin as stationary phase. Sr is selectively extracted from acid solution and >99% was recovered from loaded column using distilled water as eluent. Concerning to actinides separations, two extraction chromatographic columns were used. In the first one, TBP(XAD7) column, U and Pu were extracted and its separations were carried-out using HNO 3 and hydroxylamine nitrate + HNO 3 as eluent. In the second one, CMP0-TBP(XAD7) column, the actinides were retained on the column and the separations were done by using (NH 4 ) 2 C 2 O 4 , DTPA, HNO 3 and HCl as eluent. The behavior of some fission products were also verified in both columns. Based on the obtained data, actinides and fission products Cs and Sr partitioning process, using TBP(XAD7) and CMP0-TBP(XAD7) columns for actinides separation, R-PWA column for cesium retention and DH18C6(XAD7) column for Sr isolation was performed

  14. Evaluation of improved techniques for the removal of 90Sr and 137Cs from process wastewater and groundwater: Chabazite zeolite baseline study

    International Nuclear Information System (INIS)

    Bostick, D.T.; Arnold, W.D. Jr.; Taylor, P.A.; McTaggart, D.R.; Burgess, M.W.; Guo, B.

    1995-04-01

    Standard waste treatment procedures for the removal of 90 Sr and 137 Cs from contaminated groundwater and process wastewaters generate large volumes of secondary contaminated wastes. Several new sorbent materials, ion exchangers, and other processes hold the promise of treating large volumes of contaminated water while minimizing the generation of secondary low-level radioactive wastes. As part of the Efficient Separations/Processes-Integrated Program (ESPIP), these new treatment techniques will be compared with standard processes to define their effectiveness for the removal of radioactive strontium (Sr) and cesium (Cs), as well as to gauge the quantity of secondary radioactive waste generated by the new processes. This report summarizes the efforts made to design standardized testing procedures to evaluate the sorption characteristics of a baseline wastewater treatment technique. Definition of the experimental procedures, as well as a summary of the benchmark sorption technique, will provide the framework with which to compare newly evolving treatment technologies. Accomplishments include selecting the feed strewn to the Process Waste Treatment Plant (PWTP) at Oak Ridge National Laboratory as representative of the prototypical contaminated wastewater of many DOE sites. Samples from the PWTP feed stream were collected and analyzed for metals, anions, total Sr and Cs, radioactive Sr and Cs, alkalinity, pH, and density. The cumulative sample data were used to formulate a simulant that will be used as a standard waste surrogate for comparative testing of selected treatment methods

  15. Lysimeter experiments on root uptake of Co-60, Sr-90 and Cs-137 from soil into vine and apple trees and on the transfer into grapes and apples

    International Nuclear Information System (INIS)

    Steffens, W.; Foerstel, H.; Mittelstaedt, W.

    1993-01-01

    In lysimeters filled with two different soil types (Parabraunerde and Podzol) the transfer of 60 Co, 90 Sr and 137 Cs from soil into vine and apple trees was investigated over a time period of 5 years (1988-1992). The soil was contaminated in 1978, so that at the beginning of the experiment the radionuclides were already aged. Due to the low availability for root uptake, the transfer of 60 Co and 137 Cs into vine and apple trees was very low. 90 Sr was fairly available for root uptake which caused a considerable uptake and translocation into vegetative plant parts. The physiological behaviour of the radionuclides investigated determined generally a low transfer into must and apples. This was confirmed by the transfer factors variing between 0.001 and 0.029 for 60 Co, 0.01 and 0.036 for 90 Sr and 0.001 and 0.109 for 137 Cs, respectively. The corresponding values in apples were in the same order of magnitude. The influence of the soil type is shown by the higher incorporation of 60 Co, 90 Sr and 137 Cs into the single plant organs and by the higher transfer factors in must and apples grown on the podzolic soil. (orig.) [de

  16. Evaluation of small scale laboratory and pot experiments to determine realistic transfer factors for the radionuclides Sr-90, Cs-137, Co-60 and Mn-54

    International Nuclear Information System (INIS)

    Steffens, W.; Fuhr, F.; Mittelstaedt, W.

    1980-01-01

    Lysimeter experiments were undertaken in a controlled experimental field to study the root uptake of Sr-90, Cs-137, Co-60 and Mn-54 under outdoor conditions. Parallel experiments were set up using the Kick - Brauckman experimental pots under greenhouse and the Neubauer cups under growth chamber conditions. The results obtained from the three types of experiments are compared. (H.K.)

  17. The behaviour peculiarities 137Cs and 90Sr in the same reservoir ecosystem components of the far zone influence of the Chernobyl APS accident

    International Nuclear Information System (INIS)

    Khvaley, O.D.

    2000-01-01

    The distribution of the 137 Cs and 90 Sr between the main components of the lentical type water ecosystem in the far zone influence of the Chernobyl NPP was investigated. The water, water suspensions, bottom sediments and aquatic vegetation were investigated in 1990-1997. The date on the change of the radioactivity situation for this time were obtained. (authors)

  18. Detection of low activities 90Sr and 137Cs in surface, subsoil and sewage waters

    International Nuclear Information System (INIS)

    Babenko, V.; Isaev, A.; Kazymyrova, G.; Rudyk, O.; Khristenko, U.

    2004-01-01

    In this article the methodic of detection of volumetric activity of radionuclide 90 Sr in surface, subsoil and sewage waters on the basis of measurement of counting samples using beta-spectrometers SEB-01, produced by RPE 'Atom Komplex Prylad' (RPE 'AKP') and mathematical proceeding of spectra by software packages AKWin. At that, the time of receiving of result shortens, comparing to method of radiochemistry, from 14 days to 3 days. Activity measurement range of beta-spectrometers SEB-01 is 0.1-10 4 Bq/l, that by corresponding radionuclides concentration, allows providing control of water objects according to national norms of Ukraine (2 Bq/l). (authors)

  19. Areal distribution of 60Co, 137Cs, and 90Sr in streambed gravels of White Oak Creek Watershed, Oak Ridge, Tennessee

    International Nuclear Information System (INIS)

    Cerling, T.E.; Spalding, B.P.

    1981-01-01

    The concentrations of 90 Sr, 60 Co, and 137 Cs in streambed gravels from contaminated drainages in White Oak Creek Watershed were determined. Methods to determine the relative contributions of various sources to the total discharge from the watershed were developed. Principal sources of 90 Sr were: ORNL plant effluents (50%), leaching from solid waste disposal area (SWDA) 4 (30%), and leaching from SWDA 5 (10%). Minor sources included SWDA 3, the Molten Salt Reactor Facility, and intermediate-level liquid waste pit 1 with each representing 4% or less of the total basin discharge. The cooling water effluent from the High-Flux Isotope Reactor was the dominant source of 60 Co contamination in the watershed. ORNL plant effluents accounted for almost all the 137 Cs discharge from White Oak Creek basin. Downstream radionuclide concentrations were constant until significant dilution by other tributaries occurred. Any future activities giving rise to additional contamination can now be identified. Distribution coefficients between streambed gravels and streamwater for 85 Sr, 60 Co, and 137 Cs were 50, 560, and 8460 ml/g, respectively. An abridged radiochemical fractionation developed for 90 Sr was found to be as accurate and precise for these samples as the standard 90 Sr method above levels of 2 dpm/g

  20. Modeling of 137Cs and 90Sr behavior in the soil-plant system within the territory adjacent to 'Experimental field' technical site in the Semipalatinsk test site

    International Nuclear Information System (INIS)

    Spiridonov, S.I.; Gontarenko, I.A.; Mukusheva, M.K.

    2005-01-01

    Modelling of 137 Cs and 90 Sr behavior in the soil-plant system is presented. Models have been parameterized for the area adjacent to the 'Experimental Field' Technical Site of the Semipalatinsk Test Site. The models describe the main processes responsible for changes of 137 Cs and 90 Sr content in the soil solution and, thereby, dynamics of radionuclides intake by vegetation. Results are presented from perspective and retrospective calculations, that reflect the dynamics of 137 and 90 Sr distribution by species in soil after nuclear explosions. The importance of factors governing radionuclide accumulation in plants within Semipalatinsk test site area is assessed. The analysis of sensitivity of model output variable to change in its parameters has revealed that the key soil properties significantly influence the results of prediction of radionuclide content in plants. (author)

  1. Application of boat method in emissive flame photometry for determination of Li, Rb, Cs, Na, K, Ca, Sr, Ba

    International Nuclear Information System (INIS)

    Orlov, N.A.; Pobedonostsev, V.A.; Savel'ev, Yu.A.

    1976-01-01

    Study of the flame temperature and dependence of adsorbance on the C/O ratio over the boat for the carbide forming elements and the effect of material, thickness, and the height of the boat on the vaporization of alkaline and alkaline earth metals is described. For a boat (70x8, and 0.3 mm thickness), made from Cu, brass, and Ni, the fall in temperature over the boat was 70, 130, 250, and 340 0 , respectively, for air-C 2 H 2 and 50, 100, 210, and 280 0 for N 2 O-C 2 H 2 flame. Introduction of the boat increases the C/O ratio in the analytical zone of the flame, probably caused by a creation of a shaded space, immediately above the boat. Smaller amounts of atmospheric O enter into the space, when compared with the flame in the absence of the boat. The increase in the C/O ratio decreases the absorbance, which in turn, is caused by the fall in temperature and formation of carbides. Time lag between heating of the boat and the initiation of vaporization of the sample and the duration of evaporation impulse were measured. Solutions of CsCl, containing 1 μg Cs/ml were used at 852.1 nm. The boats, previously treated with 0.1% polystyrene in C 6 H 6 , to give a hydrophobic surface and an uniform salt layer distribution, containing the sample were dried under an ir lamp and introduced into the flame. The dependence of Cs emission on the thickness of the different materials (Ni, Cu, Ta) and heights of boats in the air-C 2 H 2 flame is illustrated. The duration of the emission impulse decreases linearly with the decrease of thickness of the boat for all materials tested. Limits of detection of Na, K, Li, Rb, Cs, Ca, Sr, and Ba were determined by using the equilibrium and the boat methods, the latter being some 1-2 orders lower than the former

  2. Oskarshamn site investigation. Batch experiments of I, Cs, Sr, Ni, Eu, U and Np sorption onto soil from the Laxemar area

    Energy Technology Data Exchange (ETDEWEB)

    Holgersson, Stellan (Dept. of Chemical and Biochemical Engineering, Nuclear Chemistry, Chalmers Univ. of Technology, Goeteborg (Sweden))

    2009-04-15

    Soil and groundwater samples from the Laxemar area have been collected and characterised, as have previously been reported. Batch experiments with sorption of radiotracers of I, Cs, Sr, Ni, Eu, U and Np have been made with eight selected soil samples and one natural groundwater. The solid/liquid ratio in the experiments was 1/48 and sampling were made at 3 hours, 1 day, 7 days, 14 days, 40 days and finally 130 days. Phase separation was made by centrifugation field > 20 kG. Experiments were made in an inert-gas glove-box (O{sub 2} < 1 ppm). The same type of batch sorption experiments was also made with a synthetic groundwater. The recipe for the synthetic groundwater was based on the analyses of the natural groundwater, except for dissolved organic matter, which were omitted. A separate series of supporting experiments, without radionuclide tracers, were made for the measurement of the evolution of pH and Eh. Another series of supporting experiments were made for a number of chemical analyses, where samples were taken at 14 and 130 days only: anion and cation chromatography, alkalinity titrations, total organic carbon (TOC), inorganic carbon, pH and Eh measurements, ICP-MS and -OES analyses of background radiotracer elements and a number of other elements. The general trend of the batch sorption results show specific surface corrected distribution coefficients, R{sub a} (m) that increase with time, but the trend is a levelling out to limiting values. Iodine sorption is generally below the lower detection limit and very few data could be collected for this tracer. Eu generally shows the strongest sorption and some measurements at the later samplings are above the upper detection limit. Results from the batch experiments with peat and natural groundwater at 130 days give R{sub a} values that ranges from 5x10-5 (Sr) to 3x10-4 m (Cs). The order of increasing sorption is: Sr, Ni, Np, Eu, U and Cs. For synthetic groundwater Eu and U sorption is stronger, at least

  3. Oskarshamn site investigation. Batch experiments of I, Cs, Sr, Ni, Eu, U and Np sorption onto soil from the Laxemar area

    International Nuclear Information System (INIS)

    Holgersson, Stellan

    2009-04-01

    Soil and groundwater samples from the Laxemar area have been collected and characterised, as have previously been reported. Batch experiments with sorption of radiotracers of I, Cs, Sr, Ni, Eu, U and Np have been made with eight selected soil samples and one natural groundwater. The solid/liquid ratio in the experiments was 1/48 and sampling were made at 3 hours, 1 day, 7 days, 14 days, 40 days and finally 130 days. Phase separation was made by centrifugation field > 20 kG. Experiments were made in an inert-gas glove-box (O 2 a (m) that increase with time, but the trend is a levelling out to limiting values. Iodine sorption is generally below the lower detection limit and very few data could be collected for this tracer. Eu generally shows the strongest sorption and some measurements at the later samplings are above the upper detection limit. Results from the batch experiments with peat and natural groundwater at 130 days give R a values that ranges from 5x10 -5 (Sr) to 3x10 -4 m (Cs). The order of increasing sorption is: Sr, Ni, Np, Eu, U and Cs. For synthetic groundwater Eu and U sorption is stronger, at least initially, compared with the natural groundwater, but for Cs the sorption is weaker over the whole sampling period. Results from the batch experiments with gyttja and natural groundwater at 130 days give R a values that ranges from 3x10 -5 (Sr) to 1x10 -2 m (Eu). The order of increasing sorption is: Sr, Cs, U, Ni, Np and Eu. For synthetic groundwater the sorption of U is stronger and comparable with Eu. Results from the batch experiments with clay gyttja, type I and natural groundwater at 130 days give R a values that ranges from 1x10 -5 (Sr) to > 1x10 -3 m (Eu). The order of increasing sorption is: Sr, Cs, Ni, U, Np and Eu. For synthetic groundwater the sorption of U is stronger, at least initially, comparable with Eu. For Np, on the other hand, the sorption is weaker and comparable with Sr over the whole sampling period. Results from the batch experiments

  4. Recording of ecological half-lives of 90Sr and 137Cs in terrestrial and aquatic ecosystems

    International Nuclear Information System (INIS)

    Proehl, G.; Fiedler, I.; Ehlken, S.

    2004-01-01

    Within this project, the long-term behaviour of 90 Sr and 137 Cs in foods, feeds and a variety of environmental was analysed. The long-term behaviour is quantified by means of the ecological half-life which integrates all processes that cause a decrease of activity in a given medium as leaching, fixation and erosion. The following results were achieved: - For plant and animal food products, the ecological half-lives are in the range of 4 to 6 and 10 to 20 years for cesium and strontium respectively. The ecological half-lives for the period 1965 to 1985 are slightly shorter than those derived from monitoring measurements performed after 1987, due to the ongoing deposition in the post weapons' fallout period. - According to the German radioecological model that is applied during licensing of nuclear installations to assess radiation exposures to the general due to planned releases, the ecological half-lives for plant food products are 26 and 13 a for cesium and strontium respectively. In radioecological model that is used within the decision support system RODOS, the ecological half-lives are 8 years for Cesium and 14 years for strontium, which agrees well with the finding of this study. - For roe deer, deer, wild boar and forest plants (including mushrooms), under Middle European conditions, the ecological half-lives are about 12 years for cesium. However, in Ukraine, the cesium levels in forest products are much more persistent; in some cases the decrease of activity is only caused by the radioactive decay. - The variability of the long-term behaviour of 137Cs and 90Sr in freshwater ecosystems is much more pronounced than for terrestrial systems. It depends strongly on the sitespecific characteristics. The observed ecological half-lives for 137Cs and 90Sr cover a wide range from several days to several years. - The data to derive ecological half-lives of cesium in soil is relatively poor. For the upper soil layer of 0-10 cm, ecological half-lives were derived

  5. Parametric study of the sorption of Cs(I) and Sr(II) on mixture of bentonite and magnetite using SCM + IEXM

    International Nuclear Information System (INIS)

    Filipska, H.; Stamberg, K.

    2005-01-01

    Full text of publication follows: The behaviour and subsequent fate of released radionuclides in bentonite barrier surrounding the degraded canister is influenced mainly by sorption. We studied sorption processes in such system experimentally and we modelled and simulated them using surface-complexation (SCM) and ion exchange (IExM) models. Our experimental system consisted of: (1) synthetic granitic water with a given ionic strength (0.1 or 0.01 NaNO 3 ), (2) radionuclides studied (10 -6 mol/l CsCl or SrCl 2 .6H 2 O spiked with 137 Cs or 85 Sr), (3) bentonite pre-treated with the aim to remove carbonates, and magnetite as a representative of corrosion products of steel canister. The alkali-metric and acidimetric titrations under exclusion of CO 2 and the percentage of sorption as a function of pH under oxic conditions at room temperature for bentonite, magnetite and their mixtures under different conditions were determined. The resulting data were modelled and appropriate mathematical description was found: SCM non-electrostatic so called Chemical Model (CEM) for the description of sorption on edge sites and ion exchange model (IExM) for sorption on layer sites. Component Additivity Approach (CA) composed of weighted combination of models describing sorption on bentonite and magnetite was verified. In the course of evaluation procedures, the protonation constants, total concentrations of edge sites and layer sites, cation exchange constants and sorption constants for present Cs and Sr forms were obtained by fitting corresponding experimental data. Consequently, CEM+IExM models and the calculated model parameters were used for predictive (simulation) calculations and parametric study of the sorption of Cs(I) and Sr(II) on bentonite, magnetite and their mixtures. The parametric study covered the influence of pH, solid to liquid ratio, bentonite to magnetite ratio, initial concentrations of Cs and Sr, pCO 2 and ionic strength on the values of selectivity coefficients

  6. The concentration of Cs, Sr and other elements in water samples collected in a paddy field

    International Nuclear Information System (INIS)

    Ban-nai, Tadaaki; Hisamatsu, Shun'ichi; Yanai-Kudo, Masumi; Hasegawa, Hidenao; Torikai, Yuji

    2000-01-01

    To research elemental concentrations in soil water in a paddy field, samples of the soil water were collected with porous Teflon resin tubes which were buried in the field. The soil water collections were made at various depth, 2.5, 12.5, 25 and 35 cm from the surface in the paddy field, located in Rokkasho, Aomori, once every two weeks during the rice cultivation period, from May to October in 1998. The paddy field was irrigated from May 7th to July 20th, dried from July 20th to August 5th, then again irrigated until September 16th. Drastic changes of the alkaline earth metal elements, Fe and Mn in soil water samples were seen at the beginning and end of the midsummer drainage. The concentrations of Cs, Fe, Mn and NH 4 in soil water samples showed a similar variation pattern to that of alkaline earth metal elements in the waterlogged period. The change of redox potential was considered a possible cause for the concentration variation for these substances. (author)

  7. The transfer factor of dairy milk from fallout of nuclear explosions to the activity concentration in milk with respect to 137Cs and 90Sr

    International Nuclear Information System (INIS)

    Moere, H.

    1979-06-01

    In the 1977 UNSCEAR report a model has been used to describe the transfer of fallout from nuclear explosions to the activity in milk. Swedish data on milk was fitted to this model by regression analysis. Out data consist of regular countrywide measurements since 1962 for 137 Cs and 1966 for 90 Sr in milk. Fallout measurements of 137 Cs have been made since 1962. To get a better fit, the fallout data has been supplemented with fallout data of 90 Sr derived from data of fallout on the northern hemisphere for the years 1957 - 61. The transfer factors which describe the transfer from fallout to activity in milk were found to be for the countrywide mean values of 137 Cs 8.1 Bqyear/gK/kBq/m 2 and of 90 Sr 5.1 Bqyear/gCa/kBq/m 2 . The transfer factors for 137 Cs for Stockholm, Malmoe and Gothenburg were 5.9, 4.4 and 8.7 Bqyear/gK/kBq/m 2 . These values agree closely to the values found in a survey made by the Institute in 1972. They also seem to agree with the values from Denmark and Norway in the 1977 UNSCEAR report. (author)

  8. METHOD FOR SIMULTANEOUS 90SR AND 137CS IN-VIVO MEASUREMENTS OF SMALL ANIMALS AND OTHER ENVIRONMENTAL MEDIA DEVELOPED FOR THE CONDITIONS OF THE CHERNOBYL EXCLUSION ZONE

    Energy Technology Data Exchange (ETDEWEB)

    Farfan, E.; Jannik, T.

    2011-10-01

    To perform in vivo simultaneous measurements of the {sup 90}Sr and {sup 137}Cs content in the bodies of animals living in the Chernobyl Exclusion Zone (ChEZ), an appropriate method and equipment were developed and installed in a mobile gamma beta spectrometry laboratory. This technique was designed for animals of relatively small sizes (up to 50 g). The {sup 90}Sr content is measured by a beta spectrometer with a 0.1 mm thick scintillation plastic detector. The spectrum processing takes into account the fact that the measured object is 'thick-layered' and contains a comparable quantity of {sup 137}Cs, which is a characteristic condition of the ChEZ. The {sup 137}Cs content is measured by a NaI scintillation detector that is part of the combined gamma beta spectrometry system. For environmental research performed in the ChEZ, the advantages of this method and equipment (rapid measurements, capability to measure live animals directly in their habitat, and the capability of simultaneous {sup 90}Sr and {sup 137}Cs measurements) far outweigh the existing limitations (considerations must be made for background radiation and the animal size, skeletal shape and body mass). The accuracy of these in vivo measurements is shown to be consistent with standard spectrometric and radiochemical methods. Apart from the in vivo measurements, the proposed methodology, after a very simple upgrade that is also described in the article, works even more accurately with samples of other media, such as soil and plants.

  9. Methodology and levels of {sup 137} Cs, {sup 90} Sr and {sup 239} {sup +} {sup 240} Pu in marine sediments from the Brazilian Southern Coast

    Energy Technology Data Exchange (ETDEWEB)

    Figueira, R.C.L. [Universidade Cruzeiro do Sul - CETEC/UNICSUL - Sao Paulo/SP (Brazil); Tessler, M.G.; Mahiques, M.M. de [Instituto Oceanografico da Univesidade de Sao Paulo - IOUSP - Sao Paulo/SP (Brazil); Cunha, I.I.L. [Instituto de Pesquisas Energeticas e Nucleares - IPEN/CNEN-SP -Sao Paulo/SP (Brazil)]. e-mail: figueira@curiango.ipen.br

    2004-07-01

    Methodologies for analysis of {sup 137} Cs, {sup 90} Sr and {sup 239} {sup +} {sup 240} Pu were developed and applied to sediment samples collected along the Brazilian coast. This paper presents the instrumental steps for {sup 137} Cs analysis and the radiochemical steps necessary to analyse {sup 90} Sr and {sup 239} {sup +} {sup 240} Pu. The analytical quality control for radionuclide analysis was verified by participation in international intercomparison exercise running by IAEA as well as in reference material analysis. Further, methodologies were applied in sediments collected from 1976 to 1986 at the Brazilian southern coastal region. {sup 137}Cs levels ranged from 0.37 to 2.03 Bq kg{sup -1}, for {sup 90} Sr from MDC to 8.2 Bq kg{sup -1} and for {sup 239} {sup +} {sup 240} Pu from MDC to 227 m Bq kg{sup -1}. The minimum detectable concentration values (MDC) for {sup 90} Sr and {sup 239} {sup +} {sup 240} Pu were of 0.3 Bq kg{sup -1} and 4.2 mBq kg{sup -1}, respectively. The artificial radioactivity levels in Brazilian sediments are typical values due to fallout deposition and represent reference values for our country. (Author)

  10. Mechanisms of desorption of 134Cs and 85Sr aerosols deposited on urban surfaces

    International Nuclear Information System (INIS)

    Real, J.; Persin, F.; Camarasa-Claret, C.

    2002-01-01

    The radioactive isotopes of cesium and strontium may be deposited on urban surfaces in the case of an accidental atmospheric discharge from a nuclear facility and thus imply a health hazard. In order to handle the decontamination of these surfaces, we have carried out experiments under controlled conditions on tiles and concrete and we have studied the physical and chemical mechanisms at the solid-liquid interface. The deposition of radionuclides was carried out in the form of aerosols indicating an accidental source term. Their desorption by rainwater is low in all cases, of the order of 5-6% for cesium for any material and 29 and 12% for strontium on tile and concrete, respectively. The low desorption values of cesium may be explained by the strong bonding that occurs with the silicates constituting the tile due to virtually irreversible processes of exchange of ions and by the formation of insoluble complexes with the C-S-H gel of concrete. The strontium-tile bonds are weaker, while strontium precipitates with the carbonates of concrete in the form of SrCO 3 . In view of these characteristics, washing solutions with high concentrations of chloride and oxalate of ammonium chosen for their ion-exchanging and sequestering properties were tested on these surfaces. The desorption of cesium improved strongly since it reached 70% on tile and 90% on concrete after 24 h of contact, which is consistent with our knowledge of the bonds between this element and the surfaces. Strontium, given the greater complexity of physical and chemical forms that it may take is less well desorbed. The ammonium chloride improves the desorption (50% and 40%, for tile and concrete, respectively) but the oxalate, while it does not affect desorption on the tiles, decreases that on the concrete since by strongly etching the concrete, it causes the release of carbonate ions that precipitate with strontium

  11. Evaluation of distribution coefficients and concentration ratios of (90)Sr and (137)Cs in the Techa River and the Miass River.

    Science.gov (United States)

    Shishkina, E A; Pryakhin, E A; Popova, I Ya; Osipov, D I; Tikhova, Yu; Andreyev, S S; Shaposhnikova, I A; Egoreichenkov, E A; Styazhkina, E V; Deryabina, L V; Tryapitsina, G A; Melnikov, V; Rudolfsen, G; Teien, H-C; Sneve, M K; Akleyev, A V

    2016-07-01

    Empirical data on the behavior of radionuclides in aquatic ecosystems are needed for radioecological modeling, which is commonly used for predicting transfer of radionuclides, estimating doses, and assessing possible adverse effects on species and communities. Preliminary studies of radioecological parameters including distribution coefficients and concentration ratios, for (90)Sr and (137)Cs were not in full agreement with the default values used in the ERICA Tool and the RESRAD BIOTA codes. The unique radiation situation in the Techa River, which was contaminated by long-lived radionuclides ((90)Sr and (137)Cs) in the middle of the last century allows improved knowledge about these parameters for river systems. Therefore, the study was focused on the evaluation of radioecological parameters (distribution coefficients and concentration ratios for (90)Sr and (137)Cs) for the Techa River and the Miass River, which is assumed as a comparison waterbody. To achieve the aim the current contamination of biotic and abiotic components of the river ecosystems was studied; distribution coefficients for (90)Sr and (137)Cs were calculated; concentration ratios of (90)Sr and (137)Cs for three fish species (roach, perch and pike), gastropods and filamentous algae were evaluated. Study results were then compared with default values available for use in the well-known computer codes ERICA Tool and RESRAD BIOTA (when site-specific data are not available). We show that the concentration ratios of (137)Cs in whole fish bodies depend on the predominant type of nutrition (carnivores and phytophagous). The results presented here are useful in the context of improving of tools for assessing concentrations of radionuclides in biota, which could rely on a wider range of ecosystem information compared with the process limited the current versions of ERICA and RESRAD codes. Further, the concentration ratios of (90)Sr are species-specific and strongly dependent on Ca(2+) concentration in

  12. Transfer factor of "9"0Sr and "1"3"7Cs to lettuce and winter wheat at different growth stage applications

    International Nuclear Information System (INIS)

    Al Attar, Lina; Al-Oudat, Mohammad; Safia, Bassam; Ghani, Basem Abdul

    2015-01-01

    The effect of clay soil contamination time on the transfer factors (F_vs) of "1"3"7Cs and "9"0Sr was investigated in four different growth stages of winter wheat and lettuce crops. The experiment was performed in an open field using lysimeters. The F_vs were the ratio of the activity concentrations of the radionuclides in crops to those in soil, both as dry weight (Bq kg"−"1). Significant difference of log-F_vs was evaluated using one-way Analysis of Variance (ANOVA). Basically, F_vs of "9"0Sr were higher than those of "1"3"7Cs, despite of the application stage or crop' variety. Higher F_vs for both radionuclides were observed for lettuce in comparison to winter wheat. F_vs of "9"0Sr showed comparable trends for both crops with enhanced F_vs obtained when contamination occurred in early stages, i.e. 1.20 for lettuce and 0.88 and 0.02 for winter wheat, straw and grains, respectively. Despite the fluctuation noted in the pattern of F_vs for "1"3"7Cs, soil contaminated at the second stage gave the highest F_vs for lettuce and grains, with geometric means of 0.21 and 0.01, respectively. However, wheat-straw showed remarkable increase in F_v for the latest contamination (ripening stage), about 0.06. It could be concluded that soil contamination at early growth stages would represent high radiological risk for the scenarios studied with an exception to "1"3"7Cs in winter wheat-straw which reflected greater hazard at the latest application. - Highlights: • Higher TFs for both radionuclides were observed for leafy plant in comparison to cereals. • Despite the growth stages & plants' variety, TFs of "9"0Sr were always higher than those of "1"3"7Cs. • TFs of "9"0Sr showed comparable trends in both crops and were higher at earlier growth stages. • Fluctuation noted in TFs for "1"3"7Cs in lettuce with higher TFs at second contamination-stage. • High TFs for "1"3"7Cs when contamination occurred at the latest growth stage of wheat vegetative.

  13. Annual deposition of Sr-90, Cs-137 and Pu-239, 240 from the 1961 - 1980 nuclear explosions: a simple model

    International Nuclear Information System (INIS)

    Hirose, K.; Aoyama, M.; Katsuragi, Y.; Sugimura, Y.

    1987-01-01

    The annual deposition of Sr-90, Cs-137, Pu-239, 240, and Pu-238 were observed from 1959 to 1984 at the Meteorological Research Institute (MRI). In order to interpret the serial trends of the annual radioactive deposition at the MRI, a semi-empirical box model of atmospheric transport was developed. The model divides the atmosphere of the Northern Hemisphere into four compartments: the atmosphere above 21 km, stratosphere below 21 km, active mixing and exchange (AME) layer near the tropopause, and the troposphere. The transfer between the compartments follows the first-order kinetics. The half residence times for transfer between upper and lower stratospheric compartments, between the lower and AME layer compartments, and between the AME layer and troposphere are 0.5, 0.7 and 0.3 yrs, respectively. It is revealed that as a long-term monitoring of the annual deposition of radioactive debris in the mid-latitude area, the model quantitatively permits the calculation of stratospheric inventories and trends of annual deposition of debris injected into the stratosphere which are characterized by apparent residence times of 0.5 to 1.7 yrs. This simple model is useful to predict the annual deposition amount of radioactive debris from the thermonuclear explosion for practical purposes. (author)

  14. 241Am, 137Cs, Sr and Pb uptake by tobacco as influenced by application of Fe chelators to soil

    International Nuclear Information System (INIS)

    Fuhrmann, Mark; Lanzirotti, Antonio

    2005-01-01

    To determine the potential for phytoextraction of 241 Am and other contaminants from soil, accumulation of 241 Am, 137 Cs, Sr, Fe, Al, Pb, and Mg by tobacco was determined for soil applications of two concentrations of ethylenediaminetetraacetic acid (EDTA), citric acid, and ascorbic acid. In tobacco receiving EDTA at 3.1 mmol/kg of soil, 241 Am content of plants averaged 15 Bq/kg (ranging up to 26 Bq/kg) while Fe concentrations became constant at 4.5 mmol/kg. Soil treatment with 18.8 mmol/kg EDTA resulted in average 241 Am concentrations of 29 Bq/kg (19 times higher than controls). Uptake of Pb was similar to 241 Am. In these samples, Fe increased to a maximum of almost 18 mmol/kg and 241 Am content increased linearly with both Fe and Al. Plants receiving ascorbic and citric acids took up smaller quantities of 241 Am, Pb, and Fe, even though these reagents were able to elute about as much Fe from the soil as EDTA. Synchrotron microbeam X-ray fluorescence (SXRF) was used to determine radial distributions of elements in roots and stems with and without EDTA treatment. SXRF maps indicate differences in behavior between Fe and Pb that are consistent with the bulk plant observations and provide insight into changes in metal content of the roots in the presence of EDTA

  15. Retention of simulated fallout nuclides in agricultural crops. 2. Deposition of Cs and Sr on grain crops

    International Nuclear Information System (INIS)

    Eriksson, Aake; Rosen, K.; Haak, E.

    1998-01-01

    Experiments with artificial wet depositions of 134 Cs and 85 Sr at different times during the growth period were carried out. The studies are complementary to the experiences after the Chernobyl fallout and the results are compared with similar earlier Swedish works on nuclide retention in experiments and on fallout in agriculture. The aim has been to cover the nuclide transfer to grain crops after deposition at different times during the growing period. The initial interception capacity per kg d.w., TRd, seemed to depend on the surface/weight ratio of the plant parts considered. Changes in TRd-values were rapid during the early growth but slower in later stages. The reduction half-time was then often 2 weeks for vegetative parts. Considering the fraction of a deposition retained, FRd, the residence half-time had an average length of 3-4 weeks. During that time there were possibilities for cesium penetration into the plant and further transfer to ears and grain. Strontium did not seem to be transferred that way. There was no increase of cesium in the ears per unit d.w. after the initial interception. However, there was a steady increase in the total content, especially after deposition during the latter half of the growth period when about 5 % was retained of cesium, and 2 % of strontium. The retention of fallout caesium in 1964 was statistically estimated to be of about the same size in Swedish grains

  16. Radiation intake and content of 90Sr and 137Cs in the bodies of the USSR residents in 1980-1982

    International Nuclear Information System (INIS)

    Barkhudarov, R.M.; Borisov, B.K.; Knizhnikov, V.A.; Petukhova, Eh.V.; Shepeleva, E.R.

    1987-01-01

    Radiation environment in the USSR territory specified by global fallout of 90 Sr and 137 Cs is characterized by stability. Changes in the levels of food contamination, rations, body concentrations and equivalent irradiation doses lie within the limits of definition errors though there exists a tendency towards a decrease. In 1982 an equivalent irradiation dose for bone marrow was 21.4 mcZv per year and for soft tissue 2.4 mcZv. Integral coefficient of 90 Sr transfer from the fallout to the equivalent dose in the bone marrow equals 0.38 mcCr/Bc/m 2

  17. A study of internal contamination, using 137Cs and 90Sr urinary level, as indicator in the case of nuclear accident

    International Nuclear Information System (INIS)

    Albulescu, L.; Gruia, D.

    1996-01-01

    Our laboratory has from long time a permanent monitoring programme concerning the radioactivity of the environmental factors in Bechet zone (fallout, drinking water, soil) and foodstuffs. The topical results of this programme indicates that there were not significant modifications in the 137 Cs and 90 Sr mean-levels, as indicators in case of nuclear accident, due by Chernobyl accident or by the nearby functioning of NPP in Koslodui. The purpose of this study is to determine the internal contamination of the population in Dolj-district, using the indirect test of determination of radioactivity of excretes (urinary analysis). The daily-urinary levels of 90 Sr and 137 Cs are the best indicators for the human body contamination, in the case of a nuclear accident, conclusion that can be drawn from the Fig.1 below. The variation of these indicators shows that the young people is the most exposed segment of population. (author)

  18. Studying of distribution of 137Cs, 90Sr, 239+240Pu, 241Am and 244Cm according to the organic acids fractions of the alienation zone soils

    International Nuclear Information System (INIS)

    Odintsov, A.A.; Sazhenyuk, A.D.

    2004-01-01

    The paper deals with data of research on the distribution of the radionuclides 137Cs, 90Sr, 239+240Pu, 241Am and 244Cm of ''the Chornobyl rains'' by the fractions of the organic matters of derno-podzolic sandy, derno-meadow and peat soils sampled in the alienation zone of the Chornobyl NPP. Functioning of organic matters was carried according to Tyurin's method. It is stressed that, independently on soil type, 137Cs is connected with the mineral contituent by 80-95%. It is found out that, independently on the soil type, 50-70% 137Sr and 15-45% 241Am are associated with fulvic acid fractions. The 241Am and 244Cm distribution according to organic acids taking into account deviations while carrying out determinations is unambiguous. It is found out that in all the soils tested the main quality of 239+24Pu is connected with humic acids

  19. On accumulation of 90Sr and 137Cs by some lower plants in the vicinity of the Beloyarsky atomic power station in the Urals

    International Nuclear Information System (INIS)

    Nifontova, M.G.; Kulikov, N.V.

    1981-01-01

    The data are given on the content of 90 Sr and 137 Cs in thalluses of the foliose epiphytic lichen Hypogymnia physodes (L) and in a number of the most widely distributed in nature edxble fungi that grow in the forests of the sanitary-protective zone of the Beloyarsk nuclear power station in the Middle Urals: russula-Russula cyaxantha (Schw)Fr; brown cap boletus-Leccinum scabrum (Fe)S.F.Gray, milk-agaric-Lactarius resimus Fr., russula-Russula foetens (Fr.)Fr. It has been ascertained that the concentration of 90 Sr and 137 Cs in epiphytic lichens and edible agaric fungi in the vicinity of the Beloyarsk nuclear power station does not exceed the background content of these radionuclides characteristic of analogous plants in other locations outside the range of a possible effect of the nuclear power station [ru

  20. Removal of Cs+, Sr2+, and Co2+ ions from the mixture of organics and suspended solids aqueous solutions by zeolites

    International Nuclear Information System (INIS)

    Fang, Xiang Hong; Fang, Fang; Lu, Chun Hai; Zheng, Lei

    2017-01-01

    Serving as an excellent adsorbent and inorganic ion exchanger in the water purification field, zeolite 4A has in this work presented a strong capability for purifying radioactive waste, such as Sr 2+ , Cs + , and Co 2+ in water. During the processes of decontamination and decommissioning of suspended solids and organics in low-level radioactive wastewater, the purification performance of zeolite 4A has been studied. Under ambient temperature and neutral condition, zeolite 4A absorbed simulated radionuclides such as Sr 2+ , Cs + , and Co 2+ with an absorption rate of almost 90%. Additionally, in alkaline condition, the adsorption percentage even approached 98.7%. After conducting research on suspended solids and organics of zeolite 4A for the treatment of radionuclides, it was found that the suspended clay was conducive to absorption, whereas the absorption of organics in solution was determined by the species of radionuclides and organics. Therefore, zeolite 4A has considerable potential in the treatment of radioactive wastewater

  1. Diffusion of I{sup -}, Cs{sup +}, and Sr{sup 2+} in compacted bentonite - Anion exclusion and surface diffusion

    Energy Technology Data Exchange (ETDEWEB)

    Eriksen, T.E.; Jansson, Mats [Royal Inst. of Tech., Stockholm (Sweden). Dept. of Nuclear Chemistry

    1996-11-01

    The diffusion of I, Cs and Sr ions in bentonite compacted to a dry density of 1.8 gr/cm{sup 3} and saturated with two groundwaters of different ionic strength have been studied experimentally using the through diffusion technique. The I{sup -} diffusivity and diffusion porosity were found to be concentration independent in the concentration range exp(-8) to exp(-2) mol/dm{sup 3}. The diffusion porosity, being only a fraction of the water porosity for normal groundwaters, is strongly ionic strength dependent due to anion exclusion. The dependence of the diffusion of Cs{sup +} and Sr{sup 2+} on the sorption intensity is accommodated by a model encompassing diffusion of the sorbed cations within the electrical double layer next to the mineral surface in addition to diffusion in the pore water. 18 refs, 12 figs.

  2. Evaluation of small scale laboratory and pot experiments to determine realistic transfer factors for the radionuclides 90Sr, 137Cs, 60Co and 54Mn

    International Nuclear Information System (INIS)

    Steffens, W.; Fuehr, F.; Mittelstaedt, W.

    1980-01-01

    Transfer factors for the root uptake of 90 Sr, 137 Cs, 60 Co and 54 Mn were compared using outdoor lysimeters, Kick-Brauckmann experimental pots under greenhouse conditions and Neubauer cups under growth chamber conditions. The uptake was studied in barley, potatoes, sugar beet and salad vegetables grown on either podsolic or loess soil. The transfer factors for these radionuclides under the specific conditions of the small scale Neubauer cup experiments differed greatly from those obtained from the outdoor lysimeter. In the pot experiments, the transfer factors for 90 Sr, 137 Cs and 54 Mn showed less deviation from the lysimeter results especially in crops grown on podsolic soil. For 60 Co, the transfer factors varied for the different crops grown. Transfer factors obtained in pot experiments can only be applicable to a limited extent to field conditions; factors influencing the transfer factors in pot experiments include soil volume, root density, root/shoot ratio, water supply and fertilizer application rate. (UK)

  3. Spallation reaction study for fission products in nuclear waste: Cross section measurements for {sup 137}Cs and {sup 90}Sr on proton and deuteron

    Energy Technology Data Exchange (ETDEWEB)

    Wang, H., E-mail: wanghe@ribf.riken.jp [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Otsu, H.; Sakurai, H.; Ahn, D.S. [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Aikawa, M. [Faculty of Science, Hokkaido University, Sapporo 060-0810 (Japan); Doornenbal, P.; Fukuda, N.; Isobe, T. [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Kawakami, S. [Department of Applied Physics, University of Miyazaki, Miyazaki 889-2192 (Japan); Koyama, S. [Department of Physics, University of Tokyo, 7-3-1 Hongo, Bunkyo, Tokyo 113-0033 (Japan); Kubo, T.; Kubono, S.; Lorusso, G. [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Maeda, Y. [Department of Applied Physics, University of Miyazaki, Miyazaki 889-2192 (Japan); Makinaga, A. [Graduate School of Medicine, Hokkaido University, North-14, West-5, Kita-ku, Sapporo 060-8648 (Japan); Momiyama, S. [Department of Physics, University of Tokyo, 7-3-1 Hongo, Bunkyo, Tokyo 113-0033 (Japan); Nakano, K. [Department of Advanced Energy Engineering Science, Kyushu University, Kasuga, Fukuoka 816-8580 (Japan); Niikura, M. [Department of Physics, University of Tokyo, 7-3-1 Hongo, Bunkyo, Tokyo 113-0033 (Japan); Shiga, Y. [Department of Physics, Rikkyo University, 3-34-1 Nishi-Ikebukuro, Toshima, Tokyo 171-8501 (Japan); RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); Söderström, P.-A. [RIKEN Nishina Center, 2-1 Hirosawa, Wako, Saitama 351-0198 (Japan); and others

    2016-03-10

    We have studied spallation reactions for the fission products {sup 137}Cs and {sup 90}Sr for the purpose of nuclear waste transmutation. The spallation cross sections on the proton and deuteron were obtained in inverse kinematics for the first time using secondary beams of {sup 137}Cs and {sup 90}Sr at 185 MeV/nucleon at the RIKEN Radioactive Isotope Beam Factory. The target dependence has been investigated systematically, and the cross-section differences between the proton and deuteron are found to be larger for lighter spallation products. The experimental data are compared with the PHITS calculation, which includes cascade and evaporation processes. Our results suggest that both proton- and deuteron-induced spallation reactions are promising mechanisms for the transmutation of radioactive fission products.

  4. Effects of Yamase climatic condition during the pollen mother cell developmental stage on concentrations of Cs and Sr in brown rice

    International Nuclear Information System (INIS)

    Yanai, Masumi; Kobayashi, Daisuke; Yamagami, Mutsumi; Takaku, Yuichi; Hisamatsu, Shun'ichi

    2007-01-01

    Effects of the Yamase climatic condition on the concentration of alkali metals and alkaline earth metals in brown rice were examined in relation to the soil-to-plant transfer factors of 137 Cs and 90 Sr. Rice plants (Oryza sativa L cv. Yumeakari) were cultivated in an artificial climate chamber, and exposed to a simulated Yamase condition for 3 or 7 d during the pollen mother cell developmental stage. In these simulated treatments, temperature and light intensity were set to 5degC lower and 50% lower than the respective control values. Fog was generated with visibility of 70±30 m. Concentrations of alkali metals, alkaline earth metals and the other minor elements in brown rice samples were analyzed. Measured Cs and Sr concentrations were found to be unaffected by the Yamase treatments, while concentrations of Fe, Cu, Zn and Mo were increased. (author)

  5. Regularity of mortality and life span of the experimental animals under the exposure of protracted internal irradiation with radionuclides of 137Cs and 90Sr

    International Nuclear Information System (INIS)

    Yindik, V.M.; Serkyiz, Ya.Yi.; Lips'ka, A.Yi.; Alyistratov, O.V.; Drozd, Yi.P.; Gerasimova, T.B.; Dudchenko, T.M.

    2002-01-01

    It has been shown that exposure to protracted low intense irradiation with low doses, caused by radionuclides ( 137 Cs and 90 Sr) has negative influence on survival indices and expected life span in different groups according to age. Mortality of irradiated animals is mainly caused by development of pathological processes of tumor origin. The frequency of radiation induced tumors is the same with intact control

  6. Influence of agrochemical characteristics of 85Sr and 137Cs in soil samples from the localities around nuclear power plants in Slovak Republic

    International Nuclear Information System (INIS)

    Cipakova, A.; Mitro, A.

    1997-01-01

    Sorption of radiostrontium and radiocesium, two biologically available radionuclides in soils was studied. Experiments were carried out on the soil samples from the localities around nuclear power plants. Adsorption processes are the function of many factors. Multi-para-metrical regression analysis was used for studying of the influence of agrochemical characteristics on sorption of 85 Sr and 137 Cs in observed soil types. (authors)

  7. Effect of chemical pollution on forms of 137Cs, 90Sr and 239,240Pu in arctic soil studied by sequential extraction.

    Science.gov (United States)

    Puhakainen, M; Riekkinen, I; Heikkinen, T; Jaakkola, T; Steinnes, E; Rissanen, K; Suomela, M; Thørring, H

    2001-01-01

    The aim of the present study was to determine the forms of 137Cs, 90Sr and 239,240Pu occurring in different soil horizons using sequential extraction of samples taken from four sites located along a pollution gradient from the copper-nickel smelter at Monchegorsk in the Kola Peninsula, Russia, and from a reference site in Finnish Lapland in 1997. A selective sequential-leaching procedure was employed using a modification of the method of Tessier, Cambell and Bisson ((1979). Analytical Chemistry, 51, 844-851). For 137Cs the organic (O) and uppermost mineral (E1) layer were studied, for 90Sr and 239,240Pu only the uppermost organic layer (Of). The fraction of 137Cs occurring in readily exchangeable form in the organic layer was about 50% at the reference site and decreased as a function of pollution, being 15% at the most polluted site in the Kola Peninsula. There was a clear positive correlation in the O layer between the distance from the smelter and the percentage of 137Cs extracted in the readily exchangeable fraction (Spearman correlation rsp = 0.7805, p = 0.0001), whereas in the E1 layer no correlation was evident. The distribution of 90Sr in the Of layer was similar at all sites, with the highest amounts occurring in exchangeable form and bound to organic matter, whereas stable Sr showed a somewhat different distribution with the highest amount in the oxide fraction. Most of the 239,240Pu was bound to organic matter. Chemical pollution affected the exchangeable fraction of 239,240Pu, which was about 1% at the most polluted site and 4-6% at the other sites.

  8. First-principles study of new series of quaternary Heusler alloys CsSrCZ (Z=Si, Ge, Sn, P, As, and Sb)

    Energy Technology Data Exchange (ETDEWEB)

    Bouabça, A. [Condensed Matter and Sustainable Development Laboratory (LMCDD), University of Sidi Bel-Abbes, Sidi Bel-Abbes 22000 (Algeria); Rozale, H., E-mail: hrozale@yahoo.fr [Condensed Matter and Sustainable Development Laboratory (LMCDD), University of Sidi Bel-Abbes, Sidi Bel-Abbes 22000 (Algeria); Amar, A. [Condensed Matter and Sustainable Development Laboratory (LMCDD), University of Sidi Bel-Abbes, Sidi Bel-Abbes 22000 (Algeria); Wang, X.T. [School of Physics and Electronic Engineering, Chongqing Normal University, Chongqing 400044 (China); Sayade, A. [UCCS, CNRS-UMR 8181, Université d’Artois, Faculté des Sciences Jean Perrin, Rue Jean Souvraz, SP 18, 62307 Lens Cedex (France); Chahed, A. [Condensed Matter and Sustainable Development Laboratory (LMCDD), University of Sidi Bel-Abbes, Sidi Bel-Abbes 22000 (Algeria)

    2016-12-01

    The structural, electronic, magnetic, and thermal properties of new quaternary Heusler alloys CsSrCZ (Z=Si, Ge, Sn, P, As, and Sb) were investigated using the full-potential linearized augmented plane wave (FPLAPW) within the generalized gradient approximation (GGA) and GGA plus modified Becke and Johnson as the exchange correlation. The results showed that all Heusler compounds were stable in Type (I) structure. The CsSrCZ (Z=Si, Ge, Sn) compounds had a nearly HM characteristic, and CsSrCZ (Z=P, As, Sb) compounds were true half-metallic (HM) ferromagnets. The strong spin polarization of p orbital for C, Si, Ge, Sn, P, As, and Sb atoms is found to be the origin of ferromagnetic. The half-metallicity is preserved up to a lattice contraction of 3.45%, 1.69%, 1.69%, 7.16%, 7.16%, and 11.2% for all six quaternary Heusler compounds. We also investigated the thermal effects using the quasi-harmonic Debye model. - Highlights: • Electronic, magnetic, and thermodynamic properties of CsSrCZ (Z=Si, Ge, Sn, P, As, and Sb) are investigated. • Until now, there have been no reports theoretical and experimental studies on d{sup 0} half-metals with quaternary structures. • The strong spin polarization of p orbital for C, Si, Ge, Sn, P, As, and Sb atoms is found to be the origin of ferromagnetic. • The half-metallicity is preserved up to a lattice contraction.

  9. Migration of 137Cs, 90Sr, 239,240Pu and 241Am in the chain soil-soil solution-plant. The soil-soil solution link

    International Nuclear Information System (INIS)

    Sokolik, G.A.; Ovsyannikova, S.V.; Kil'chitskaya, S.L.; Ehjsmont, E.A.; Zhukovich, N.V.; Kimlenko, I.M.; Duksina, V.V.; Rubinchik, S.Ya.

    1999-01-01

    The mobility of 137 Cs, 90 Sr, 239,240 Pu and 241 Am in the link soil-soil solution is analysed for different soil types on the basis of radionuclide distribution coefficients between solid and liquid soil phases. The distribution coefficients allow to differentiate soils in correlation with radionuclide migration rate from the solid phase to the soil solution. The reasons of different radionuclide mobility are considered

  10. Level and dynamics of internal dose from 137Cs and 90Sr formation in connection with ecological diversity of polluted agrogenoses of Ukraine

    International Nuclear Information System (INIS)

    Kravets, A.P.; Grodzinsky, D.M.; Pavlenko, Yu.A.

    2004-01-01

    The purpose of our calculations was estimation of quantitative influence of ecological diversity on levels and dynamics of internal doses formation from long-lived radionuclide such as 137 Cs and 90 Sr. Our estimations have radioecological nature that is they are based on registration of natural mechanisms of agricultural products pollution. It has been realized on the basis of three-module ecological model of assessment of radiological consequences (EMARC) of use of polluted agrocenoses

  11. Evaluation of distribution coefficients and concentration ratios of 90Sr and 137Cs in the Techa River and the Miass River

    OpenAIRE

    Shishkina, Elena A.; Pryakhin, Evgeny A.; Popova, Irina Ya.; Osipov, Denis I.; Tikhova, Yu.; Andreyev, S.S.; Shaposhnikova, I.A.; Egoreichenkov, E.A.; Styazhkina, E.V.; Deryabina, Larisa V.; Tryapitsina, Galina A.; Melnikov, Viktor S.; Rudolfsen, Geir; Teien, Hans-Christian; Sneve, Malgorzata Karpov

    2016-01-01

    Source:http://www.sciencedirect.com/science/article/pii/S0265931X16300959 Empirical data on the behavior of radionuclides in aquatic ecosystems are needed for radioecological modeling, which is commonly used for predicting transfer of radionuclides, estimating doses, and assessing possible adverse effects on species and communities. Preliminary studies of radioecological parameters including distribution coefficients and concentration ratios, for 90Sr and 137Cs were not in full agreement w...

  12. Investigation on leaching of actinide oxides into supercritical fluids

    International Nuclear Information System (INIS)

    Shafikov, D.N.; Kamachev, V.A.; Babain, V.A.; Murzin, A.A.; Shadrin, A.Yu.; Podojnitsin, S.V.

    2006-01-01

    The extraction of actinide oxides into solutions of the TBP-HNO 3 complex in supercritical (SC) CO 2 was investigated. Experiments on the extraction of the TBP-HNO 3 complex into SC CO 2 were first conducted. It was found that a constant concentration of TBP in SC CO 2 of 13.5-14.8 % vol. can be attained using a constant molar ratio of [HNO 3 ]:[TBP] about 2.5 : 1. Joint leaching of uranium, plutonium and neptunium from mixtures of actinide oxides with solutions of TBP-HNO 3 in SC CO 2 was found feasible. If the leaching of uranium is about 95 %, its purification coefficients from major gamma-emitting radionuclides (Cs and Sr) exceed 100, while the purification coefficients of uranium from rare earth elements are 10-20

  13. Estimation of Th, Cs, Sr, I, Co, Fe, Zn, Ca and K in major food components using neutron activation analysis technique

    International Nuclear Information System (INIS)

    Nair, Suma; Bhati, Sharda

    2010-01-01

    The concentration of some radiologically and nutritionally important trace elements: Th, Cs, Sr, I, Co, Fe, Zn, Ca and K were determined in major food components such as cereals, pulses, vegetables, fruits, milk etc. The trace elements in food samples were determined using neutron activation analysis technique which involves instrumental and radiochemical neutron activation analysis. Whereas, the trace elements Th, Cs, K and Sr, are important in radiation protection; Fe and Zn are of importance in nutrition studies and Ca and I have dual importance, both in nutrition and radiation protection. The results of analysis show that among the food materials, higher concentrations of Th, Cs, Sr, K, Fe, Zn and Co were found in cereals and pulses. In case of Ca, the milk appears to be the main contributor towards its dietary intake. The estimated concentrations of the trace elements in food components can be employed in determining the daily dietary intake of these elements which in turn can be used for their biokinetic studies. (author)

  14. Estimate of the internal doses received by the population of Bucharest due to 137 Cs and 90 Sr intake in the first five years after the Chernobyl accident

    International Nuclear Information System (INIS)

    Toader, Maria; Vasilache, R. A.

    1995-01-01

    The evolution of the 137 Cs and 90 Sr daily intake between April 1986 and March 1991 as well as the internal doses resulting from ingestion of contaminated food is presented for a group of adults living in Bucharest. The results indicate that the effective doses due to 137 Cs and 90 Sr dietary intake had the highest values in the first year after the Chernobyl accident, namely, 796 μSv as a result of 137 Cs dietary intake and 23 μSv as a result of the 90 Sr dietary intake. The effective doses committed annually due to the Caesium-137 dietary intake decreased very fast from 796 μSv committed in the first year after the accident to 7.3 μSv committed in the fifth year after the accident. Although the effective dose committed in the first year after the accident due to the Strontium-90 dietary intake was much smaller than the dose due to the Caesium-137 (23 μSv), the decrease was slower so that the effective dose committed in the fifth year after the accident due to the Strontium-90 dietary intake was 7.5 μSv. (authors)

  15. Electric conductivity of solid solutions the Cs3-2xMxPO4 (M=Ba, Sr, Ca, Mg) systems

    International Nuclear Information System (INIS)

    Burmakin, E.I.; Stroev, S.S.; Shekhtman, G.Sh.; Antonov, B.D.

    2003-01-01

    The solid solutions in the Cs 3-2x M x PO 4 (M=Ba, Sr, Ca, Mg) system are synthesized and their thermal behavior and electric conductivity are studied. The introduction of the alkaline earth metal cations into cesium orthophosphates is accompanied by the shift of the phase transition occurring in the pure Cs 3 PO 4 at 450-620 Deg C into the low-temperature area as well as by increase in the cesium-cation conductivity at low temperatures. The electric conductivity in the area of existence of the Cs 3 PO 4 high-temperature modification slightly depends on the availability and concentration of the modifying additions, which make it possible to suppose the calcium sublattice structural disordering [ru

  16. Accumulation and distribution of 137Cs and 90Sr in the body of the wild boar (Sus scrofa) found on the territory with radioactive contamination

    International Nuclear Information System (INIS)

    Gulakov, Andrey Vladimirovich

    2014-01-01

    We studied the concentration and distribution of 137 Cs and 90 Sr in the bodies of 188 wild boar (Sus scrofa Linnaeus, 1758) taken near the Chernobyl site. Of these, 111 animals were taken in the Alienation Zone, 41 animals were taken in the Permanent Control Zone and 36 animals were taken in the Periodic Control Zone. The samples included muscle and bone (rib) tissues and samples of heart, liver, lungs, kidneys, spleen, genitals and skin. The weight of the samples was 0.5 kg fresh weigh. The average concentration of 137 Cs in the muscles of the wild boar found in the Alienation Zone was 46 ± 10 kBq/kg, in the Permanent Control Zone – 13 ± 3.0 kBq/kg and in the Periodic Control Zone – 0.6 ± 0.1 kBq/kg. The largest concentration of 137 Cs was detected in the muscle tissue and kidneys taken animals. In some samples of muscle tissue it reached more than 660 kBq/kg. The 137 Cs concentrations were also high in heart and spleen up 64.3 kBq/kg and 67.5 kBq/kg – animals from the Alienation Zone and 10.3–10.6 kBq/kg – animals from the Permanent Control zone. The lowest concentration of 137 Cs was found in the lungs and skin of animals. The analyses of 90 Sr concentration in the organs and tissues of the wild boar showed that 90 Sr was concentrated mainly in the bone tissue. The average level of 90 Sr concentration in bone was 17.6 kBq/kg fresh weight animals from the Alienation Zone and 13.47 kBg/kg – animals from the Permanent Control zone. In muscle tissues and organs contained 90 Sr – 30.0–110.0 Bq/kg in the Alienation Zone and 11.0–30.0 Bq/kg in the Permanent Control zone

  17. Fate of 137Cs, 90Sr and 239+240Pu in soil profiles at a water recharge site in Basel, Switzerland.

    Science.gov (United States)

    Abraham, Johannes; Meusburger, Katrin; Waldis, Judith Kobler; Ketterer, Michael E; Zehringer, Markus

    2018-02-01

    An important process in the production of drinking water is the recharge of the withdrawn ground water with river water at protected recharge fields. While it is well known that undisturbed soils are efficiently filtering and adsorbing radionuclides, the goal of this study was to investigate their behaviour in an artificial recharge site that may receive rapid and additional input of radionuclides by river water (particularly when draining a catchment including nuclear power plants (NPP)). Soil profiles of recharge sites were drilled and analysed for radionuclides, specifically radiocesium ( 137 Cs), radiostrontium ( 90 Sr) and plutonium ( 239+240 Pu). The distribution of the analysed radionuclides were compared with an uncultivated reference soil outside the recharge site. The main activity of 137 Cs was located in the top soil (4.5-7.5 cm) and reached down to a depth of 84 cm and 48 cm for the recharge and the reference site, respectively. The found activities of 239+240 Pu originate from the global fallout after 1950. 239+240 Pu appeared to be strongly adsorbed onto soil particles. The shape of the depth profile was similar to 137 Cs, but also similar between the recharge and the reference site. In contrast, 90 Sr showed a uniform distribution over the entire depth of the recharge and reference profiles indicating that 90 Sr already entered the gravel zone and the ground water. Elevated inventories of the radionuclides were observed for the recharge site. The soil of the recharge field exhibited a threefold higher activity of 137 Cs compared to the reference soil. Also for 239+240 Pu higher inventories where observed for the recharge sites (40%). 90 Sr behaved differently, showing similar inventories between reference and recharge site. We estimate that 75-89% of the total inventory of 137 Cs in the soil at the recharge site (7.000 Bq/m 2 ) originated from the fallout of the Chernobyl accident and from emissions of Swiss NPPs. This estimate is based on the

  18. Time-dependent transfer of 54Mn, 60Co, 85Sr and 137Cs from a sandy soil to soybean plants

    International Nuclear Information System (INIS)

    Choi, Yong-Ho; Lim, Kwang-Muk; Jun, In; Keum, Dong-Kwon; Han, Moon-Hee

    2011-01-01

    Greenhouse experiments were performed to investigate the dependence of 54 Mn, 60 Co, 85 Sr and 137 Cs transfer from sandy soil to soybean plants on the growth stage when a radioactive deposition occurs. A solution containing 54 Mn, 60 Co, 85 Sr and 137 Cs was applied onto the soil surfaces in the lysimeters at six different times -2 d before sowing and 13, 40, 61, 82 and 96 d after sowing. Soil-to-plant transfer was quantified with a transfer factor (m 2 kg -1 -dry) specified for the deposition time. The transfer factor values of 54 Mn, 60 Co, 85 Sr and 137 Cs for the seeds were in the range of 1.5×10 -3 -1.0×10 -2 , 4.7×10 -4 -3.2×10 -3 , 5.7×10 -4 -1.0×10 -2 and 3.0×10 -5 -2.7×10 -4 , respectively, for different deposition times. The corresponding values for the leaves were 6.4×10 -3 -3.2×10 -2 , 4.3×10 -4 -2.0×10 -3 , 5.1×10 -3 -5.3×10 -2 and 9.2×10 -5 -1.9×10 -4 , respectively. The values for the seeds were on the whole highest following the middle-growth-stage deposition. After the pre-sowing deposition, the transfer factor values of 54 Mn, 60 Co and 137 Cs for the seeds decreased annually so those in the fourth year were 53%, 75% and 34% of those in the first year, respectively. The present results may be useful for predicting the radionuclide concentrations in soybean plants due to their root uptake following an acute soil-deposition during the vegetation period, and for validating a relevant model. (author)

  19. Riverine transport of Cs-137 and Sr-90 into the Black Sea after Chernobyl accident (data analysis and methodological aspects of monitoring)

    International Nuclear Information System (INIS)

    Kanivets, V.V.; Voitsekhovitch, O.V.; Khrystyk, B.F.

    1999-01-01

    Upper part of Dnieper catchment had been heavily contaminated after the Chernobyl accident and serves as a main source of the secondary input of radionuclides to the river. As a result of fast sorption of dissolved radiocesium by suspended sediments and sedimentation of contaminated particles to the bottom, practically all the 137 Cs having entered into the upper reaches of the Dnieper river after the Chernobyl accident was retained in the Dnieper reservoirs and the Dnieper-Bug estuary. Taking into account relatively high mobility of 90 Sr the extent of it's trapping by Dnieper reservoirs is significantly less comparatively to 137 Cs and accounted as some 60-70%. The Danube River catchment is characterized by less radioactive contamination, in comparison with the Dnieper catchment, and more homogeneous spatial distribution of this contamination. Suspended particles play a crucial role in 137 Cs transport by Danube to the Black Sea. Regular observations showed, that in average 60-70% of 137 Cs transport to the Black Sea is associated with suspended particles. The conditions for water selfpurification are absent on the Danube River due to the high velocity of the currents along the whole it length. Therefore, the significant portion of 137 Cs and other contaminants in particulate phase washed out from the upper part of basin can reach the Black Sea. The correct accounting of 137 Cs discharge on suspended particles by river strictly depends on representativity of samples used in calculation. Sampling procedure which had been done in uncorrect way could cause in significant underestimation of 137 Cs concentration up to 10 times. (author)

  20. Comparison of the NaI-CsI phoswich and a hyperpure germanium array for in vivo detection of the actinides

    Energy Technology Data Exchange (ETDEWEB)

    Berger, C D; Goans, R E [Oak Ridge National Lab., TN (USA)

    1981-04-01

    An array of hyperpure germanium detectors has recently been employed at ORNL for the identification and quantification of internally deposited actinides. Its advantages over the phoswich detector - the current state-of-the-art for detection of the actinides - were found to be improved background reduction and superior energy resolution. The germanium system and the currently operating phoswich system are discussed and compared. The improvement in performance of the germanium system over the phoswich system (a factor of 2.5 for /sup 239/Pu and 15.3 for /sup 241/Am) appears to justify the financial investment, particularly when /sup 241/Am is used as an indirect means of detection and measurement of /sup 239/Pu.

  1. Measurements of instant-release source terms for 137Cs, 90Sr, 99Tc, 129I and 14C in used CANDU fuels

    International Nuclear Information System (INIS)

    Stroes-Gascoyne, S.

    1996-01-01

    Combined gap and grain-boundary inventories of 137 Cs, 129 I, 90 Sr, 99 Tc and 14 C were measured in 15 used CANDU fuel elements by leaching crushed fuel samples. A good correlation between the combined gap and grain-boundary inventories of 137 Cs and 129 I was found, suggesting that these fission products exhibit similar behavior in CANDU fuel. The expected correlation between combined gap and grain-boundary inventories of 137 Cs and 129 I with calculated fission-gas release to the gap and grain boundaries could only be confirmed for lower power fuels ( 90 Sr were higher than expected and showed no correlation with calculated fission-gas release. No values for the combined gap and grain-boundary inventories of 99 Tc were obtained because 99 Tc in used fuel samples is very insoluble and appears to require oxidation prior to dissolution. Combined gap and grain-boundary inventories of 14 C appeared to be independent of fuel power or burnup. (orig.)

  2. Evolution of {sup 137}Cs and {sup 90}Sr content of the main foodstuff in Bucharest area after the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Toader, M; Vasilache, R A [Institute of Hygiene and Public Health, Bucharest (Romania)

    1997-09-01

    Soon after the Chernobyl accident, the radioactive cloud, carrying the nuclides released into the atmosphere, reached Romania and, due to the rainy weather, an important fallout occurred over the Romanian territory. The most important contaminants for Romania were I{sup 131}, Cs{sup 134}, Cs{sup 137} and Sr{sup 90}. As in many other countries, in the first days, I{sup 131} had the main contribution to the irradiation dose released to the population. After its decay, and the decay of other short-lived radionuclides, Cs{sup 137} and Sr{sup 90} remained the most important contaminants. The principal route of intake for these two radionuclides is considered to be the ingestion of contaminated foods. To assess the radioactive burden of foods, a long term, large scale survey was initiated at the National Institute of Hygiene and Public Health (INISP). These results were then used to assess the doses committed to cesium and strontium intake and the excedentary cancer risk for the population from Bucharest area. 5 refs, 8 figs.

  3. The influence of interstitial water velocity on the migration of 85Sr and 137Cs in an aerated sandy soil layer

    International Nuclear Information System (INIS)

    Ohnuki, Toshihiko; Takebe, Shinichi; Yamamoto, Tadatoshi; Wadachi, Yoshiki

    1983-01-01

    The influence of interstitial water velocity on the migration of Sr-85 and Cs-137 in an aerated sandy soil layer was studied at different feed water velocities and feed times. As well known, it was found that Sr-85 migrated with interstitial water, but Cs-137 little migrated with interstitial water. The apparent migration velocity for each fraction corresponding to three concentrations (2 x 10 -2 , 1 x 10 -2 and 5 x 10 -3 μCi/g) of Sr-85 was further investigated. At constant interstitial water velocity (1cm/ min), different values were given for the apparent migration velocity of three fractions, and the fraction with thin concentration migrated faster. At constant feeding time (100hr), there was a linear relationship between apparent migration velocity of three fractions and interstitial water velocity, in the range of slow water velocity ( -2 and 5 x 10 -3 μCi/g) and interstitial water velocity, in the range of fast water velocity (> 1cm/min). (author)

  4. Contamination of terrestrial ecosystem components with 90Sr, 137Cs, and 226Ra caused by the deterioration of the multibarrier protection of radioactive waste storages

    Science.gov (United States)

    Latynova, N. E.

    2010-03-01

    The spatial-temporal features of the radioactive contamination of terrestrial ecosystem components caused by the deterioration of the multibarrier protection of regional radioactive waste storages of the State Research Center of the Russian Federation-Leipunskii Institute of Physics and Power Engineering at the input of radionuclides into the soil and ground water were studied. The composition of the radioactive contamination was determined, and the hydrological and geochemical processes resulting in the formation of large radioactive sources were described. The natural features of the radioactive waste storage areas favoring the entry of 90Sr, 137Cs, and 226Ra into the soils and their inclusion in the biological turnover were characterized. The directions of the horizontal migration of 90Sr, 137Cs, and 226Ra and the sites of their accumulation within the superaquatic and aquatic landscapes of a near-terrace depression were studied; the factors of the 90Sr accumulation in plants and cockles were calculated. The results of the studies expand the theoretical concepts of the mechanisms, processes, and factors controlling the behavior of radionuclides at the deterioration of the multibarrier protection of radioactive waste storages. The presented experimental data can be used for solving practical problems related to environmental protection in the areas of industrial nuclear complexes.

  5. Effect of mycorrhizal infection on root uptake by pine seedlings and redistribution of three contrasting radio-isotopes: 85Sr, 95mTc and 137Cs

    International Nuclear Information System (INIS)

    Plassard, C.; Ladeyn, I.; Staunton, S.

    2004-01-01

    Mycorrhizal infection is known to improve phosphate nutrition and water supply of higher plants. It has been reported to both increase the uptake of potentially toxic pollutant elements and to protect plants against toxic effects. Little is known about the effect of mycorrhizal infection on the dynamics of radioactive pollutants in soil-plant systems. The aim of this study was to compare the root uptake and root-shoot transfer of three radio-isotopes with contrasting chemical properties ( 85 Sr, 95m Tc and 137 Cs) in mycorrhizal and control, non mycorrhizal plants. The plant studied was Pinus pinaster and the associated ecto-mycorrhizal fungus was Rhizopogon roseolus (strain R18-2). Plants were grown under anoxic conditions for 3 months then transferred to thin layers of autoclaved soil and allowed to grow for four months. After this period, the rhizotrons were dismantled, and plant tissue analysed. Biomass, nutrient content (K, P, N, Ca) and activities of each isotope in roots, shoots and stems were measured, and the degree of mycorrhizal infection assessed. The transfer factors decreased in the order Tc>Sr>Cs as expected from the degree of immobilisation by soil. No effect of mycorrhizal infection on root uptake was observed for Sr. Shoot activity concentration of Tc was decreased by mycorrhizal infection but root uptake correlated well with mycelial soil surface area. In contrast, Cs shoot activity was greater in mycorrhizal than control plants. The uptake and root to shoot distribution shall be discussed in relation to nutrient dynamics. (author)

  6. The role of pore soil solutions in redistribution of 137Cs, 90Sr, 239,240Pu and 241Am within soil-vegetative cover

    International Nuclear Information System (INIS)

    Ovsiannikova, S.V.; Sokolik, G.A.; Kilchitskaya, S.L.; Eismont, E.A.; Zhukovich, N.V.; Kimlenko, I.M.

    1998-01-01

    The role of pore soil solutions in the migration of 137 Cs, 90 Sr, 239,240 Pu and 241 Am within soil-vegetative cover of natural ecosystems was examined. The soil solutions were found to play an important role in the redistribution of 137 Cs, 90 Sr, 239,240 Pu and 241 Am in the soil-plant systems. Obvious relationships between the distribution coefficients of radionuclides between solid and liquid phases (K d ) and the intensity of vertical migration of 137 Cs, 90 Sr, 239,240 Pu and 241 Am along the soil profiles and with intensity of their accumulation by grass vegetation of natural meadows have been obtained. It means that the distribution coefficient may be used as a criterion of the radionuclide mobility in the soil-plant system whatever its level of radioactive contamination is. The influence of the degree of soil moistening, the content of mobile radionuclide forms in the soils and some characteristics of pore soil solutions (pH, content of K + , Ca 2+ , NH 4 + , water soluble organic substances) on the concentration of radionuclide in the soil solutions and on the value of radionuclide distribution coefficient have been analysed. The results of investigation are of great importance in the evaluation of radioecological situation and in solution of problems of radioecological rehabilitation of the contaminated territories. The received data constitute a part of scientific basis for the development of a system of countermeasures to decrease the mobility and biological availability of radionuclides of high and very high radiotoxicity

  7. Interlaboratory comparison of the determination of 137Cs and 90Sr in water, food and soil: preparation and characterization of test materials

    International Nuclear Information System (INIS)

    Fuks, L.; Polkowska-Motrenko, H.

    2006-01-01

    Only reliable analytical results can serve as a basis of meaningful evaluation and protection of the environment against radioactive contaminants. So, laboratories dealing with the environmental radioactivity determinations should regularly demonstrate their ability to produce acceptable results. Since 2002, every two years organization of national interlaboratory comparisons (ILC) on the determination of different radionuclides in food and environmental samples is required by the Polish law. The aim of the paper is presentation how test materials applied in the Institute of Nuclear Chemistry and Technology (INCT, Warsaw, Poland) for the 2004 ILC on the determination of 137 Cs and 90 Sr in water, food and soil were prepared. (author)

  8. The estimation of daily intake and organ content of Cs, I, Sr, Th and U in Indian population: Application to the study of their biokinetics

    International Nuclear Information System (INIS)

    Dang, H.S.; Jaiswal, D.D.; Pullat, V.R.; Parameswaran, M.; Krishnamony, S.

    1998-01-01

    The analytical methods involving both instrumental and radiochemical neutron activation techniques (INAA and RNAA) are being standardised for the determination of the elements Cs, I, Sr, Th and U in various kinds of biological samples. The sampling method proposed to be adopted for the estimation of the daily dietary intake, of the above elements is described. Also reported in this paper are the preliminary results on the concentrations of these elements in the food ingredients which form important components of the diet of Indian population. (author)

  9. Spallation reaction study for fission products in nuclear waste: Cross section measurements for 137Cs, 90Sr and 107Pd on proton and deuteron

    Directory of Open Access Journals (Sweden)

    Wang He

    2017-01-01

    Full Text Available Spallation reactions for the long-lived fission products 137Cs, 90Sr and 107Pd have been studied for the purpose of nuclear waste transmutation. The cross sections on the proton- and deuteron-induced spallation were obtained in inverse kinematics at the RIKEN Radioactive Isotope Beam Factory. Both the target and energy dependences of cross sections have been investigated systematically. and the cross-section differences between the proton and deuteron are found to be larger for lighter fragments. The experimental data are compared with the SPACS semi-empirical parameterization and the PHITS calculations including both the intra-nuclear cascade and evaporation processes.

  10. Adsorption of Cs(I), Sr(II), Eu(III), Co(II) and Cd(II) by Al2O3

    International Nuclear Information System (INIS)

    Shiao, S.Y.; Egozy, Y.; Meyer, R.E.

    1981-01-01

    Adsorption of Cs(I), Sr(II), Eu(III), Co(II) and Cd(II) by Al 2 O 3 was carried out over a wide range of NaCl concentration and solution pH. In the medium pH region (pH 5 to 9), adsorption depends strongly on pH and less on salt concentration. However, in the high pH region (pH above 9), the salt dependence of the distribution coefficient becomes important. (author)

  11. Actinides-1981

    International Nuclear Information System (INIS)

    1981-09-01

    Abstracts of 134 papers which were presented at the Actinides-1981 conference are presented. Approximately half of these papers deal with electronic structure of the actinides. Others deal with solid state chemistry, nuclear physic, thermodynamic properties, solution chemistry, and applied chemistry

  12. Actinides-1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-09-01

    Abstracts of 134 papers which were presented at the Actinides-1981 conference are presented. Approximately half of these papers deal with electronic structure of the actinides. Others deal with solid state chemistry, nuclear physic, thermodynamic properties, solution chemistry, and applied chemistry.

  13. Sorption and desorption of Sr-90 and Cs-137 by sediments of the Sozh-river valley and border water collections

    International Nuclear Information System (INIS)

    Onoshko, M.P.

    2001-01-01

    From the last literature analysis it follows, that to studying of sorption and desorption soil, some rocks and minerals properties concerning radioisotopes the steadfast attention of researchers is paid nowadays. The materials of heavy particles sorption kinetics, the action of adsorption molecules and ions from solutions on leaching products are examined. Sr-90, Cs-137, Pu-239,240 diffusion is estimated. It is found out, that sorbed and desorbed amount of radioisotopes is proportionally to their concentration in soil, and sorption (S) and distributions (Cd) factors do not depend on soil contamination density, and are determined by its physical and chemical properties, parity of firm and liquid phases. It is judged, that increase of soil absorbing properties by the increase of sorbent entering are unpromising, as sorption soil capacity is filled by Cs-137 only in thousand shares of per cent from the sorbent amount, which can be absorbed by soil. With the reference to the conditions of Belarus, experiments and natural supervision on Sr-90 and Cs-137 sorption by Fe, Mn, Si, Al, Ti hydroxides were executed. At experimental researches of electrolyte influence on radioisotope sorption by peat soils Cd amount lines were established. Sediments under certain conditions, due to desorption, become a source of the secondary contamination of natural waters up to ecologically dangerous concentration. Radioisotopes desorption ambiguity is connected to many parallel proceeding processes: exchange sorption on organic and mineral components, co-sedimentation with one-and-a-half Fe, Al and Mn hydroxides and also depends on solutions structure, cationic exchange rocks and soil capacities, concentration of competing ions. At low radioisotopes contents desorption is insignificant, at high - their extraction does not depend on reagent concentration. We carried out the experiment on studying Cs-137 and Sr-90 sorption-desorption from sediments Sozh-river valley and border water

  14. Physico-chemical characterisation and sorption measurements of Cs, Sr, Ni, Eu, Th, Sn and Se on Opalinus clay from Mont Terri

    International Nuclear Information System (INIS)

    Lauber, Matthias; Baeyens, Bart; Bradbury, Michael H.

    2000-12-01

    Opalinus Clay is currently under investigation as a potential host rock for the disposal of high level and long-lived intermediate radioactive waste. A throughout physico-chemical characterisation was carried out on a bore core sample from the underground rock laboratory Mont Terri (Canton Jura). The results of these investigations indicate that the major characteristics (mineralogy, cation exchange capacity, cation occupancies, selectivity coefficients, chloride and sulphate inventories) were very similar to a different core sample, previously used for pore water modelling studies. It was concluded that the pore water compositions derived in the earlier studies were reliable and could be used in this work. The organic matter which dissolved from the Opalinus Clay rock was not humic or fulvic acids and the concentration remaining in the liquid phase in the sorption experiments was < 0.5 ppm C. The organic matter is therefore considered to have little or no influence on the sorption behaviour of the studied radionuclides. Redox potential measurements of the Opalinus Clay/synthetic pore water system inside the glove boxes indicated anoxic conditions. The main focus of the experimental work presented here is on the sorption behaviour of Cs (I), Sr (II), Ni (II), Eu (III), Th (IV), Sn (IV) and Se (IV) on Opalinus Clay equilibrated with synthetic pore waters at pH 6.3 and 8. Sorption isotherms were measured for Cs, Ni, Eu, Th and Se. Single point data were measured for Sr and Sn. For all radionuclides studied the sorption kinetics were measured first. The times required to complete the sorption on the Opalinus Clay varied between one day for Th and one month for Ni and Se. Within the concentration ranges under study the uptake of Cs, Ni, Eu and Se on Opalinus Clay was non-linear, whereas for Th a linear sorption behaviour was observed. For Ni, Eu and Th the sorption increased with increasing pH. For Cs a pH independent sorption behaviour was observed. The concentration

  15. Wash-off of Sr-90 and Cs-137 from two experimental plots. Model testing using Chernobyl data

    International Nuclear Information System (INIS)

    Konoplev, A.; Bulgakov, A.; Hoffman, O.; Thiessen, K.

    1996-09-01

    Surface water runoff from contaminated land is one of the major processes responsible for the contamination of water bodies. For example, the large area of land contaminated after the Chernobyl accident has become a continuing source of radionuclide contamination for natural waters and the aquatic ecosystem. Based on data from the Chernobyl accident, the 'Wash-off' scenario was developed to provide an opportunity to test models concerned with the movement of trace contaminants from terrestrial sources to water bodies. In particular, this scenario provides an opportunity for (1) evaluation of the movement of contaminants from soil to water, (2) calculation of the alteration and migration of contaminants in soil over different time scales, (3) increased understanding of contaminant transport at the process level, and (4) development and use of methods for estimation of key parameters. Modelers were provided with descriptions of two experimental plots near the Chernobyl NPP, one using simulated heavy rain (plot HR) and one using snow melt (plot SM). Initial information for plot HR included soil properties; hydrographs of rainfall and runoff dynamics; the time of application of rainfall; rainfall amounts, duration, and intensities; soil moisture content before the application of rainfall; regional data on average monthly precipitation and temperature; recorded information on naturally occurring precipitation between May and October 1986; and chemical forms of radionuclides in the soil of the plots prior to the experiments. Information for plot SM included the soil description and properties, snow storage in the snow melt period of 1988, chemical composition of the snow water, a hydrograph of the runoff dynamics, chemical radionuclide forms in the soil at the end of the experiment, and air and soil temperatures for the plot during the snow melt period. For each experimental plot, modelers were requested to estimate the vertical distribution of radionuclides (137 Cs and

  16. Forecasting of accumulation of Cs 137 and Sr 90 in the herbage of the main types of the Belarus Palessje meadows utilizing agrochemical soil properties

    International Nuclear Information System (INIS)

    Podolyak, A.G.; Bogdevich, I.M.; Ivashkova, I.I.

    2007-01-01

    On the basis of long-term stationary experience it was established that the minimum accumulation of Cs 137 and Sr 90 in the herbage of the waterless valley, marshed and flood types of the Belarus Palessje meadows contaminated by Chernobyl radionuclides is seen when the optimum basic agrochemical soil properties are achieved with the application of the scientifically reasonable protective measures. It was demonstrated that in the remote period of the accident for the prognosis of radionuclides contents in natural and cultural meadows herbage it is advisable to use of transfer factors (TFa, Bq/kg : kBq/m2) based on the complex agrochemical parameters - basic saturation degree (V, %) and agrochemical cultivation soils index (Iac), which take into account several soil characteristics simultaneously. This article provides the equations of linear and multiple regressions that can be used to calculate the transfer factors for Cs 137 and Sr 90 uptake and the herbage contamination degree for the main types of meadows of the region, which will allow one to reduce the volume of forages production (hay, green bulk) that is not adequate to the established permissible levels: Republican allowable levels of the contents of cesium-137 and strontium-90 in agricultural raw material and forages. (authors)

  17. Removal of Cs{sup +}, Sr{sup 2+}, and Co{sup 2+} ions from the mixture of organics and suspended solids aqueous solutions by zeolites

    Energy Technology Data Exchange (ETDEWEB)

    Fang, Xiang Hong; Fang, Fang; Lu, Chun Hai [College of Nuclear Technology and Automation Engineering, Chengdu University of Technology, Chengdu (China); Zheng, Lei [Southwest University of Science and Technology, Key Laboratory of Solid Waste Treatment and Resource Recycle, Ministry of Education, Mianyang (China)

    2017-04-15

    Serving as an excellent adsorbent and inorganic ion exchanger in the water purification field, zeolite 4A has in this work presented a strong capability for purifying radioactive waste, such as Sr{sup 2+}, Cs{sup +}, and Co{sup 2+} in water. During the processes of decontamination and decommissioning of suspended solids and organics in low-level radioactive wastewater, the purification performance of zeolite 4A has been studied. Under ambient temperature and neutral condition, zeolite 4A absorbed simulated radionuclides such as Sr{sup 2+}, Cs{sup +}, and Co{sup 2+} with an absorption rate of almost 90%. Additionally, in alkaline condition, the adsorption percentage even approached 98.7%. After conducting research on suspended solids and organics of zeolite 4A for the treatment of radionuclides, it was found that the suspended clay was conducive to absorption, whereas the absorption of organics in solution was determined by the species of radionuclides and organics. Therefore, zeolite 4A has considerable potential in the treatment of radioactive wastewater.

  18. Determination of soil-to-plant transfer factors of {sup 137}Cs and {sup 90}Sr in the tropical environment of Bangladesh

    Energy Technology Data Exchange (ETDEWEB)

    Mollah, A.S.; Begum, A. [Atomic Energy Research Establishment (AERE), Savar, Dacca (Bangladesh); Ullah, S.M. [University of Dhaka (Bangladesh). Department of Soil Science

    1998-07-01

    Soil-to-plant transfer factors (TF) of {sup 137}Cs and {sup 90}Sr have been determined for different plants/crops, such as rice, beans, peanuts, pineapple, cabbage, tomato, spinach and grass. They were obtained from radioisotope experiments on plants grown in pots under outdoor ambient tropical conditions for three growing seasons (1994-1996). In the case of {sup 137}Cs and concerning the above mentioned plants/crops, the average TFs were found to be 0.28, 0.25, 0.77, 0.19, 0.23, 0.28, 0.59 and 0.18, respectively. In the case of {sup 90}Sr, the average TFs were found to be 0.82, 0.51, 0.20, 0.82, 0.69, 0.59, 0.91 and 0.84, respectively. A minor seasonal variation was observed. This study provides a database of TFs for tropical environments to be used, e.g., for radiological safety assessment models. (orig.) With 1 fig., 3 tabs., 12 refs.

  19. Trace elements (Rb, Cs, Sr, Pb, Th, U) bioavailability potential and speciation in the Piracicaba river bottom sediments, Sao Paulo, Brazil

    International Nuclear Information System (INIS)

    Fernandes, Alexandre Martins; Mortatti, Jefferson; Oliveira, Helder de; Bibian, Joao Paulo Rambelli; Moraes, Graziela Meneghel de; Probst, Jean-Luc

    2007-01-01

    It was studied the bioavailability potential of Rb, Cs, Sr, Pb, Th and U and their chemical speciation in Piracicaba river bottom sediments. This river system crosses important agricultural and urban areas of Sao Paulo state, which groups about 3 million people and receives a large load of agricultural, industrial and domestic wastes. The procedure used to estimate trace elements bioavailability potential was related to a 7-step sequential chemical extraction. This scheme was designed to dissolved and separate sample chemical phases, which can be affected by changes in physical-chemical conditions; in the following order: water soluble, exchangeable, bound to carbonates or acid fraction, bound to Mn-oxides, bound to Fe-oxides and bound to organic matter. Trace element concentrations were determined by Inductively Coupled Plasma-Atomic Emission Spectrometry (ICP-AES) after each extraction step. With the used extraction procedure, it was possible to identify the fraction where some trace elements could be found in order to evaluate their bioavailability potential. Rb and Cs were particularly involved with the organic fraction, while Sr revealed to be associated mainly to the exchangeable fraction (clay minerals). Pb, Th and U were mainly bound to the residual and Fe-oxide fractions. (author)

  20. Development of a Mass Transfer Model and Its Application to the Behavior of the Cs, Sr, Ba, and Oxygen ions in an Electrolytic Reduction Process for SF

    International Nuclear Information System (INIS)

    Park, Byung Heung; Kang, Dae Seung; Seo, Chung Seok; Park, Seong Won

    2005-01-01

    Isotopes of alkali and alkaline earth metals (AM and AEM) are the main contributors to the heat load and the radiotoxicity of spent fuel (SF). These components are separated from the SF and dissolved in a molten LiCl in an electrolytic reduction process. A mass transfer model is developed to describe the diffusion behavior of Cs, Sr, and Ba in the SF into the molten salt. The model is an analytical solution of Fick's second law of diffusion for a cylinder which is the shape of a cathode in the electrolytic reduction process. And the model is also applied to depict the concentration profile of the oxygen ion which is produced by the electrolysis of Li 2 O. The regressed diffusion coefficients of the model correlating the experimentally measured data are evaluated to be greater in the order of Ba, Cs, and Sr for the metal ions and the diffusion of the oxygen ion is slower than the metal ions which implies that different mechanisms govern the diffusion of the metal ions and the oxygen ions in a molten LiCl.

  1. 137Cs and 90Sr mobility in soils and transfer in soil-plant systems in the Novozybkov district affected by the Chernobyl accident

    International Nuclear Information System (INIS)

    Korobova, E.; Ermakov, A.; Linnik, V.

    1998-01-01

    The Chernobyl radionuclides distribution and mobility in soils and uptake by plants have been studied in seminatural and agricultural moraine and in fluvioglacial landscapes typical for the areas of the Bryansk region affected by the accident.The major part of the Chernobyl 137 Cs accumulated in the topsoil is insoluble in water, 40 to 93% of this radionuclide is strongly fixed by soil, while 70 to 90% of the 90 Sr is present in water soluble, exchangeable and weak-acid soluble forms. Radionuclide vertical migration is most pronounced in local depressions with organic and gley soils in which both radionuclides are detected to the depth of 30-40 cm.In woodlands, most of the 137 grasses. Transfer to grasses in local depressions is usually higher compared with the dry levees. Observed exclusions are assumed to be due to comparatively low mobility of 137 Cs and relatively high K content in soil. 137 Cs accumulation in potato tubers grown on sandy soddy podzolic watershed soils mainly corresponds to its total amount in soils; uptake of 90 Sr depends upon the percentage of its most mobile fraction.Pronounced relief is proved to cause different patterns in distribution and migration of radionuclides in soils and local food chains. The study showed it to be true for private farms situated in different landscape positions within the same settlement.The forest litter, topsoil and products, and flood plain pastures, especially localities in depressions are critical materials for the long-term radioecological monitoring of the contaminated landscapes of the study area and those of similar conditions. Population of the areas within the zone of contamination exceeding 15Ci/km 2 (555kBq/m 2 ) should be recommended to exclude local forest products from their diets and to avoid cattle grazing on wet flood plain meadows without remediation. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

  2. Model testing of radioactive contamination by {sup 90}Sr, {sup 137}Cs and {sup 239,240}Pu of water and bottom sediments in the Techa River (Southern Urals, Russia)

    Energy Technology Data Exchange (ETDEWEB)

    Kryshev, I.I. [Scientific and Production Association ' Typhoon' , 82 Lenin Ave., Obninsk, Kaluga Region, 249038 (Russian Federation)], E-mail: ecomod@obninsk.com; Boyer, P.; Monte, L.; Brittain, J.E.; Dzyuba, N.N.; Krylov, A.L.; Kryshev, A.I.; Nosov, A.V.; Sanina, K.D.; Zheleznyak, M.I. [Scientific and Production Association ' Typhoon' , 82 Lenin Ave., Obninsk, Kaluga Region, 249038 (Russian Federation)

    2009-03-15

    This paper presents results of testing models for the radioactive contamination of river water and bottom sediments by {sup 90}Sr, {sup 137}Cs and {sup 239,240}Pu. The scenario for the model testing was based on data from the Techa River (Southern Urals, Russia), which was contaminated as a result of discharges of liquid radioactive waste into the river. The endpoints of the scenario were model predictions of the activity concentrations of {sup 90}Sr, {sup 137}Cs and {sup 239,240}Pu in water and bottom sediments along the Techa River in 1996. Calculations for the Techa scenario were performed by six participant teams from France (model CASTEAUR), Italy (model MARTE), Russia (models TRANSFER-2, CASSANDRA, GIDRO-W) and Ukraine (model RIVTOX), all using different models. As a whole, the radionuclide predictions for {sup 90}Sr in water for all considered models, {sup 137}Cs for MARTE and TRANSFER-2, and {sup 239,240}Pu for TRANSFER-2 and CASSANDRA can be considered sufficiently reliable, whereas the prediction for sediments should be considered cautiously. At the same time the CASTEAUR and RIVTOX models estimate the activity concentrations of {sup 137}Cs and {sup 239,240}Pu in water more reliably than in bottom sediments. The models MARTE ({sup 239,240}Pu) and CASSANDRA ({sup 137}Cs) evaluated the activity concentrations of radionuclides in sediments with about the same agreement with observations as for water. For {sup 90}Sr and {sup 137}Cs the agreement between empirical data and model predictions was good, but not for all the observations of {sup 239,240}Pu in the river water-bottom sediment system. The modelling of {sup 239,240}Pu distribution proved difficult because, in contrast to {sup 137}Cs and {sup 90}Sr, most of models have not been previously tested or validated for plutonium.

  3. Effects of {sup 137}Cs and {sup 90}Sr on structure and functional aspects of the microflora in agricultural used soils

    Energy Technology Data Exchange (ETDEWEB)

    Niedree, Bastian

    2013-11-01

    At long sight {sup 137}Cs and {sup 90}Sr are the main radionuclides responsible for the contamination of agricultural soils due to core melts in nuclear power plants such as Chernobyl or Fukushima. Once deposited on the soil surface, the two radionuclides remain in the upper soil layer for several decades. In the upper soil layer the highest microbial activity can be found, due to high organic matter contents, warm temperatures and gas exchange with the atmosphere. Hence, in contaminated soils microorganisms in upper soil layers (e.g. the plow layer on agricultural fields) are exceedingly exposed to radioactivity. However, no data are available how radioactive contaminations with {sup 137}Cs or {sup 90}Sr in a realistic order of magnitude affect the microbial community and its functions in soils. This dissertation discusses the effects of radioactive contaminations on the microbial community structure and some of its functions in soils. Therefore, typical agricultural soils, an Orthic Luvisol from field site Merzenhausen and a Gleyic Cambisol from field site Kaldenkirchen-Huelst were artificially contaminated with various concentrations of {sup 137}Cs and {sup 90}Sr and partly applied with radiolabeled substrates and incubated in soil microcosms under controlled laboratory conditions. The lower radionuclide concentrations corresponded to the contaminations in the Chernobyl exclusion zone, the higher concentrations were up to 50-fold that of the maximum occurring hotspots ({sup 137}Cs) in this zone. In three experiments the effects of the ionizing radiation on the bacterial and the fungal community structure (16S and 18S rDNA DGGE), the degradation of {sup 14}C-labeled wheat straw or uniformly ring-labeled 2,4-dichlorophenoxyacetic acid, the development of the fungal biomass (ergosterol quantification) and the chemical composition of the soil organic matter ({sup 13}C CP/MAS NMR) were investigated. In half of the microcosms the soils were autoclaved and reinoculated

  4. Soil-water distribution coefficients and plant transfer factors for {sup 134}Cs, {sup 85}Sr and {sup 65}Zn under field conditions in tropical Australia

    Energy Technology Data Exchange (ETDEWEB)

    Twining, J.R. E-mail: jrt@ansto.gov.au; Payne, T.E.; Itakura, T

    2004-07-01

    Measurements of soil-to-plant transfer of {sup 134}Cs, {sup 85}Sr and {sup 65}Zn from two tropical red earth soils ('Blain' and 'Tippera') to sorghum and mung crops have been undertaken in the north of Australia. The aim of the study was to identify factors that control bioaccumulation of these radionuclides in tropical regions, for which few previous data are available. Batch sorption experiments were conducted to determine the distribution coefficient (K{sub d}) of the selected radionuclides at pH values similar to natural pH values, which ranged from about 5.5 to 6.7. In addition, K{sub d} values were obtained at one pH unit above and below the soil-water equilibrium pH values to determine the effect of pH. The adsorption of Cs showed no pH dependence, but the K{sub d} values for the Tippera soils (2300-4100 ml/g) exceeded those for the Blain soils (800-1200 ml/g) at equilibrium pH. This was related to the greater clay content of the Tippera soil. Both Sr and Zn were more strongly adsorbed at higher pH values, but the K{sub d} values showed less dependence on the soil type. Strontium K{sub d}s were 30-60 ml/g whilst Zn ranged from 160 to 1630 ml/g for the two soils at equilibrium pH. With the possible exception of Sr, there was no evidence for downward movement of radionuclides through the soils during the course of the growing season. There was some evidence of surface movement of labelled soil particles. Soil-to-plant transfer factors varied slightly between the soils. The average results for sorghum were 0.1-0.3 g/g for Cs, 0.4-0.8 g/g for Sr and 18-26 g/g for Zn (dry weight) with the initial values relating to Blain and the following values to Tippera. Similar values were observed for the mung bean samples. The transfer factors for Cs and Sr were not substantially different from the typical values observed in temperate studies. However, Zn transfer factors for plants grown on both these tropical soils were greater than for soils in

  5. Simulations of the Thermodynamic and Diffusion Properties of Actinide Oxide Fuel Materials

    International Nuclear Information System (INIS)

    Becker, Udo

    2013-01-01

    Spent nuclear fuel from commercial reactors is comprised of 95-99 percent UO 2 and 1-5 percent fission products and transuranic elements. Certain actinides and fission products are of particular interest in terms of fuel stability, which affects reprocessing and waste materials. The transuranics found in spent nuclear fuels are Np, Pu, Am, and Cm, some of which have long half- lives (e.g., 2.1 million years for 237 Np). These actinides can be separated and recycled into new fuel matrices, thereby reducing the nuclear waste inventory. Oxides of these actinides are isostructural with UO 2 , and are expected to form solid solutions. This project will use computational techniques to conduct a comprehensive study on thermodynamic properties of actinide-oxide solid solutions. The goals of this project are to: Determine the temperature-dependent mixing properties of actinide-oxide fuels; Validate computational methods by comparing results with experimental results; Expand research scope to complex (ternary and quaternary) mixed actinide oxide fuels. After deriving phase diagrams and the stability of solid solutions as a function of temperature and pressure, the project team will determine whether potential phase separations or ordered phases can actually occur by studying diffusion of cations and the kinetics of potential phase separations or ordered phases. In addition, the team will investigate the diffusion of fission product gases that can also have a significant influence on fuel stability. Once the system has been established for binary solid solutions of Th, U, Np, and Pu oxides, the methodology can be quickly applied to new compositions that apply to ternaries and quaternaries, higher actinides (Am, Cm), burnable poisons (B, Gd, Hf), and fission products (Cs, Sr, Tc) to improve reactivity

  6. Prediction of 137Cs and 90Sr accumulation in milk of horses and sheep grazing the area adjacent to the 'Experimental Field' technical area of the Semipalatinsk test site

    International Nuclear Information System (INIS)

    Gontarenko, I.A.; Spiridonov, S.I.; Mukusheva, M.K.

    2005-01-01

    The paper describes mathematical models for 137 Cs and 90 Sr behavior in body of horses and sheep grazing the area adjacent to the 'Experimental Field' Technical Area of the Semipalatinsk test site. The models were parametrized on the basis of experimental data for those breeds of animals that are currently encountered within the Semipalatinsk test area. The predictive conclusions using devised models have shown that 137 Cs and 90 Sr concentration in milk of horses and sheep grazing the Experimental field are can exceed the adopted standards during a long period of time. (author)

  7. Evaluation of 137Cs and 90Sr effect on the industrial and medical X-ray films for autoradiography using the OSIRIS software

    International Nuclear Information System (INIS)

    Dabbagh, R.; Ghafourian, H.; Baghvand, A.; Nabi, G.R.; Riahi, H.

    2006-01-01

    Autoradiography is one of the techniques developed for screening and isolating suitable radionuclide bioaccumulator microorganisms such as cyanobacteria, algae and bacteria. In this research autoradiography is developed for a kind of industrial film and a medical X-ray film. Irradiation time estimation according to radiotracer activity and suitable film selection are the most important aims in this research. These parameters are estimated for 137 Cs and 90 Sr on the basis of the appearances of the dark black spots on the developed films. Selected film and estimated irradiation time could be used to screen the needed microorganisms in the laboratory studies. The micro-organisms isolated by this method could be used to remove radioactive pollution in environmental engineering

  8. Comparison of Radioecological Processes on Examples of Villages Polluted by 137Cs and 90Sr Appreciated on the Box Model Method

    International Nuclear Information System (INIS)

    Matvjejeva, I.V.; Kutlakhmedov, Yu.O.; Isajenko, V.M.; Krivorot'ko, V.M.

    2006-01-01

    Results of the analysis of 137 Cs radionuclides flows as an example of village Galusia of the Volyn region and in ecosystem of village Kotsubinchiki in Ternopil region polluted by 90 Sr are considered. The analysis is made by the method of box models. The block diagrams of ecosystems were created, and the mathematical models by the method of box models are developed. It has allowed estimating ways of formation doses of an internal irradiation at the expense of products of meal for different groups of population - working people, pensioners and children, and prognosis dynamics of these doses for the next years after Chornobyl NPP accident. It was established, that doses in these villages formed by other ways, depending on radionuclide, pastures structure and levels of their pollution

  9. Identification of the neutron-rich nuclides /sup 147; 148/Ba and half- life determination of the heavy isotopes of Rb, Sr, Y, Cs, Ba and La

    CERN Document Server

    Amiel, S; Nir-El, Y; Shmid, M

    1976-01-01

    The neutron nuclides /sup 147; 148/Ba were produced in the thermal neutron induced fission of /sup 235/U. A new surface ionization integrated target ion source operating at temperatures in the region of 1800 degrees C permits the measurement of half-lives of isotopes down to about 0.1 sec due to the very fast release of atoms from the target. Isotopes of Rb, Sr, Cs, and Ba were separated by positive surface ionization and their half-lives measured using beta activity detected by a silicon surface barrier detector with a depletion depth of 300 mu . The isotopes /sup 147/Ba and /sup 148/Ba were identified for the first time and their half-lives were found to be 0.72+or-0.07 sec and 0.47+or-0.20 sec, respectively. (0 refs).

  10. The development of models for the transfer of 137Cs and 90Sr in the pasture-cow-milk pathway using fallout data

    International Nuclear Information System (INIS)

    Haywood, S.M.; Simmonds, J.R.; Linsley, G.S.

    1980-11-01

    Records of the measurements of fallout in the UK between the years 1958-77 have been used to develop versions of a general model for transfer in the pasture-cow-milk pathway for the radionuclides 137 Cs and 90 Sr. The revised models take account of the experimentally observed processes of fixation of caesium in soils and the plant base absorption of strontium. They predict, with reasonable accuracy, the variation of activity levels in milk over the period for which records exist. The form of the models permits examination of the relative contributions of the most important transfer mechanisms and their time dependence in the soil-plant system. The study has indicated an upper limit for the resuspension factor in UK rural environments. (author)

  11. A study of nuclear structure for 244Cm, 241Am, 238Pu, 210Po, 147Pm, 137Cs, 90Sr and 63Ni nuclei used in nuclear battery

    Science.gov (United States)

    Artun, Ozan

    2017-07-01

    In this paper, we intend to extend the nuclear data of 244Cm, 241Am, 238Pu, 210Po, 147Pm, 137Cs, 90Sr and 63Ni nuclei used in nuclear battery technology, because, these nuclei are quite important for space investigations in radioisotope thermoelectric generator (RTG) and for microelectronic technologies in betavoltaic batteries. Therefore, the nuclear structure properties of nuclei such as separation energies, neutron skin thicknesses, proton, charge and neutron density distributions as a function of radius, the root mean square (rms) proton, charge and neutron radii, binding energies per particle, have been investigated by Hartree-Fock with eight different Skyrme forces. The obtained results have been compared with the experimental data in literature and relativistic mean field theory (RMFT) results.

  12. Determinations of 90Sr, 137Cs, 226Ra, 228Ra, 210Pb, 210Po contents in chinese diet and estimations of internal doses due to these radionuclides

    International Nuclear Information System (INIS)

    Zhu Hongda; Wang Shouliang; Meng Wei; Wang Daoping; Zheng Xiujun; Liu Qingfen; Liu Peng

    1993-01-01

    As a part of Chinese Total Diet Survey taken place in 1990, the authors report the determined results on 90 Sr, 137 Cs, 226 Ra, 228 Ra, 210 Pb and 210 Pb and 210 Po contents in various foods of Chinese total diet. Based on obtained dietary composition and the determined contents, the Annual Intakes (AI) and Committed Dose Equivalents (CDE) for the public by ingestion were estimated. It is shown that the total CDE for 6 radionuclides is about 0.24 mSv/a. The food categories and nuclides whose relative contributions to the total are dominant were vegetables, aquatic products and cereal, and 210 Pb, 210 Po, 228 Ra, respectively. The results have updated the data from 1982 survey and have complemented important information for water consumption. The regional difference of dietary compositions and resultant internal doses are discussed as well

  13. Activity concentration measurements of 137Cs, 90Sr and 40K in a wild food matrix reference material (Wild Berries) CCRI(II)-S8

    International Nuclear Information System (INIS)

    Watjen, U.; Altzitzogloa, T.; Spasova, Y.; Ceccatelli, A.; Kis-Benedek, G.; Dikmen, H.; Gundogdu, G.; Yucel, U.; Ferreux, L.; Frechou, C.; Pierre, S.; Garcia, L.; Moreno, Y.; Oropesa, P.; La Rosa, J.; Luca, A.; Schmiedel, M.; Wershofen, H.; Szucs, L.; Vasile, M.

    2014-01-01

    In 2009, the CCRI approved a supplementary comparison to be organized by the IRMM as pilot laboratory for the activity concentrations of 137 Cs, 90 Sr and 40 K in a matrix material of dried bilberries. The organization of this comparison and the material and measurement methods used are described. The supplementary comparison reference values (SCRV) for each of the three radionuclides are given together with the degrees of equivalence of each participating laboratory with the SCRV for the specific radionuclide. The results of this supplementary comparison allow the participating NMIs/designated institutes to declare calibration and measurement capabilities (CMCs) for the given radionuclides in a similar type of food matrix, an important aspect given the relatively few supplementary comparisons for activity in matrix materials organized so far. (authors)

  14. Radioactive tracer studies of soil and litter arthropod food chains. Progress report, November 1, 1975--October 31, 1976. [/sup 134/Cs, /sup 85/Sr

    Energy Technology Data Exchange (ETDEWEB)

    Crossley, D.A. Jr.

    1976-07-31

    Progress is described in radioisotope measurement of nutrient element flow in soil-litter arthropod food chains. Two models of accumulation (Goldstein-Elwood, Reichle-Crossley) were tested experimentally and found to yield equivalent predictions of /sup 134/Cs and /sup 85/Sr movement through arthropod populations. Radioisotope retention studies were used to compare trophic strategies of soil tipulids from arctic tundra and temperate forest. Arctic tipulids were found to compensate for low temperatures with enhanced assimilation and slower turnover of nutrients. Electron microprobe analysis is being used to measure elemental content of soil microarthropods. Concentrations as high as 70,000 ppm of Ca are reported for oribatid mites. Improved measurements of input-output nutrient concentrations are reported for island ecosystems on granitic outcrops, which are being subjected to experimental alteration in studies of ecosystem function.

  15. Results of study of Sr-90 and Cs-137 content in organism and effective doses of internal and external irradiation of Ukrainian population residing in different regions

    International Nuclear Information System (INIS)

    Kalmykov, L.; Gur, E.

    1996-01-01

    The authors have studied effective doses of internal and external radiation for 1992-1994 in the residents of Chernigov and Kharkov Regions of Ukraine, i.e. those who live in the zone of strict radioecologic control and in relatively ''clean'' zones, respectively. In 95% of the investigated residents of Chernigov Region Cs-137 activity in the organism was lower than 1500 Bq, maximum amount being 11 kBq. Conditioned Cs-137 effective dose of internal radiation did not exceed 250 micro Sv per year, in 96% of the investigated subjects it was less than 30 micro Sv per year. Mean amount of this radionuclide in the organisms of both adults and children aged 3-6 years residing in Kharkov Region was 90 and 6 Bq respectively, dose being 2 and 0.4 micro Sv per year. Sr-90 amount in the bone tissue decreases with the age and for the residents of Chernigov region it was 7-23 Bq/kg of bone, for the adult residents of Kharkov region it was about 3 Bq/kg of bone. Mean effective dose of internal radiation due to Sr-90 incorporation for the residents of both Kharkov and Chernigov Regions was 0.7 and 1.9 micro Sv per year. Effective dose of external radiation for the residents of Kharkov Region has not changed since the Chernobyl accident. Total effective dose of external and internal radiation in various professional groups for the residents of Chernigov region increased by 80 micro Sv per year which makes up 14% of mean population dose in Ukraine. (author). 11 refs, 5 tabs

  16. Foliar contamination of plants with aerosols of 137Cs, 85Sr, 133Ba and 123mTe: influence of rain

    International Nuclear Information System (INIS)

    Madoz-Escande, C.; Bonhomme, T.; Poncet-Bonnard, D.

    2004-01-01

    Different types of plants (lettuce, radish and grass sward) were contaminated by dry deposition of radioactive aerosols ( 137 Cs, 85 Sr, 133 Ba and 123m Te). Due to the rain efficiency in decreasing radiological contamination of crops, a range of rain scenarios was applied on these three types of plants. These experiments aimed at improving the prediction of the consequences on agricultural products of a nuclear accident occurring on a PWR, and also at improving the understanding of the different processes occurring between the contamination and the first harvest. For a plant species at a given stage of its growth cycle, interception of the four radionuclides was identical and varied from 68% for radish to 84% for grass. The interception of aerosols by lettuce was intermediary with 75% (at the middle of ripeness stage) or 78%(at the mature plant stage). By the use of a conceptual model, the predominance between the two processes: washing-off the leaves and absorption through the leaves cuticles that allows the translocation, was evidenced. For Cs, Sr and Ba,, for the lettuce and the radish the washing-off process on the foliar cover of lettuce and radish was the most significant during the first rain. The absorption process inside the plant became dominant only from the third rain event. Tellurium had a particular behaviour: it was non-mobile and stayed put on the leaves. The values of the washing-off and absorption coefficients were estimated. For the grass, during the washing-off, radionuclides had a tendency to accumulate in the basal parts of plant first and the root matt later. Moreover, grass cuts came in between the rains. The global transfer factor values were dependant on both the radionuclides and the plant species, nevertheless the higher value was obtained for the cesium, whatever the plant and the rain (from 0,06 m 2 .kg fresh -1 for radish to 0,1 m 2 .kg fresh -1 for whole lettuce). (author)

  17. 40K, 137Cs, 90Sr, 238,239+240Pu and 241Am in mammals' skulls from owls' pellets and owl skeletons in Poland.

    Science.gov (United States)

    Gaca, Paweł; Mietelski, Jerzy W; Kitowski, Ignacy; Grabowska, Sylwia; Tomankiewicz, Ewa

    2005-01-01

    Skulls of small mammals belonging to two species of rodents and three species of insectivores collected in Eastern Poland were the subject of the present investigation. The skulls were separated from owl pellets. Activities of 40K, 137Cs, 90Sr, 238,239+240Pu and 241Am were determined by means of gamma spectrometry as well as liquid scintillation spectrometry or alpha spectrometry along with relevant radiochemical procedures. A detailed description of the procedures is provided. The research was supplied with the analysis of three skeletons of owls. No measurable difference between the skulls of rodents and insectivorous animals with regard to activity of any of the examined radionuclides was found. No accumulation effect in the owl skeletons was detected. Though measured activities of 137Cs and 40K for the skulls were of the same magnitude as those found previously for large wild herbivorous animals from typical locations in Poland, those for 90Sr were even lower than previously determined. A big difference was found for activities of plutonium and americium isotopes. Their mean activities were higher by an order of magnitude when compared to the examined previously values. The maximum 239+240Pu activity was equal to 97.5+/-7.7 mBq/kg, with 65% of it originating from global fallout. Relatively high content of transuranic elements found for rodents and insectivorous mammals seems to be unrelated to their feeding habits and should rather be attributed to the living conditions. It is suggested that small mammals, together with tiny soil particles present in mid-soil living tunnels, can inhale the transuranic elements.

  18. Modeling the washoff of 90Sr and 137Cs from an experimental plot established in the vicinity of the Chernobyl reactor

    International Nuclear Information System (INIS)

    Nair, S.K.; Hoffman, F.O.; Thiessen, K.M.; Konoplev, A.V.

    1996-01-01

    After the Chernobyl event, a large area of land was contaminated following the deposition of radionuclides. This area became a continuing source of radionuclides to natural waters and aquatic ecosystems. In 1986, an experimental plot was constructed in a contaminated area near the Chernobyl Nuclear Power Plant to study the washoff of radionuclides by surface runoff. Concentrations of 137 Cs and 90 Sr were measured in the top 10 cm of the soil prior to the experiments. During two separate experiments, intense artificial rainfall was applied to the plot. A washoff scenario was prepared with site-specific information on initial soil contamination, duration and quantities of rainfall and runoff, physicochemical properties of the topsoil, and some climatological data. Modelers were asked to predict (a) the vertical distributions of the initial concentrations of 137 Cs and 90 Sr in various chemical forms in the topsoil, (b) concentrations of these radionuclides in various chemical forms in the runoff water during each experiment, and (c) the total amounts of these radionuclides in various chemical forms in the runoff water during each experiment, and (c) the total amounts of these radionuclides that were washed off during each experiment. A vertical, one-dimensional, multiphase, multispecies transport model was then developed to simulate the movement of contaminants in the topsoil during the 160-d period between the Chernobyl event and the experiments as well as the washouts of contaminants by runoff during the experiments and during the 24-h period thereafter. The model provided very good predictions of the vertical distributions of total contaminant concentrations in the top 10 cm of the soil; however, the concentrations in individual chemical forms were not predicted as accurately. The complete modeling approach and comparisons of model predictions with measurements and with predictions from other modelers are presented. 19 refs., 22 figs., 8 tabs

  19. Report on Three IAEA Intercomparisons: 1) Determination of Potassium and Cs-137 in Animal Blood Serum (A-1); 2) Determination of Sr-90 and Ra-226 in Animal Bone Ash (A-3); 3) Determination of Sr-90, Cs-137, Na, K, Cs, Ca, Sr and Ba in Milk Powder (A-7)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1973-12-01

    The samples were made from fresh animal blood by separating the blood particles from the serum, stirring and subsequent spray drying. No spiking with active or inactive materials was made. Each participating laboratory received a 500 g sub-sample of the material. In the case of {sup 137}Cs-analysis, two of the laboratories submitted two different sets of results which were obtained by different analytical methods. Results were presented in separate tables for both elements.

  20. Mid-year status report for TTP number-sign SR-1320-02 UST: Cs extraction testing

    International Nuclear Information System (INIS)

    Bibler, J.P.

    1993-01-01

    This project was designed to perform several tasks to provide transfer of technology to PNL concerning optimization of a cesium-specific ion exchange resin, developed at WSRC. The tasks support the development of a Compact Processing Unit (CPU) for Cs-removal from a variety of waste streams at Westinghouse Hanford (WH). In a series of experiments, WSRC has studied the behavior of a small column of the resin at various, increasingly greater flow rates with the HW simulant solution to determine an optimum column loading rate. Elution studies of the resin after saturation with Cs+ will generate an elution profile from which an optimum elution medium, flow rate, and volume can be determined. Small column tests at temperatures ranging from 40 degrees C 80 degrees C are planned but have not yet begun. Further, WSRC has begun a study in which the resin is subjected to ionizing radiation in a Co-60 source. This study will determine if any flammable or hazardous compounds, that might require special process controls, are formed as a result of irradiation. it will also define the ability of the resin to maintain its selectivity and capacity in a radiation field. During this period, a literature survey of the effects of radiation on this type of resin and similar compounds was initiated. For this survey, the extensive database established by the Radiation Chemistry Data Center at the University of Notre Dame is being used

  1. Actinide recycle

    Energy Technology Data Exchange (ETDEWEB)

    Till, C; Chang, Y [Argonne National Laboratory, Argonne, IL (United States)

    1990-07-01

    A multitude of studies and assessments of actinide partitioning and transmutation were carried out in the late 1970s and early 1980s. Probably the most comprehensive of these was a study coordinated by Oak Ridge National Laboratory. The conclusions of this study were that only rather weak economic and safety incentives existed for partitioning and transmuting the actinides for waste management purposes, due to the facts that (1) partitioning processes were complicated and expensive, and (2) the geologic repository was assumed to contain actinides for hundreds of thousands of years. Much has changed in the few years since then. A variety of developments now combine to warrant a renewed assessment of the actinide recycle. First of all, it has become increasingly difficult to provide to all parties the necessary assurance that the repository will contain essentially all radioactive materials until they have decayed. Assurance can almost certainly be provided to regulatory agencies by sound technical arguments, but it is difficult to convince the general public that the behavior of wastes stored in the ground can be modeled and predicted for even a few thousand years. From this point of view alone there would seem to be a clear benefit in reducing the long-term toxicity of the high-level wastes placed in the repository.

  2. Actinide recycle

    International Nuclear Information System (INIS)

    Till, C.; Chang, Y.

    1990-01-01

    A multitude of studies and assessments of actinide partitioning and transmutation were carried out in the late 1970s and early 1980s. Probably the most comprehensive of these was a study coordinated by Oak Ridge National Laboratory. The conclusions of this study were that only rather weak economic and safety incentives existed for partitioning and transmuting the actinides for waste management purposes, due to the facts that (1) partitioning processes were complicated and expensive, and (2) the geologic repository was assumed to contain actinides for hundreds of thousands of years. Much has changed in the few years since then. A variety of developments now combine to warrant a renewed assessment of the actinide recycle. First of all, it has become increasingly difficult to provide to all parties the necessary assurance that the repository will contain essentially all radioactive materials until they have decayed. Assurance can almost certainly be provided to regulatory agencies by sound technical arguments, but it is difficult to convince the general public that the behavior of wastes stored in the ground can be modeled and predicted for even a few thousand years. From this point of view alone there would seem to be a clear benefit in reducing the long-term toxicity of the high-level wastes placed in the repository

  3. Laboratory Optimization Tests of Decontamination of Cs, Sr, and Actinides from Hanford Waste Treatment Plant Low Activity Waste Off-Gas Condensate Simulant

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Nash, C. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); McCabe, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-01-06

    The Hanford Waste Treatment and Immobilization Plant (WTP) Low Activity Waste (LAW) vitrification facility will generate an aqueous condensate recycle stream (LAW Off-Gas Condensate) from the off-gas system. The baseline plan for disposition of this stream is to send it to the WTP Pretreatment Facility, where it will be blended with LAW, concentrated by evaporation and recycled to the LAW vitrification facility. Alternate disposition of this stream would eliminate recycling of problematic components, and would enable less integrated operation of the LAW melter and the Pretreatment Facilities. Eliminating this stream from recycling within WTP would also substantially decrease the LAW vitrification mission duration and quantity of glass waste.

  4. {sup 137}Cs, {sup 90}Sr, {sup 241}Am and {sup 239+240}Pu radionuclides speciation in soils of the former Semipalatinsk test site

    Energy Technology Data Exchange (ETDEWEB)

    Kabdyrakova, A.M.; Kunduzbaeva, A.Y.; Lukashenko, S.N.; Magasheva, R.Y. [Institute of radiation safety and ecology (Kazakhstan)

    2014-07-01

    The paper presents results of studies into {sup 137}Cs and {sup 90}Sr, {sup 241}Am and {sup 239+240}Pu techno-genic radionuclides speciation in soils of ecosystems at different topography of the Semipalatinsk Test Site (STS), exposed to different nuclear testing. The data were obtained for radionuclides speciation in soils of the following STS ecosystems: - grassland ecosystems within near-portal areas of tunnels - horizontal adits constructed for nuclear testing, affected by radioactive-contaminated water flows from the tunnels of Degelen Site; - steppe ecosystems, exposed to ground radioactive contamination resulted from above-ground and aerial nuclear testing of different yield, as well as simulation (hydrodynamic and hydro-nuclear) experiments at 'Experimental Field' testing site. - steppe ecosystems, exposed to ground radioactive contamination caused by testing of liquid and powdery radiological warfare weapon (RWW) at Site '4 a'; - 'Northern' and 'Western' areas of STS, where concentration level of artificial radionuclides in soil is comparable with the level of global fall-outs ('background' areas). To study the radionuclides speciation, method of sequential extraction was applied, and water-soluble, exchange, organic mobile and tightly bound forms were separated. Feature of the studied grassland ecosystems is that they are developed solely along the bed of water streams flowing from tunnels and are located at small area of 1-2 m{sup 2}. Radioactive contamination of soil is caused by radioactive contaminant sorption by sediments. Despite the significant space limitation of the ecosystems content of radionuclides speciation in soil greatly varies, particularly readily-soluble and mobile forms. The variation may be explained by high humidity which makes possible both sorption and desorption processes. If basic radionuclides contributing to radioactive contamination of grassland soils at Degelen Site are {sup

  5. Modeling the washoff of 90Sr and 137Cs from an experimental plot established in the vicinity of the Chernobyl reactor.

    Science.gov (United States)

    Nair, S K; Hoffman, F O; Thiessen, K M; Konoplev, A V

    1996-12-01

    After the Chernobyl event, a large area of land was contaminated following the deposition of radionuclides. This area became a continuing source of radionuclides to natural waters and aquatic ecosystems. In 1986, an experimental plot was constructed in a contaminated area near the Chernobyl Nuclear Power Plant to study the washoff of radionuclides by surface runoff. Concentrations of 137Cs and 90Sr were measured in the top 10 cm of the soil prior to the experiments. During two separate experiments, intense artificial rainfall was applied to the plot. A washoff scenario was then prepared with site-specific information on initial soil contamination, duration and quantities of rainfall and runoff, physicochemical properties of the topsoil, and some climatological data. Modelers were asked to predict (a) the vertical distributions of the initial concentrations of 137Cs and 90Sr in various chemical forms in the topsoil, (b) concentrations of these radionuclides in various chemical forms in the runoff water during each experiment, and (c) the total amounts of these radionuclides that were washed off during each experiment. Stochastically generated local rainfall data were used in a water budget model to generate annual average runoff and infiltration rates. A vertical, one-dimensional, multiphase, multispecies transport model was then developed to simulate the movement of contaminants in the topsoil during the 160-d period between the Chernobyl event and the experiments as well as the washouts of contaminants by runoff during the experiments and during the 24-h period thereafter. The model provided very good predictions of the vertical distributions of total contaminant concentrations in the top 10 cm of the soil; however, the concentrations in individual chemical forms were not predicted as accurately. Initially, the model overpredicted the washout of contaminants for the two experiments and the 24-h period thereafter. Fraction of runoff that flows as interflow and

  6. The actinides

    International Nuclear Information System (INIS)

    Bagnall, K.W.

    1987-01-01

    This chapter of coordination compound chemistry is devoted to the actinides and starts with a general survey. Most of the chapter relates to thorium and uranium but protactinium, neptunium and plutonium are included. There are sections on nitrogen, phosphorus, sulfur, selenium, tellurium and halogen ligands of the metals in their +3, +4, +5 and +6 oxidation states and of the transplutonium elements in their +2, +3, +4, and +5 oxidation states. (UK)

  7. Coefficients of leaf-fruit translocation for {sup 60}Co, {sup 90}Sr and {sup 137}Cs in bean plant (Phaseolus vulgaris); Coeficientes de translocacao folha-fruto de {sup 60}Co, {sup 90}Sr e {sup 137}Cs em feijoeiro (Phaseolus vulgaris)

    Energy Technology Data Exchange (ETDEWEB)

    Macacini, Jose Flavio

    2000-01-15

    Due to the increasing use of nuclear fission for the generation of electrical energy, the safety aspects of power plants must be minutely appraised. In case of an accident, with liberation of radioactive material into the atmosphere, knowledge about the behavior of plant species when in contact with radionuclides is indispensable. An important route through which agricultural products are contaminated by radionuclides is leaf-fruit translocation. This phenomenon can be evaluated by simulating a fallout contamination in a controlled atmosphere using as a tracer man-made radionuclides. In order to quantity the leaf-fruit translocation coefficients for {sup 60}Co, {sup 90}Sr and {sup 137}Cs in the common bean (Phaseolus vulgaris), variety black diamond, an experiment was carried out in a greenhouse with completely randomized blocks design with six treatments and four blocks. A mixture of these three radionuclides was prepared and used to determine their translocation coefficients. The bean plants were contaminated inside a device especially designed to avoid environmental contamination. In each treatment four vases were sprinkled and one was used to estimate the initial activity of the other three vases. High-resolution gamma-ray spectrometry was used for {sup 60}Co and {sup 137}Cs activity determinations and chemical separation followed by beta counting of {sup 90}Y was used for {sup 90}Sr determinations. The number of treatments was reduced from six to four sprayings corresponding to 30, 45, 60 and 75 days after planting. This reduction was due to the attack of common and gold mosaic viroses. Symptoms were observed on the diseased bean plants 50 days after planting. It was possible, however, to verify a functional dependence between instant of tracer application and the level of physiological development of the bean plant. It was verified that the temporal relationship values for leaf-fruit translocation were similar for {sup 60}Co and {sup 137}Cs. For the {sup 90

  8. Rapid actinide analysis method coupling liquid chromatography/ICP-MS and "9"0Sr gas proportional counter in post-accidental situation environmental samples

    International Nuclear Information System (INIS)

    Habibi, Azza

    2015-01-01

    The present study follows the Fukushima power plant accident and aimed to develop an analytical method to achieve, during an emergency situation, a rapid identification and quantification of alpha and beta emitters in environmental samples. The first step of this study allowed us to list the alpha and beta emitters which can be released in the environment in case of a nuclear accident. The second step aimed towards the development of a rapid analysis method to quantify 17 radionuclides of U, Th, Pu, Am, Np and Sr. The main objective was the automation of the radiochemical separation step and its coupling for the measurement. The separation is performed using columns containing extraction resins, namely TEVA, TRU and Sr. The measurement is performed using an ICP-MS (inductively coupled plasma mass spectrometry) and in some cases a gas proportional counter to quantify radiostrontium ("8"9Sr and "9"0Sr). Excellent figures of merit were obtained, off line, with water (tap, river and sea water) and solid matrices (soil and aerosol filters), after a micro-wave digestion or an alkaline fusion dissolution followed by a Ca_3(PO_4)_2 coprecipitation. The proposed analytical strategy showed yields between 70 % and 100 % and standard deviations between 5 % and 10 %. The newly developed separation method was then automated and coupled on-line to ICP-MS. The operating parameters were optimized using a design of experiments and the results were processed with Minitab. The optimized automated separation coupled on-line to the ICP-MS allows the rapid quantification, in 1.5 h per sample, of U, Th, Pu, Am, Np and Sr with detection limits gain as high as 20 times for artificial radionuclide. (author)

  9. Evaluation of improved technologies for the removal of 90Sr and 137Cs from process wastewater and groundwater: FY 1995 status

    International Nuclear Information System (INIS)

    Bostick, D.T.; Arnold, W.D. Jr.; Burgess, M.W.; McTaggart, D.R.; Taylor, P.A.; Guo, B.

    1996-03-01

    A number of new sorbents are currently being developed for the removal of 90 Sr and 137 Cs from contaminated, caustic low-level liquid waste (LLLW). These sorbents are potentially promising for use in the cleanup of contaminated groundwater and process wastewater containing the two radionuclides. The goal of this subtask is to evaluate the new sorbents to determine whether their associated treatment technology is more selective for the decontamination of wastewater streams than that of currently available processes. Activities during fiscal year 1995 have included completing the characterization of the standard treatment technology, ion exchange on chabazite zeolite. Strontium and cesium sorption on sodium-modified zeolite was observed in the presence of elevated concentrations of wastewater components: sodium, potassium, magnesium, and calcium. The most significant loss of nuclide sorption was noted in the first 0- to 4-meq/L addition of the cations to a wastewater simulant. Radionuclide sorption on the pretreated zeolite was also determined under dynamic flow conditions. Resorcinol-formaldehyde (R-F) resin, which was developed at the Savannah River Site, was selected as the first new sorbent to be evaluated for wastewater treatment. Nuclide sorption on this resin was greater when the resin had been washed with ultrapure water and air dried prior to use

  10. Transfer of some artificial (226Sr and 137Cs) and natural (40K and 226Ra) radionuclides from milk to its products

    International Nuclear Information System (INIS)

    Al-Masri, M. S.; Nashawati, A.; Amin, Y.; Al-Akel, B.

    2005-01-01

    Transfer of some artificial radionuclides ( 137 Cs and 85 Sr) and natural radionuclides ( 226 Ra and 40 K) from milk (cheep and cows) to its products processed according to local manufacturing procedures (home made cheese, kashkawan cheese, shelal cheese, haloom cheese, kareshah cheese, sharkasiah cheese, liquid cheese, yogurt, butter and keshdah) has been studied. The results showed that the retention percent of radium 226 in milk products has reached %100 in the home made cheese and %72 for strontium 85 in the shelal cheese and %40 for cesium 137 in yogurt and %46 for potassium 40 also in yogurt. In addition, most of the retention percent ratios of the studied radionuclides in yogurt were relatively low (about %25 and % 40 in the yogurt processed from the milk of the cows and cheep respectively) with a high processing efficiency, so that making yogurt from the contaminated milk is the best way to reduce the contamination ratio and to make use of the contaminated milk. Furthermore, home made cheese was processed with salty solutions of different concentrations and the results showed that about %90 of cesium and potassium has transferred to the salty solution of %5 soaked for 48 hours, while %40 of the radium and %80 of strontium were removed from the contaminated cheese after 48 hours soaking in a salty solution of %2.5. However, the results of the present work can be used for processing of contaminated milk with artificial radionuclides in order to be utilized. (Authors)

  11. Environmental studies on radioecological sensitivity and variability with special emphasis on the fallout nuclides 90Sr and 137Cs. Pt. 1

    International Nuclear Information System (INIS)

    Aarkrog, A.

    1979-06-01

    Radioecological sensitivity and variability are quantities that are used to characterize the radioecological properties of environmental samples. The radioecological sensitivity is the infinite time-integrated radionuclide concentration in the environmental sample considered arising from a deposition of 1 mCi KM -2 of the radionuclide in question. This quantity makes it possible to compare various environments as to their vulnerability to a given radioactive contamination. The variability of the concentrations of a radionuclide in an environmental sample, with respect to a given parameter, is defined as the partial coefficient of variation due to this parameter. The variability with time is a useful way to assess the route of contamination of the sample and the local variability is a measure of environmental inhomogenity with respect to radioactive contamination. Radioecology sensitivity and variability were applied to the 90 Sr and 137 Cs data obtained from the environmental studies on the human foodchain carried out during the last two decades in Denmark, the Faroe Islands, and Greenland. The per caput effective dose-equivalent commitments from radioactive debris from nuclear weapons testing was estimated to be 1.6 mSv in Denmark, 4.2 mSv in the Faroe Islands, and 1.6 mSv in Greenland. (author)

  12. Report on intercomparison IAEA/SOIL-6 of the determination of Cs-137, Pu-239, Ra-226, and Sr-90 in soil

    International Nuclear Information System (INIS)

    Pszonicki, L.; Hanna, A.N.; Suschny, O.

    1984-04-01

    The report presents results of a laboratory intercomparison of the determination of the activity level of cesium-137, plutonium-239, radium-226 and strontium-90 in a provided soil sample organized by the IAEA's Analytical Quality Control Service. Twenty-seven laboratories from 16 countries returned results based on 77 laboratory means (295 individual determinations). The aim of the interlaboratory comparison was to offer to the laboratories engaged in soil investigation an opportunity to control their analytical performance and to establish the concentration level of some radionuclides in a batch of analyzed soil for certification purposes. All radionuclides were determined by typical commonly used methods: cesium-137 by direct gamma spectroscopy, plutonium-239 by alpha spectroscopy after separation and electrodeposition, radium-226 by direct determination without or with separation or by determination of radon, and strontium-90 by measurement of its daughter yttrium-90. In general, the results can be accepted as satisfactory at such low level of activity (pCi/kg). The relative confidence intervals of the medians of 137 Cs and 239 Pu are below +-10% and of 226 Ra and 90 Sr below +-20%

  13. Decontaminating effectiveness of Ca-, Zn-, MnDTPA chelates in contamination with inner radioisotopes 137Cs, 144Ce, 131I, 90Sr

    International Nuclear Information System (INIS)

    Kossakowski, S.

    1987-01-01

    The studies were carried out on 240 rabbits divided into 4 groups, in which, after contamination with radioisotopes 137 Cs (A), 144 Ce (B), 131 I (C), 90 Sr (D), Ca-, Zn-, MnDTPA chelates were used in 12.5% water solutions in doses of 0.4 g/kg of body weight. The evaluation of the decontaminating effectiveness of the above DTPA compounds, taking into account veterinary-clinical and veterinary-sanitary aspects, was made after 1,2,4,6,15 days from the contamination. The results expressing the per cent values of radioactivity of the organs are presented in individual groups. From these data it can be assumed for practical veterinary purposes that Ca-, Zn-, MnDTPA chelates show an effective action with respect to the veterinary-clinical aspect in contamination with radiocerium and with respect to the veterinary-sanitary aspect in contamination with radiocerium and radioiodine; less effective action with respect to the veterinary-sanitary aspect and ineffective with respect to the veterinary-clinical aspect in contamination with radiocesium; negative one with respect to both aspects in contamination with radiostrontium. As regards the individual chelating compounds, the most effective can be recognized sodium zinc salt of DTPA. 58 refs., 4 tabs. (author)

  14. Experimental studies on the migration of radionuclides of the elements I, Sr, Cs, Co and Pd in the roof rock of the projected waste repository at Gorleben

    International Nuclear Information System (INIS)

    Klotz, D.; Lang, H.; Moser, H.

    1985-07-01

    The studies were intended to provide information on the sorptive properties of 15 samples of fine-grain and medium-grain sands with regard to the radionuclides of I, Sr, Cs, Co, and Pd, and on their hydraulic properties. The samples were taken from the geologic formations in the area surrounding the projected waste repository in the Gorleben salt mine, at depth of up to 250 m down from terrain surface, and were analysed by means of column and batch experiments. Further goals were to determine the radionuclide migration as a function of flow velocity of the groundwater, and of sand compactness, as well as the effects of carrier ions and main groundwater contituents. The margins of retardation factors for the various radionuclides are given. One important result of the studies is that it could be expeimentally verified that there is the process of quasi irreversible sorption, i.e. it could be shown that desorption of radionuclides from natural, unconsolidated rock proceeds very much slowlier than sorption, so that this finding is of great significance to the safety assessment of a radioactive waste repository in geologic formations. (orig./HP) [de

  15. Pre operational levels of 137Cs and 90Sr in seawater and sea foods in Gulf of Mannar near Kudankulam Nuclear Power Plant

    International Nuclear Information System (INIS)

    Vijayakumar, B.; Thomas, G.; Rajan, P.S.; Selvi, B.S.; Balamurugan, M.; Ravi, P.M.; Tripathy, R.M.

    2014-01-01

    The first unit of Kudankulam Nuclear Power Project (KKNPP) attained first criticality on July 13, 2013 and synchronized to the grid on October 22, 2013. The first unit achieved the full rated power of 1000 MWe on June 7, 2014. The second unit of KKNPP is under advanced stage of commissioning and hot run of the plant is expected shortly. Commercial operational of the first unit is expected soon. It is imperative to establish the pre operational levels of Fall out nuclides like 137 Cs and 90 Sr in and around Kudankulam site, especially sea waters and sea food samples as these nuclides are produced in the reactor as fission products. Nevertheless, they are retained in the fuel matrix itself as the reactors host a multiple layered barrier to prevent the escape of these radionuclides into the environment by adopting the philosophy of defense in depth. Benchmarking the levels of these nuclides in the aquatic domain will help in future comparison of the levels of these nuclides after the plants start operation in addition to generating the regional database in south eastern tip of the sea

  16. Retention and translocation of foliar applied {sup 239,240}Pu and {sup 241}Am, as compared to {sup 137}Cs and {sup 85}Sr, into bean plants (Phaseolus vulgaris)

    Energy Technology Data Exchange (ETDEWEB)

    Henner, P. [Institute for Radioprotection and Nuclear Safety, Environment and Emergency Operations Division, Department for the Study of Radionuclides Behaviour in Ecosystems, Laboratory of Radioecology and Ecotoxicology, IRSN/DPRE/SECRE/LRE, Cadarache Centre, Building 186, BP 3, 13115 Saint-Paul-lez-Durance (France)]. E-mail: pascale.henner@irsn.fr; Colle, C. [Institute for Radioprotection and Nuclear Safety, Environment and Emergency Operations Division, Department for the Study of Radionuclides Behaviour in Ecosystems, Laboratory of Radioecology and Ecotoxicology, IRSN/DPRE/SECRE/LRE, Cadarache Centre, Building 186, BP 3, 13115 Saint-Paul-lez-Durance (France); Morello, M. [Institute for Radioprotection and Nuclear Safety, Environment and Emergency Operations Division, Department for the Study of Radionuclides Behaviour in Ecosystems, Laboratory of Radioecology and Ecotoxicology, IRSN/DPRE/SECRE/LRE, Cadarache Centre, Building 186, BP 3, 13115 Saint-Paul-lez-Durance (France)

    2005-07-01

    Foliar transfer of {sup 241}Am, {sup 239,240}Pu, {sup 137}Cs and {sup 85}Sr was evaluated after contamination of bean plants (Phaseolus vulgaris) at the flowering development stage, by soaking their first two trifoliate leaves into contaminated solutions. Initial retentions of {sup 241}Am (27%) and {sup 239,240}Pu (37%) were higher than those of {sup 137}Cs and {sup 85}Sr (10-15%). Mean fraction of retained activity redistributed among bean organs was higher for {sup 137}Cs (20.3%) than for {sup 239,240}Pu (2.2%), {sup 241}Am (1%) or {sup 85}Sr (0.1%). Mean leaf-to-pod translocation factors (Bq kg{sup -1}dry weight pod/Bq kg{sup -1}dry weight contaminated leaves) were 5.0 x 10{sup -4} for {sup 241}Am, 2.7 x 10{sup -6} for {sup 239,240}Pu, 5.4 x 10{sup -2} for {sup 137}Cs and 3.6 x 10{sup -4} for {sup 85}Sr. Caesium was mainly recovered in pods (12.8%). Americium and strontium were uniformly redistributed among leaves, stems and pods. Plutonium showed preferential redistribution in oldest bean organs, leaves and stems, and very little redistribution in forming pods. Results for americium and plutonium were compared to those of strontium and caesium to evaluate the consistency of the attribution of behaviour of strontium to transuranium elements towards foliar transfer, based on translocation factors, as stated in two radioecological models, ECOSYS-87 and ASTRAL.

  17. The 90Sr, 137Cs, 3H and 131I content in surface water and sediments of the Danube, Olt and Arges river and in milk samples for the year 1972

    International Nuclear Information System (INIS)

    Podeanu, G.; Iancu, E.

    1975-01-01

    The radioactivity of the measured radionuclides in water decreased from their discharge into the Danube to the mouth of the river. The amounts of certain radioisotopes in water samples, sediments, and milk are far below the maximum permissible concentrations. With some exceptions, the radioactivity of 137 Cs is lower than that of 90 Sr. With some exceptions, the highest values for the radionuclides studied were measured during the summer months. (orig./RW) [de

  18. Actinide separation by electrorefining

    International Nuclear Information System (INIS)

    Fusselman, S.P.; Gay, R.L.; Grantham, L.F.; Grimmett, D.L.; Roy, J.J.; Inoue, T.; Hijikata, T.; Krueger, C.L.; Storvick, T.S.; Takahashi, N.

    1995-01-01

    TRUMP-S is a pyrochemical process being developed for the recovery of actinides from PUREX wastes. This paper describes development of the electrochemical partitioning step for recovery of actinides in the TRUMP-S process. The objectives are to remove 99 % of each actinide from PUREX wastes, with a product that is > 90 % actinides. Laboratory tests indicate that > 99 % of actinides can be removed in the electrochemical partitioning step. A dynamic (not equilibrium) process model predicts that 90 wt % product actinide content can be achieved through 99 % actinide removal. Accuracy of model simulation results were confirmed in tests with rare earths. (authors)

  19. Large-scale treatment of high-salt, high-pH wastewater for {sup 137}Cs and {sup 90}Sr removal, using crystalline silicotitanate resin

    Energy Technology Data Exchange (ETDEWEB)

    Taylor, P.A.; Walker, J.F.; Lee, D.D.

    1998-04-01

    A full-scale demonstration of cesium removal technology has been conducted at Oak Ridge National Laboratory (ORNL). This demonstration utilized a modular, mobile ion-exchange system and existing facilities for the off-gas system, secondary containment, and utilities. The ion-exchange material, crystalline silicotitanate (CST), was selected on the basis of its effectiveness in laboratory tests. The CST, which was developed through a Cooperative Research and Development Agreement between DOE and private industry, is highly selective for removing cesium from solutions containing high concentrations of other contaminants, such as sodium and potassium. Approximately 116,000 liters of supernate was processed during the demonstration with {approximately} 1,142 Ci of {sup 137}Cs removed from the supernate and loaded onto 266 liters of the CST sorbent. The supernate processed had a high salt content, about 4 M NaNO{sub 3} and a pH of 12 to 13. The CST also loaded Ba, Pb, Sr, U and Zn. Analysis of the spent sorbent has shown that it is not hazardous under the Resource Conservation and Recovery Act (RCRA). The cesium breakthrough curves for the lab and full-scale columns agreed very well, suggesting that lab-scale tests can be used to predict the performance of larger systems. The cesium breakthrough curves for runs at different flowrates show that film diffusion is significant in controlling the mass transfer process. Operational factors that increase the effect of film diffusion include the small size and high porosity of the CST sorbent, and the relatively low liquid velocity through the sorbent.

  20. Numerical Modeling of 90Sr and 137Cs Transport from a Spill in the B-Cell of the 324 Building, Hanford Site 300 Area

    Energy Technology Data Exchange (ETDEWEB)

    Rockhold, Mark L.; Bacon, Diana H.; Freedman, Vicky L.; Lindberg, Michael J.; Clayton, Ray E.

    2012-03-19

    To characterize the extent of contamination under the 324 Building, a pit was excavated on the north side of the building in 2010 by Washington Closure Hanford LLC (WCH). Horizontal closed-end steel access pipes were installed under the foundation of the building from this pit and were used for measuring temperatures and exposure rates under the B-Cell. The deployed sensors measured elevated temperatures of up to 61 C (142 F) and exposure rates of up to 8,900 R/hr. WCH suspended deactivation of the facility because it recognized that building safety systems and additional characterization data might be needed for remediation of the contaminated material. The characterization work included additional field sampling, laboratory measurements, and numerical flow and transport modeling. Laboratory measurements of sediment physical, hydraulic, and geochemical properties were performed by Pacific Northwest National Laboratory (PNNL) and others. Geochemical modeling and subsurface flow and transport modeling also were performed by PNNL to evaluate the possible extent of contamination in the unsaturated sand and gravel sediments underlying the building. Historical records suggest that the concentrated 137Cs- and 90Sr-bearing liquid wastes that were spilled in B-Cell were likely from a glass-waste repository testing program associated with the Federal Republic of Germany (FRG). Incomplete estimates of the aqueous chemical composition (no anion data provided) of the FRG waste solutions were entered into a geochemical speciation model and were charge balanced with nitrate to estimate waste composition. Additional geochemical modeling was performed to evaluate reactions of the waste stream with the concrete foundation of the building prior to the stream entering the subsurface.

  1. Large-scale treatment of high-salt, high-pH wastewater for 137Cs and 90Sr removal, using crystalline silicotitanate resin

    International Nuclear Information System (INIS)

    Taylor, P.A.; Walker, J.F.; Lee, D.D.

    1998-04-01

    A full-scale demonstration of cesium removal technology has been conducted at Oak Ridge National Laboratory (ORNL). This demonstration utilized a modular, mobile ion-exchange system and existing facilities for the off-gas system, secondary containment, and utilities. The ion-exchange material, crystalline silicotitanate (CST), was selected on the basis of its effectiveness in laboratory tests. The CST, which was developed through a Cooperative Research and Development Agreement between DOE and private industry, is highly selective for removing cesium from solutions containing high concentrations of other contaminants, such as sodium and potassium. Approximately 116,000 liters of supernate was processed during the demonstration with ∼ 1,142 Ci of 137 Cs removed from the supernate and loaded onto 266 liters of the CST sorbent. The supernate processed had a high salt content, about 4 M NaNO 3 and a pH of 12 to 13. The CST also loaded Ba, Pb, Sr, U and Zn. Analysis of the spent sorbent has shown that it is not hazardous under the Resource Conservation and Recovery Act (RCRA). The cesium breakthrough curves for the lab and full-scale columns agreed very well, suggesting that lab-scale tests can be used to predict the performance of larger systems. The cesium breakthrough curves for runs at different flowrates show that film diffusion is significant in controlling the mass transfer process. Operational factors that increase the effect of film diffusion include the small size and high porosity of the CST sorbent, and the relatively low liquid velocity through the sorbent

  2. Actinide metal processing

    International Nuclear Information System (INIS)

    Sauer, N.N.; Watkin, J.G.

    1992-01-01

    A process for converting an actinide metal such as thorium, uranium, or plutonium to an actinide oxide material by admixing the actinide metal in an aqueous medium with a hypochlorite as an oxidizing agent for sufficient time to form the actinide oxide material and recovering the actinide oxide material is described together with a low temperature process for preparing an actinide oxide nitrate such as uranyl nitrate. Additionally, a composition of matter comprising the reaction product of uranium metal and sodium hypochlorite is provided, the reaction product being an essentially insoluble uranium oxide material suitable for disposal or long term storage

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

    Energy Technology Data Exchange (ETDEWEB)

    Hardy, E.P. Jr.

    1976-07-01

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

  4. Retention behavior of actinides and long lived fission products on Smectite rich clays

    International Nuclear Information System (INIS)

    Tomar, B.S.

    2014-01-01

    In the present work, sorption of Am(llI), Cs(I) and Sr(ll) by the Smectite rich clay from western India has been studied in detail under the varying experimental conditions, viz., pH, ionic strength, and metal ion concentration. The experimental data on sorption have been modeled using the surface complexation model. Am(llI) sorption by smectite rich clay was found to increase with the pH of the suspension. At lower pH values, the sorption decreased with increasing ionic strength of the suspension, but remained constant at higher pH values. This is reminiscent of the ion exchange mechanism at lower pH and predominantly inner sphere complexation at higher pH. Surface complexation modeling using FITEQL could successfully explain these two mechanisms operating in the different pH values. Sorption of Cs(I) and Sr(II) by the smectite rich clay was studied under the varying experimental conditions. Though the sorption of both the metal ions increased with pH, it decreased with the increasing ionic strength, at all pH values, suggesting ion exchange as the predominant mechanism at all pH values. Further, the ionic strength dependence was different in the case of Cs(I) and Sr(II) depending upon the metal ion concentration. At same metal ion concentration of Cs(I) and Sr(II) (10 -5 M) the extent of decrease with ionic strength was same in both cases, while at 10 -9 M, Cs(I), the decrease was much smaller than that at 10 -5 M. This indicates the existence of ion exchange sites having different affinities. These studies have shown high retention capacity of the clay for actinides and long lived fission products with the sorption following ion exchange mechanism in the case of Cs(I) and Sr(II) and a combination of ion exchange and surface complexation in the case of Am(III) depending upon the pH. The sorption data could be successfully explained within the framework of FITEQL, taking into account both the types of binding sites

  5. Actinide metals

    Energy Technology Data Exchange (ETDEWEB)

    Brown, Paul L. [Geochem Australia, Kiama, NSW (Australia); Ekberg, Christian [Chalmers Univ. of Technology, Goeteborg (Sweden). Nuclear Chemistry/Industrial Materials Recycling

    2016-07-01

    All isotopes of actinium are radioactive and exist in aqueous solution only in the trivalent state. There have been very few studies on the hydrolytic reactions of actinium(III). The hydrolysis reactions for uranium would only be important in alkaline pH conditions. Thermodynamic parameters for the hydrolysis species of uranium(VI) and its oxide and hydroxide phases can be determined from the stability and solubility constants. The hydrolytic behaviour of neptunium(VI) is quite similar to that of uranium(VI). The solubility constant of NpO{sub 2}OH(am) has been reported a number of times for both zero ionic strength and in fixed ionic strength media. Americium can form four oxidation states in aqueous solution, namely trivalent, tetravalent, pentavalent and hexavalent. Desire, Hussonnois and Guillaumont determined stability constants for the species AmOH{sup 2+} for the actinides, plutonium(III), americium(III), curium(III), berkelium(III) and californium(III) using a solvent extraction technique.

  6. Actinide metals

    International Nuclear Information System (INIS)

    Brown, Paul L.; Ekberg, Christian

    2016-01-01

    All isotopes of actinium are radioactive and exist in aqueous solution only in the trivalent state. There have been very few studies on the hydrolytic reactions of actinium(III). The hydrolysis reactions for uranium would only be important in alkaline pH conditions. Thermodynamic parameters for the hydrolysis species of uranium(VI) and its oxide and hydroxide phases can be determined from the stability and solubility constants. The hydrolytic behaviour of neptunium(VI) is quite similar to that of uranium(VI). The solubility constant of NpO 2 OH(am) has been reported a number of times for both zero ionic strength and in fixed ionic strength media. Americium can form four oxidation states in aqueous solution, namely trivalent, tetravalent, pentavalent and hexavalent. Desire, Hussonnois and Guillaumont determined stability constants for the species AmOH 2+ for the actinides, plutonium(III), americium(III), curium(III), berkelium(III) and californium(III) using a solvent extraction technique.

  7. 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

  8. Radionuclides {sup 137}Cs, {sup 90}Sr, {sup 241}Am and {sup 239+240}Pu in vegetation cover of the former Semipalatinsk test site

    Energy Technology Data Exchange (ETDEWEB)

    Larionova, N. [Institute of Radiation Safety and Ecology (Kazakhstan); Lukashenko, S. [Institute of Radiation Safety and Ecology of the Republican State Enterprise (Kazakhstan)

    2014-07-01

    integrated picture about accumulation of artificial radionuclides {sup 137}Cs, {sup 90}Sr, {sup 239+240}Pu and {sup 241}Am in plants at STS. It has been found that parameters of radionuclide accumulation in plants primarily depend on the nature of radioactive contamination of STS, in particular speciation radionuclides in soil. Certain differences are observed for individual species of plants and soils, which are characterized by different physico-chemical properties. Radionuclides have been broken down by their ability to accumulate from soil into above-ground parts of plants, a quantitative characterization of difference in accumulation is provided. A comparative analysis of the accumulation factors for the various areas of STS and generalized international data. Recommendations have been provided on the safe use of forage of natural pastures at STS. Document available in abstract form only. (authors)

  9. Advances in computational actinide chemistry in China

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Dongqi; Wu, Jingyi; Chai, Zhifang [Chinese Academy of Sciences, Beijing (China). Multidisciplinary Initiative Center; Su, Jing [Chinese Academy of Sciences, Shanghai (China). Div. of Nuclear Materials Science and Engineering; Li, Jun [Tsinghua Univ., Beijing (China). Dept. of Chemistry and Laboratory of Organic Optoelectronics and Molecular Engineering

    2014-04-01

    The advances in computational actinide chemistry made in China are reviewed. Several areas relevant to chemistry of actinides in gas, liquid, and solid phases have been explored. However, we limit the scope to selected contributions in the chemistry of molecular actinide systems in gas and liquid phases. These studies may be classified into two categories: treatment of relativistic effects, which cover the development of two- and four-component Hamiltonians and the optimization of relativistic pseudopotentials, and the applications of theoretical methods in actinide chemistry. The applications include (1) the electronic structures of actinocene, noble gas complexes, An-C multiple bonding compounds, uranyl and its isoelectronic species, fluorides and oxides, molecular systems with metal-metal bonding in their isolated forms (U{sub 2}, Pu{sub 2}) and in fullerene (U{sub 2} rate at C{sub 60}), and the excited states of actinide complexes; (2) chemical reactions, including oxidation, hydrolysis of UF{sub 6}, ligand exchange, reactivities of thorium oxo and sulfido metallocenes, CO{sub 2}/CS{sub 2} functionalization promoted by trivalent uranium complex; and (3) migration of actinides in the environment. A future outlook is discussed. (orig.)

  10. Effect of mycorrhizal infection on root uptake by pine seedlings and redistribution of three contrasting radio-isotopes: {sup 85}Sr, {sup 95m}Tc and {sup 137}Cs

    Energy Technology Data Exchange (ETDEWEB)

    Plassard, C.; Ladeyn, I.; Staunton, S. [Institut National de Recherches Agronomiques (INRA), UMR Rhizosphere and Symbiose 34 - Montpellier (France)

    2004-07-01

    Mycorrhizal infection is known to improve phosphate nutrition and water supply of higher plants. It has been reported to both increase the uptake of potentially toxic pollutant elements and to protect plants against toxic effects. Little is known about the effect of mycorrhizal infection on the dynamics of radioactive pollutants in soil-plant systems. The aim of this study was to compare the root uptake and root-shoot transfer of three radio-isotopes with contrasting chemical properties ({sup 85}Sr, {sup 95m}Tc and {sup 137}Cs) in mycorrhizal and control, non mycorrhizal plants. The plant studied was Pinus pinaster and the associated ecto-mycorrhizal fungus was Rhizopogon roseolus (strain R18-2). Plants were grown under anoxic conditions for 3 months then transferred to thin layers of autoclaved soil and allowed to grow for four months. After this period, the rhizotrons were dismantled, and plant tissue analysed. Biomass, nutrient content (K, P, N, Ca) and activities of each isotope in roots, shoots and stems were measured, and the degree of mycorrhizal infection assessed. The transfer factors decreased in the order Tc>Sr>Cs as expected from the degree of immobilisation by soil. No effect of mycorrhizal infection on root uptake was observed for Sr. Shoot activity concentration of Tc was decreased by mycorrhizal infection but root uptake correlated well with mycelial soil surface area. In contrast, Cs shoot activity was greater in mycorrhizal than control plants. The uptake and root to shoot distribution shall be discussed in relation to nutrient dynamics. (author)

  11. Assessment of transferring Sr-90 and Cs-137 in products of processing of seeds raps for getting raps' oil and biodiesel

    International Nuclear Information System (INIS)

    Yatsino, T.S.; Mironov, V.P.

    2009-01-01

    The objects of research are soil assays, seeds of raps, straw and the stalks selected on polluted radio nuclides of territory. The work purpose is to measure specific activity of strontium and cesium in assays, to calculate factors of transition Sr 90 and Sr 137 in products of processing of seeds of raps. (authors)

  12. Mycorrhizal association of maritime pine, Pinus pinaster, with Rhizopogon roseolus has contrasting effects on the uptake from soil and root-to-shoot transfer of {sup 137}Cs, {sup 85}Sr and {sup 95m}Tc

    Energy Technology Data Exchange (ETDEWEB)

    Ladeyn, Ingrid; Plassard, Claude [INRA, UMR 1222, Biogeochimie du Sol et de la Rhizosphere, place Viala, 34060 Montpellier (France); Staunton, Siobhan [INRA, UMR 1222, Biogeochimie du Sol et de la Rhizosphere, place Viala, 34060 Montpellier (France)], E-mail: staunton@montpellier.inra.fr

    2008-05-15

    The beneficial role of mycorrhizal association on plant nutrition and water supply is well-known, however, very little information exists with respect to the availability of radionuclides. We have measured the effect of controlled mycorrhizal association on the root uptake from soil and accumulation in leaves of three radionuclides. The radionuclides have contrasting chemical and biological properties: Cs is strongly adsorbed on soil, has no biological role and is a close analogue of potassium; Sr is less strongly adsorbed on soil and behaves very similarly to calcium; and Tc is very mobile in soil as pertechnetate, but immobilised when reduced to Tc(IV), it is also considered to be easily assimilated by biological systems. We found that mycorrhizal association had no effect on root-to-needle transfer of Cs, but increased root uptake and that this increase could not be explained by improved potassium nutrition. In contrast, the symbiotic relation decreased Tc soil-to-needle transfer, but this resulted from complex dynamics of root uptake and rapid immobilisation of Tc in soil. No effect of mycorrhizal association on Sr, like its stable analogue Ca, was observed. The addition of a phytotoxic metal, Cu, inhibited mycorrhizal association, thus eliminating the effects observed for non-contaminated plant-fungus couples, but had no additional effect on radionuclide dynamics.

  13. Mycorrhizal association of maritime pine, Pinus pinaster, with Rhizopogon roseolus has contrasting effects on the uptake from soil and root-to-shoot transfer of 137Cs, 85Sr and 95mTc

    International Nuclear Information System (INIS)

    Ladeyn, Ingrid; Plassard, Claude; Staunton, Siobhan

    2008-01-01

    The beneficial role of mycorrhizal association on plant nutrition and water supply is well-known, however, very little information exists with respect to the availability of radionuclides. We have measured the effect of controlled mycorrhizal association on the root uptake from soil and accumulation in leaves of three radionuclides. The radionuclides have contrasting chemical and biological properties: Cs is strongly adsorbed on soil, has no biological role and is a close analogue of potassium; Sr is less strongly adsorbed on soil and behaves very similarly to calcium; and Tc is very mobile in soil as pertechnetate, but immobilised when reduced to Tc(IV), it is also considered to be easily assimilated by biological systems. We found that mycorrhizal association had no effect on root-to-needle transfer of Cs, but increased root uptake and that this increase could not be explained by improved potassium nutrition. In contrast, the symbiotic relation decreased Tc soil-to-needle transfer, but this resulted from complex dynamics of root uptake and rapid immobilisation of Tc in soil. No effect of mycorrhizal association on Sr, like its stable analogue Ca, was observed. The addition of a phytotoxic metal, Cu, inhibited mycorrhizal association, thus eliminating the effects observed for non-contaminated plant-fungus couples, but had no additional effect on radionuclide dynamics

  14. Transfer pathways of {sup 54}Mn, {sup 57}Co, {sup 85}Sr, {sup 103}Ru and {sup 134}Cs in rice and radish plants directly contaminated at different growth stages

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Y.H. E-mail: yhchoi1@kaeri.re.kr; Lim, K.M.; Yu, D.; Park, H.G.; Choi, Y.G.; Lee, C.M

    2002-03-01

    In order to study radionuclide transfer pathways related to direct contamination of plants, the above-ground parts of rice and radish plants were sprayed with a solution containing {sup 54}Mn, {sup 57}Co, {sup 85}Sr, {sup 103}Ru and {sup 134}Cs in a greenhouse at 5 or 6 different times. Showing little difference among radionuclides, the interception factor increased as plants grew to maturity. Its highest observed value was 0.94 in rice and 0.83 in radish. Weathering losses of the intercepted activity by harvest were 32-89% in rice and 32-85% in radish depending on application time and radionuclide. Half lives for weathering loss were estimated to be longer on the whole for earlier applications. The translocation factor varied with application time by factors of 6-110 for hulled rice seeds and 2-23 for radish roots depending on the radionuclide. It varied with radionuclides by factors of 6-800 depending on application time and plant species. It was highest in the plants sprayed during active seed growth for rice and during early plant growth for radish. In general, {sup 134}Cs and {sup 57}Co had the highest translocation factors followed by {sup 54}Mn, {sup 85}Sr and {sup 103}Ru. Based on the experimental results, radionuclide concentrations in the edible parts of mature plants were predicted for unit deposition.

  15. Studies on the radioactive contamination due to nuclear detonations V. The radioactive contamination of human body by Sr{sup 90} and Cs{sup 137} and its correlation with the fallout rate and ground deposition

    Energy Technology Data Exchange (ETDEWEB)

    Nishiwaki, Yasushi [Nuclear Reactor Laboratory, Tokyo Institute of Technology, Tokyo (Japan); Nuclear Reactor Laboratoroy, Kinki University, Fuse City, Osaka Precture (Japan)

    1961-11-25

    About 60 bone samples were analysed for Sr 90 during the period from January 1957 to July 1959. The highest average concentration was found to be about 1 S.U for the age group of 5 to 10 years old. However since most of the cases are more or less pathological ones after long period of hospitalization the results may not be considered to be the representative values for the average normal person. The highest concentration among the cases whose past history is known was 175 S.U. or roughly, about 2 S.U. During the period of observation occasionally we have found higher concentration than 2 S.U, in the bone samples of a few cases obtained from the crematory. However, since the past history of these cases is not known, it is not clear whether they depended on the rainwater or on the brown ice with much higher contamination than the white rice. In view of these findings it may not be to, much to assume that the concentration of Sr 90 in te bones of the average normal children might reach 2 S.U c corresponding to the cumulative ground deposition and the fallout rate. The concentration of Cs whose physical half-life is very much similar to Sr 90 was in the range of about 30 - 100 cesium unit in 1957 to early 1958. However, during the period from 1958 to early 1959 the concentration of Cs 137 in come of the organs of the human body has been reported to be about two to three times higher on the average in Tokyo than the above value in 1957.

  16. Studies on the radioactive contamination due to nuclear detonations V. The radioactive contamination of human body by Sr90 and Cs137 and its correlation with the fallout rate and ground deposition

    International Nuclear Information System (INIS)

    Nishiwaki, Yasushi

    1961-01-01

    About 60 bone samples were analysed for Sr 90 during the period from January 1957 to July 1959. The highest average concentration was found to be about 1 S.U for the age group of 5 to 10 years old. However since most of the cases are more or less pathological ones after long period of hospitalization the results may not be considered to be the representative values for the average normal person. The highest concentration among the cases whose past history is known was 175 S.U. or roughly, about 2 S.U. During the period of observation occasionally we have found higher concentration than 2 S.U, in the bone samples of a few cases obtained from the crematory. However, since the past history of these cases is not known, it is not clear whether they depended on the rainwater or on the brown ice with much higher contamination than the white rice. In view of these findings it may not be to, much to assume that the concentration of Sr 90 in te bones of the average normal children might reach 2 S.U c corresponding to the cumulative ground deposition and the fallout rate. The concentration of Cs whose physical half-life is very much similar to Sr 90 was in the range of about 30 - 100 cesium unit in 1957 to early 1958. However, during the period from 1958 to early 1959 the concentration of Cs 137 in come of the organs of the human body has been reported to be about two to three times higher on the average in Tokyo than the above value in 1957

  17. Synthesis of tetravalent actinide chlorides. Versatile compounds for actinide chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Maerz, Juliane [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Div. Chemistry of the F-Elements

    2016-07-01

    Anhydrous actinide tetrachlorides (AnCl{sub 4}) were synthesized under mild conditions to provide versatile compounds for actinide chemistry. They enable a direct access to actinide complexes with organic and inorganic ligands.

  18. Synthesis, structure, and electrical conductivity of A'[A(sub 2)B(sub 3)O(sub 10)] (A'=Rb, Cs A=Sr, Ba; B=Nb, Ta)

    International Nuclear Information System (INIS)

    Thangadurai, Venkataraman; Schmid-Beurmann, Peter; Weppner, Werner

    2001-01-01

    New members of Dion-Jacobson (D-J)-type layered perovskites of the general formula A'[A(sub 2)B(sub 3)O(sub 10)] (A'=Rb, Cs; A=Sr, Ba; B=Nb, Ta) were prepared by solid-state reactions between the metal oxides, nitrates, and carbonates under specific conditions. The crystal structures were determined using powder X-ray diffraction data in combination with Rietveld analysis. The c-axis lattice parameter increases as the size of the alkaline earth ion increases. Both Sr and Ba compounds crystallize in a tetragonal cell, while the corresponding Ca compounds crystallize in an orthorhombic cell. The electrical conductivity of the layered perovskites was determined using AC impedance analysis and DC methods. Among the compounds with the same alkali ion and different alkaline earth ions, the Ca compound exhibits a higher electrical conductivity than the corresponding Sr and Ba compounds. DC measurements reveal that the layered perovskites exhibit both ionic and electronic conduction

  19. Fabrication and characterization of SrAl{sub 2}O{sub 4}: Eu{sup 2+} Dy{sup 3+}/CS-PCL electrospun nanocomposite scaffold for retinal tissue regeneration

    Energy Technology Data Exchange (ETDEWEB)

    Sepahvandi, Azadeh; Eskandari, Mahnaz, E-mail: eskandarim@aut.ac.ir; Moztarzadeh, Fathollah

    2016-09-01

    Millions of people around the world become blind due to losing a part of the retina cells. In tissue engineering field one way to address this issue is to develop a retina tissue by scaffolds based on structure and signals received These scaffolds can play an essential role in repair and reformation of the damaged retina tissue. Here, SrAl{sub 2}O{sub 4}: Eu{sup 2+}, Dy{sup 3+} nanophosphor were prepared by sol-gel method and then coated with PEG to become biocompatible. Next 10%, 30% and 50% concentration of the coated nanophosphors were dispersed in CS-PCL copolymer and electrospuned to form SrAl{sub 2}O{sub 4}: Eu{sup 2+}, Dy{sup 3+}/CS-PCL scaffolds. The aforementioned photo –luminescence-scaffolds were studied for their optical, mechanical and morphological characteristics finally the effect of these scaffolds on the mice RPCs cells' proliferation and differentiation was observed. The 30% nanophosphor dispersion scaffold while providing adequate mechanical flexibility and integrity, and exhibiting superior proliferation rates and acceptable differentiation into retinal neural cells (particularly photo receptors retinal) is suggested as a promising choice in retinal tissue repair. - Highlights: • The 30% nanophosphor dispersion scaffold for both shorter wavelength and middle intense emission is more near to biocompatible nanophosphors. • 30% dispersed nanophosphor scaffold displays satisfactory mechanical strength and flexibility where its behavior is similar to the retina tissue. • Besides as the most effective signal in this study is the electromagnetic signals emitted by nanophosphors, we attribute the enhanced proliferation to the positive effects of the later, the emitted signals of scaffolds. • The tendency towards spherical morphology implies that emitting light may stimulate the cell signaling toward differentiation • These findings implies that mRPC grown on SrAl{sub 2}O{sub 4}: Eu{sup 2+},Dy{sup 3+}/CS-PCL scaffolds in differentiation

  20. Distribution of 137Cs, 90Sr, 239+240Pu, 241Am and 230,232Th on the fractions of natural organic species soils of ChNPP alienation zone

    International Nuclear Information System (INIS)

    Odintsov, A.A.; Sazhenyuk, A.D.

    2003-01-01

    The experimental data determination of distribution 137 Cs, 90 Sr, 239+240 Pu, 241 Am 'Chernobyl' releases and 230 , 232 Th on the fraction of humic and fulvic acids sandy- podsolic, meadow and peaty soils taken in the exclusive zone ChNPP are presents. Soils organic matter was isolated by conventional alkali extraction (Turin's method). It was shown that, with depending of soils types 15-45 % 241 Am associate with fulvic acids. In all investigated types of soils 30 - 40 % 239+240 Pu connects with humic acids, as strong complexes. The distribution of environmental 230 , 232 Th and artificial 239+240 Pu on the fraction natural organic species is the same

  1. Determinations of [sup 90]Sr, [sup 137]Cs, [sup 226]Ra, [sup 228]Ra, [sup 210]Pb, [sup 210]Po contents in chinese diet and estimations of internal doses due to these radionuclides

    Energy Technology Data Exchange (ETDEWEB)

    Hongda, Zhu; Shouliang, Wang; Wei, Meng; Daoping, Wang; Xiujun, Zheng; Qingfen, Liu; Peng, Liu [Chinese Academy of Medical Sciences, Tianjin, TJ (China). Inst. of Radiomedicine

    1993-03-01

    As a part of Chinese Total Diet Survey taken place in 1990, the authors report the determined results on [sup 90]Sr, [sup 137]Cs, [sup 226]Ra, [sup 228]Ra, [sup 210]Pb and [sup 210]Pb and [sup 210]Po contents in various foods of Chinese total diet. Based on obtained dietary composition and the determined contents, the Annual Intakes (AI) and Committed Dose Equivalents (CDE) for the public by ingestion were estimated. It is shown that the total CDE for 6 radionuclides is about 0.24 mSv/a. The food categories and nuclides whose relative contributions to the total are dominant were vegetables, aquatic products and cereal, and [sup 210]Pb, [sup 210]Po, [sup 228]Ra, respectively. The results have updated the data from 1982 survey and have complemented important information for water consumption. The regional difference of dietary compositions and resultant internal doses are discussed as well.

  2. Experimental studies of the migration of radionuclides of the elements Cs, Sr, Ra, Mo, I, and C in the caprock of the Gorleben candidate repository

    International Nuclear Information System (INIS)

    Klotz, D.; Lang, H.; Moser, H.

    1988-01-01

    The studies were mainly concerned with investigations of the sorption of radioactive Cs and C using three sandy and three cohesive samples with the help of batch and continuous-flow column tests. The results show that the sorption behaviour of Cs-134 can be described with the help of an exponential isotherm. Differences in sorption and desorption behaviour as well as the dependence of the results on the volume/mass ratios applied in the batch tests are explained in this way. Accordingly, the transportation of the Cs in continuous-column tests reveals a delay increase proportional to an increase of path length. The tests using C-14 are strongly inhibited by a rapid exchange of the applied C-14 labelled carbonate ions with the CO 2 of the supernatant gaseous phase. This notwithstanding, it could be shown that the carbonate ions are only slightly delayed, and that substantial quantities of the radioactive carbon applied are held back with the examined sediments. (orig./HP) [de

  3. Thermodynamic Properties of Actinides and Actinide Compounds

    Science.gov (United States)

    Konings, Rudy J. M.; Morss, Lester R.; Fuger, Jean

    The necessity of obtaining accurate thermodynamic quantities for the actinide elements and their compounds was recognized at the outset of the Manhattan Project, when a dedicated team of scientists and engineers initiated the program to exploit nuclear energy for military purposes. Since the end of World War II, both fundamental and applied objectives have motivated a great deal of further study of actinide thermodynamics. This chapter brings together many research papers and critical reviews on this subject. It also seeks to assess, to systematize, and to predict important properties of the actinide elements, ions, and compounds, especially for species in which there is significant interest and for which there is an experimental basis for the prediction.

  4. Research in actinide chemistry

    International Nuclear Information System (INIS)

    Choppin, G.R.

    1993-01-01

    This research studies the behavior of the actinide elements in aqueous solution. The high radioactivity of the transuranium actinides limits the concentrations which can be studied and, consequently, limits the experimental techniques. However, oxidation state analogs (trivalent lanthanides, tetravalent thorium, and hexavalent uranium) do not suffer from these limitations. Behavior of actinides in the environment are a major USDOE concern, whether in connection with long-term releases from a repository, releases from stored defense wastes or accidental releases in reprocessing, etc. Principal goal of our research was expand the thermodynamic data base on complexation of actinides by natural ligands (e.g., OH - , CO 3 2- , PO 4 3- , humates). The research undertakes fundamental studies of actinide complexes which can increase understanding of the environmental behavior of these elements

  5. The estimation of 137Cs and 90Sr location in the biomass of the macrophytes from the Yenisei river (Krasnoyarsky region, Russia) and Glubokoe lake (Chernobyl accident exclusion zone, Ukraine)

    International Nuclear Information System (INIS)

    Zotina, T.A.; Bolsunovskiy, A.Ya.; Klenus, V.G.; Gudkov, D.I.; Belyaev, V.V.

    2008-01-01

    The distribution of cesium and strontium as well as their chemical analogs potassium and calcium in the biomass of aquatic plants collected in zone of radioactive contamination of the Yenisei River and in Glubokoe Lake, in Chernobyl accident exclusion zone, was investigated with chemical fractionation technique. Despite of the essential difference in activity concentration in the biomass of the plants from the two water bodies, the distribution of 137 Cs among the biomass fractions was similar. 90 Sr was recorded in the biomass in more mobile form, than 137 Cs. The distribution of cesium in the biomass of plants essentially differed from the distribution of it's chemical analog, potassium. The distribution of elements - analogs, 90 S and Ca, in the biomass of the plants was similar. More than half of cesium concentration in the samples of plants from the Yenisei River was associated with particles of seston, bound to the surface of the plants. The results obtained should be considered while interpret the data of radioecological monitoring and modeling of the migration of radionuclides in the water bodies.

  6. Foliar contamination of Phaseolus vulgaris with aerosols of {sup 137}Cs, {sup 85}Sr, {sup 133}Ba and {sup 123m}Te: influence of plant development stage upon contamination and rain

    Energy Technology Data Exchange (ETDEWEB)

    Madoz-Escande, C. E-mail: chantal.madoz-escande@irsn.fr; Henner, P.; Bonhomme, T

    2004-07-01

    As part of a requirement to improve the assessment of the impact of radioactive fallout on consumed agricultural products, bean plants at four development stages (seedlings, preflowering, late flowering and mature plants) were contaminated by dry deposition of {sup 137}Cs, {sup 85}Sr, {sup 133}Ba and {sup 123m}Te aerosols. The influence of two rain scenarios and of the development stage upon contamination on interception, retention, and translocation to pods was studied. Interception of the four radionuclides was almost identical and varied from 30 to 60% with increasing development stage. The most important rain parameter was the time which elapsed between contamination and the first rain. Whatever the development stage, rain washed off more cesium from the leaves when it occurred 2 days after the deposit (37% at the seedling stage, for example) rather than later on (6 days, 27%), due to rapid migration of Cs in the plant. The first rain washed off nearly 40% of Ba whatever the scenario. For later stages, Sr and Ba were more washed off by heavy weekly rains than by weak twice-a-week rains, perhaps because of the Sr/Ba-contaminated material loss associated with wash off (desquamation of cuticles). Te showed little wash off (less than 5%). Wash off decreased with an older development stage for a weak rain intensity, due to the superimposition of leaves. Heavy rains removed this shelter effect. At harvest, rain effect was no longer detectable as foliar activity was similar for both rain scenarios. Translocation factors (TF) for strontium and barium increased from 6x10{sup -3} to 1x10{sup -1} with the plant development stage upon contamination, whereas those for cesium remained almost unchanged between 2x10{sup -1} and 4 x 10{sup -1}. Flowering is the most critical stage towards residual contamination in pods at harvest, with the exception of direct deposit on pods at the mature stage (TF values are one order of magnitude higher). TF value for Te was 6.5x10{sup -2

  7. Measuring and predicting the transport of actinides and fission product contaminants in unsaturated prairie soil

    Science.gov (United States)

    Sims, D. J.

    Soil samples have been taken in 2001 from the area of a 1951 release from an underground storage tank of 6.7 L of an aqueous solution of irradiated uranium (360 GBq). A simulation of the dispersion of the actinides and fission products was conducted in the laboratory using irradiated natural uranium, non-irradiated natural uranium and metal standards dissolved in acidic aqueous solutions and added to soil columns containing uncontaminated prairie soil. The lab soil columns were allowed 12 to 14 months for contaminant transport. Soil samples were analyzed using gamma-ray spectroscopy, neutron activation analysis (NAA) and liquid scintillation counting (LSC) to determine the elemental concentrations of U, Cs and Sr. Diffusion coefficients from the 50 year soil samples and the lab soil samples were determined. The measured diffusion coefficients from the field samples were 3.0 x 10-4 cm2 s-1 (Cs-137), 1.8 x 10-5 cm2 s-1 (U-238) and 2.6 x 10-3 cm2 s-1 (Sr-90) and the values determined from lab simulation were 5 x 10-6 cm 2 s-1 (Cs-137), 3 x 10-5 cm2 s-1 (U-238) and 1.9 x 10-5 cm 2 s-1 (Sr-90). The differences between the sets of diffusion coefficients can be attributed to differences in retardation effects, weather effects and changes in the soil characteristics when transporting, such as porosity. The analytical work showed that Cs-137 content of soil can be determined effectively using gamma-ray spectroscopy; U-238 content can be measured using NAA; and Sr-90 content can be measured using LSC. For non- and low-radioactive species, it was shown that both flame atomic absorption spectrometry (FAAS) and inductively-coupled plasma-mass spectrometry (ICP-MS) gave comparable results for Sr, Cs and Sm, with the average values ranging from 0.5 to 4.5 ppm of each other. The U-238 content results from NAA and from ICP-MS showed general agreement with an average difference of 81.3 ppm on samples having concentrations up to 988.2 ppm. The difference may have been due to matrix

  8. Screening assessment from potential exposure to 137Cs, 60Co and 90Sr in the upper floodplain of White Oak Lake

    International Nuclear Information System (INIS)

    Ghiron, J.A.

    1991-01-01

    In 1943, Oak Ridge National Laboratory formed White Oak Lake, a small shallow retention basin for their treated and untreated liquid waste. The waste flowed into White Oak Lake, where it was retained for a period of time, and most of the radioactive contaminants settled out, accumulating in the lake bed. Currently, the lake is being maintained at a lower level than in the past. Consequently, sections of the old lake bed are presently exposed as an upper floodplain. A preliminary screening assessment was performed on the upper floodplain of White Oak Lake to identify the radionuclides of concern, quantify the potential risk to human health, and rank potential contaminants of concern. From the screening criteria applied in this assessment, 137 Cs in the external pathway and in the ingestion pathway was identified as a high priority contaminant. The external and ingestion pathways were identified as pathways of concern that need to be addressed in further investigations. Screening did not identify the inhalation pathway as a potential pathway of concern. It is recommended that when the health risk assessment is conducted, emphasis should be placed on investigating the potential exposures from 137 Cs in the external and ingestion pathways

  9. Actinide partitioning from HLW in a continuous DIDPA extraction process by means of centrifugal extractors

    International Nuclear Information System (INIS)

    Morita, Y.; Kubota, M.; Glatz, J.P.; Koch, L.; Pagliosa, G.; Roemer, K.; Nicholl, A.

    1996-01-01

    An experiment on actinide partitioning from real high level waste (HLW) was performed in a continuous process by extraction with diisodecylphosphoric acid (DIDPA) using a battery of 12 centrifugal extractors installed in a hot cell. The HNO 3 concentration of the HLW was adjusted to 0.5 M by dilution. The extraction section had 8 stages, and H 2 O 2 was added to extract Np effectively. After extraction, Am and Cm were back-extracted with 4 M HNO 3 in 4 stages and Np and Pu were stripped with 0.8 M H 2 C 2 O 4 in 8 stages. The actinides, expect Np, were extracted from HLW with a very high yield. Although only 84% of the Np were recovered in the present experiment, the recovery would be improved to 99.7 % by increasing the temperature to 45 degree C, the number of stages from 8 to 16 and the H 2 O 2 concentration from 1 M to 2 M. Long-lived Tc and the main heat and radiation emitters Cs and Sr were not extracted and were thus separated from the actinides with high decontamination factors. About 98% of Am and Cm were recovered from the loaded solvent in the first stripping step with 4M HNO 3 . About 86% of Np and about 92% of Pu were back-extracted with 0.8 M H 2 C 2 O 4 . These incomplete recoveries would be improved by increasing the number of stages and by optimizing the other process parameters. 18 refs., 5 figs., 3 tabs

  10. A study of internal contamination levels resulting from {sup 90}Sr and {sup 137}Cs environmental pollution. The influence of different factors; Etude des niveaux de contamination interne resultant d'une pollution de l'environnement par le {sup 90}Sr et le {sup 137}Cs influence des differents parametres

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, A [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1970-07-01

    This study includes two parts. The purpose of the former one is to try and evaluate the amounts of {sup 90}Sr and {sup 137}Cs dietary intakes as a function of age with a view to assessing internal exposure doses and estimating the critical age, and to study the relative significance of the several factors it depends on. The data used are both the results of dietary surveys made in 11 districts of the European community from which the evolution of the consumed amounts of 13 groups of foodstuffs, as a function of age was derived, and the mean factors of contamination pathways. The variability of some factors is very large and an attempt is made to assess their significance on the whole contamination; also, the influence of the various diets has been emphasized. The purpose of the second part is to assess, doses as a function of age in the case of protracted exposure on the basis of the aforesaid results and radiobiological factors derived from bibliographic states of the arts. An assessment is made of body burdens and mean doses (either to the skeleton or the whole body according to the radionuclides) originating either from a direct unitary exposure or from situations implying both modes of exposure. As assumed only the diets vary with the districts, thus the results reflect their significance which should be corrected, for a more accurate assessment of the dose variability, by the significance of human and transfer factors. (author) [French] Cette etude comprend deux parties. L'objet de la premiere partie est a la fois un essai d'evaluation en fonction de l'age des quantites de strontium 90 et de cesium 137 ingerees avec les aliments dans la perspective d'une application a l'estimation des doses d'irradiation interne et a la recherche de l'age critique, et une etude de l'influence relative des divers parametres dont elle depend. Les donnees utilisees sont, d'une part, les resultats des enquetes alimentaires faites en onze regions de la Communaute Europeenne dont on

  11. A study of internal contamination levels resulting from {sup 90}Sr and {sup 137}Cs environmental pollution. The influence of different factors; Etude des niveaux de contamination interne resultant d'une pollution de l'environnement par le {sup 90}Sr et le {sup 137}Cs influence des differents parametres

    Energy Technology Data Exchange (ETDEWEB)

    Garnier, A. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1970-07-01

    This study includes two parts. The purpose of the former one is to try and evaluate the amounts of {sup 90}Sr and {sup 137}Cs dietary intakes as a function of age with a view to assessing internal exposure doses and estimating the critical age, and to study the relative significance of the several factors it depends on. The data used are both the results of dietary surveys made in 11 districts of the European community from which the evolution of the consumed amounts of 13 groups of foodstuffs, as a function of age was derived, and the mean factors of contamination pathways. The variability of some factors is very large and an attempt is made to assess their significance on the whole contamination; also, the influence of the various diets has been emphasized. The purpose of the second part is to assess, doses as a function of age in the case of protracted exposure on the basis of the aforesaid results and radiobiological factors derived from bibliographic states of the arts. An assessment is made of body burdens and mean doses (either to the skeleton or the whole body according to the radionuclides) originating either from a direct unitary exposure or from situations implying both modes of exposure. As assumed only the diets vary with the districts, thus the results reflect their significance which should be corrected, for a more accurate assessment of the dose variability, by the significance of human and transfer factors. (author) [French] Cette etude comprend deux parties. L'objet de la premiere partie est a la fois un essai d'evaluation en fonction de l'age des quantites de strontium 90 et de cesium 137 ingerees avec les aliments dans la perspective d'une application a l'estimation des doses d'irradiation interne et a la recherche de l'age critique, et une etude de l'influence relative des divers parametres dont elle depend. Les donnees utilisees sont, d'une part, les resultats des enquetes alimentaires faites en

  12. Study in Vietnam on ingestion and organ content of trace elements of importance in radiological protection (Cs, I, Sr, U, Th etc.)

    International Nuclear Information System (INIS)

    Nguyen Mong Sinh

    2000-01-01

    This report presents results of our investigation work carried out from November 1996 to April 1998 in the field of 'Study in Vietnam on ingestion and organ content of trace elements of importance in Radiological Protection'. This work related to the Co-ordinated Research Programme for Reference Asian Man Project, Phase 2. The data reported are the daily individual intake of the elements of interest for some different socio-economic groups of Vietnamese population living in Hanoi, Hochiminh city Vinh Phu and Dalat areas. The obtained results showed that the average content for four elements (Cs, I, U, Th) in Vietnamese dietary intakes slightly changes from area to area in dependence on geographical, natural and socio-economical conditions, on type and composition of foods. (author)

  13. PRODUCTION OF ACTINIDE METAL

    Science.gov (United States)

    Knighton, J.B.

    1963-11-01

    A process of reducing actinide oxide to the metal with magnesium-zinc alloy in a flux of 5 mole% of magnesium fluoride and 95 mole% of magnesium chloride plus lithium, sodium, potassium, calcium, strontium, or barium chloride is presented. The flux contains at least 14 mole% of magnesium cation at 600-- 900 deg C in air. The formed magnesium-zinc-actinide alloy is separated from the magnesium-oxide-containing flux. (AEC)

  14. Superconductivity in the actinides

    International Nuclear Information System (INIS)

    Smith, J.L.; Lawson, A.C.

    1985-01-01

    The trends in the occurrence of superconductivity in actinide materials are discussed. Most of them seem to show simple transition metal behavior. However, the superconductivity of americium proves that the f electrons are localized in that element and that ''actinides'' is the correct name for this row of elements. Recently the superconductivity of UBe 13 and UPt 3 has been shown to be extremely unusual, and these compounds fall in the new class of compounds now known as heavy fermion materials

  15. Minor actinide transmutation using minor actinide burner reactors

    International Nuclear Information System (INIS)

    Mukaiyama, T.; Yoshida, H.; Gunji, Y.

    1991-01-01

    The concept of minor actinide burner reactor is proposed as an efficient way to transmute long-lived minor actinides in order to ease the burden of high-level radioactive waste disposal problem. Conceptual design study of minor actinide burner reactors was performed to obtain a reactor model with very hard neutron spectrum and very high neutron flux in which minor actinides can be fissioned efficiently. Two models of burner reactors were obtained, one with metal fuel core and the other with particle fuel core. Minor actinide transmutation by the actinide burner reactors is compared with that by power reactors from both the reactor physics and fuel cycle facilities view point. (author)

  16. Subsurface Biogeochemistry of Actinides

    Energy Technology Data Exchange (ETDEWEB)

    Kersting, Annie B. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States). Univ. Relations and Science Education; Zavarin, Mavrik [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States). Glenn T. Seaborg Inst.

    2016-06-29

    A major scientific challenge in environmental sciences is to identify the dominant processes controlling actinide transport in the environment. It is estimated that currently, over 2200 metric tons of plutonium (Pu) have been deposited in the subsurface worldwide, a number that increases yearly with additional spent nuclear fuel (Ewing et al., 2010). Plutonium has been shown to migrate on the scale of kilometers, giving way to a critical concern that the fundamental biogeochemical processes that control its behavior in the subsurface are not well understood (Kersting et al., 1999; Novikov et al., 2006; Santschi et al., 2002). Neptunium (Np) is less prevalent in the environment; however, it is predicted to be a significant long-term dose contributor in high-level nuclear waste. Our focus on Np chemistry in this Science Plan is intended to help formulate a better understanding of Pu redox transformations in the environment and clarify the differences between the two long-lived actinides. The research approach of our Science Plan combines (1) Fundamental Mechanistic Studies that identify and quantify biogeochemical processes that control actinide behavior in solution and on solids, (2) Field Integration Studies that investigate the transport characteristics of Pu and test our conceptual understanding of actinide transport, and (3) Actinide Research Capabilities that allow us to achieve the objectives of this Scientific Focus Area (SFA and provide new opportunities for advancing actinide environmental chemistry. These three Research Thrusts form the basis of our SFA Science Program (Figure 1).

  17. Actinide colloid generation in groundwater

    International Nuclear Information System (INIS)

    Kim, J.I.

    1990-05-01

    The progress made in the investigation of actinide colloid generation in groundwaters is summarized and discussed with particular examples relevant to an understanding of the migration behaviour of actinides in natural aquifer systems. The first part deals with the characterization of colloids: groundwater colloids, actinide real-colloids and actinide pseudocolloids. The second part concentrates on the generation processes and migration behaviour of actinide pseudocolloids, which are discussed with some notable experimental examples. Importance is stressed more on the chemical aspects of the actinide colloid generation in groundwater. This work is a contribution to the CEC project MIRAGE II, particularly, to research area: complexation and colloids. (orig.)

  18. Partitioning of Mercury from Actinides in the TRUEX Process

    International Nuclear Information System (INIS)

    Fiskum, Sandra K.; Rapko, Brian M.; Lumetta, Gregg J.

    2000-01-01

    A mercury complexant, L-cysteine hydrochloride, was tested for use in separating Hg from actinides during TRUEX processing of wastes at the Idaho National Engineering and Environmental Laboratory (INEEL). Mercury, americium, plutonium and uranyl distributions from TRUEX solvent were characterized over a nitric acid concentration range of 0.01 to 2 M. The applicability of cysteine was also evaluated for selective Hg complexation in an INEEL sodium-bearing waste simulant. A test was also conducted to evaluate the applicability of cysteine to separate Hg from Sr in the SREX process with Sr Resin used as a stand-in for the SREX process solvent. In all cases, the use of L-cysteine HCl retained Hg in the aqueous phase while causing no or little perturbation in the actinide and Sr distribution behavior

  19. Actinide isotopic analysis systems

    International Nuclear Information System (INIS)

    Koenig, Z.M.; Ruhter, W.D.; Gunnink, R.

    1990-01-01

    This manual provides instructions and procedures for using the Lawrence Livermore National Laboratory's two-detector actinide isotope analysis system to measure plutonium samples with other possible actinides (including uranium, americium, and neptunium) by gamma-ray spectrometry. The computer program that controls the system and analyzes the gamma-ray spectral data is driven by a menu of one-, two-, or three-letter options chosen by the operator. Provided in this manual are descriptions of these options and their functions, plus detailed instructions (operator dialog) for choosing among the options. Also provided are general instructions for calibrating the actinide isotropic analysis system and for monitoring its performance. The inventory measurement of a sample's total plutonium and other actinides content is determined by two nondestructive measurements. One is a calorimetry measurement of the sample's heat or power output, and the other is a gamma-ray spectrometry measurement of its relative isotopic abundances. The isotopic measurements needed to interpret the observed calorimetric power measurement are the relative abundances of various plutonium and uranium isotopes and americium-241. The actinide analysis system carries out these measurements. 8 figs

  20. Protactinium and the intersection of actinide and transition metal chemistry

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Richard E.; De Sio, Stephanie; Vallet, Valérie

    2018-02-12

    The role of the 5f and 6d orbitals in the chemistry of the actinide elements has been of considerable interest since their discovery and synthesis. Relativistic effects cause the energetics of the 5f and 6d orbitals to change as the actinide series is traversed left to right imparting a rich and complex chemistry. The 5f and 6d atomic states cross in energy at protactinium (Pa), making it a potential intersection between transition metal and actinide chemistries. Herein, we report the synthesis of a Pa-peroxo cluster, A(6)(Pa4O(O-2)(6)F-12) [A = Rb, Cs, (CH3)(4)N], formed in pursuit of an actinide polyoxometalate. Quantum chemical calculations at the density functional theory level demonstrate equal 5f and 6d orbital participation in the chemistry of Pa and increasing 5f orbital participation for the heavier actinides. Periodic changes in orbital character to the bonding in the early actinides highlights the influence of the 5f orbitals in their reactivity and chemical structure.

  1. Evaluation algorithm for Hp (10), Hp (0.07) and response matrix in mixed fields of 137Cs+90Sr/90Y for badge TLD without use of its commercial holder

    International Nuclear Information System (INIS)

    Alvarez R, Jose T.; Tovar M, Victor M.; Castaneda P, Mario; Padilla, Ismael

    2008-01-01

    American standards HPS N 13.11 (1993, 2001) set up performance category tests for deep and shallow personal equivalent dose evaluated by dosimetry processors. These standards establish the parameters bias B, standard deviation S and tolerance level L, whose values indicate the deviations from the conventionally true value for the equivalent dose. On the other hand, for a right evaluation of the equivalent dose, all personal dosimetry systems have four basic components: badge, holder, reading protocol and dose evaluation algorithm. However, in Nuclear Plant Laguna Verde NPP dosimetry laboratory uses the badges Panasonic 802 A without Panasonic UD874AT holder, and instead employs a polyethylene holder bag to protect the badge from misuse. This situation disables the manufacturer algorithm designed for the combination: badge + holder. Therefore, the purpose of this work is to design a personal equivalent dose algorithm for this badge + bag, such this corrected algorithm let fulfill the HPS N 13.11 (1993) categories II, IV, V and VII. The algorithm starts from the readings of the elements: E1, E2, E3 and E4, only corrected by their element correction factor ECF. Additionally, we characterize the badge + bag by means of the response function for: 137 Cs, 85 Kr and 90 Sr/ 90 Y radiation fields. Finally, for validation of the algorithm one verifies that parameters B, S and L accomplish with the limits indicated by the standard. (author)

  2. Extraction chromatography of actinides

    International Nuclear Information System (INIS)

    Muller, W.

    1978-01-01

    Extraction chromatography of actinides in the oxidation state from 2 to 6 is reviewed. Data on using neutral (tbp), basic (substituted ammonium salts) and acidic [di-(2-ethylhexyl)-phosphoric acid (D2EHPA)] extracting agents ketones, esters, alcohols and β-diketones in this method are given. Using the example of actinide separation using D2EHPA, discussed are factors influencing the efficiency of their chromatography separation (nature and particle size of the carrier materials, extracting agents amount on the carrier, temperature and elution rate)

  3. Actinide nanoparticle research

    International Nuclear Information System (INIS)

    Kalmykov, Stepan N.; Denecke, Melissa A.

    2011-01-01

    This is the first book to cover actinide nano research. It is of interest both for fundamental research into the chemistry and physics of f-block elements as well as for applied researchers such as those studying the long-term safety of nuclear waste disposal and developing remediation strategies. The authors cover important issues of the formation of actinide nano-particles, their properties and structure, environmental behavior of colloids and nanoparticles related to the safe disposal of nuclear wastes, modeling and advanced methods of characterization at the nano-scale. (orig.)

  4. Radiochemistry and actinide chemistry

    International Nuclear Information System (INIS)

    Guillaumont, R.; Peneloux, A.

    1989-01-01

    The analysis of trace amounts of actinide elements by means of radiochemistry, is discussed. The similarities between radiochemistry and actinide chemistry, in the case of species amount by cubic cm below 10 12 , are explained. The parameters which allow to define what are the observable chemical reactions, are given. The classification of radionuclides in micro or macrocomponents is considered. The validity of the mass action law and the partition function in the definition of the average number of species for trace amounts, is investigated. Examples illustrating the results are given

  5. Actinides, the narrowwest bands

    International Nuclear Information System (INIS)

    Smith, J.L.; Riseborough, P.S.

    1984-01-01

    A table of elements is shown that demonstrates the crossover from superconductivity to magnetism as well as regions of mixed valence. In particular, the actinides must eventually show 4f-electron like mixed valence, after the 5f-electrons become localized. There also seems to be an adiabatic continuation between heavy fermion and mixed valence behavior

  6. Actinide separative chemistry

    International Nuclear Information System (INIS)

    Boullis, B.

    2004-01-01

    Actinide separative chemistry has focused very heavy work during the last decades. The main was nuclear spent fuel reprocessing: solvent extraction processes appeared quickly a suitable, an efficient way to recover major actinides (uranium and plutonium), and an extensive research, concerning both process chemistry and chemical engineering technologies, allowed the industrial development in this field. We can observe for about half a century a succession of Purex plants which, if based on the same initial discovery (i.e. the outstanding properties of a molecule, the famous TBP), present huge improvements at each step, for a large part due to an increased mastery of the mechanisms involved. And actinide separation should still focus R and D in the near future: there is a real, an important need for this, even if reprocessing may appear as a mature industry. We can present three main reasons for this. First, actinide recycling appear as a key-issue for future nuclear fuel cycles, both for waste management optimization and for conservation of natural resource; and the need concerns not only major actinide but also so-called minor ones, thus enlarging the scope of the investigation. Second, extraction processes are not well mastered at microscopic scale: there is a real, great lack in fundamental knowledge, useful or even necessary for process optimization (for instance, how to design the best extracting molecule, taken into account the several notifications and constraints, from selectivity to radiolytic resistivity?); and such a need for a real optimization is to be more accurate with the search of always cheaper, cleaner processes. And then, there is room too for exploratory research, on new concepts-perhaps for processing quite new fuels- which could appear attractive and justify further developments to be properly assessed: pyro-processes first, but also others, like chemistry in 'extreme' or 'unusual' conditions (supercritical solvents, sono-chemistry, could be

  7. Actinide oxide photodiode and nuclear battery

    Energy Technology Data Exchange (ETDEWEB)

    Sykora, Milan; Usov, Igor

    2017-12-05

    Photodiodes and nuclear batteries may utilize actinide oxides, such a uranium oxide. An actinide oxide photodiode may include a first actinide oxide layer and a second actinide oxide layer deposited on the first actinide oxide layer. The first actinide oxide layer may be n-doped or p-doped. The second actinide oxide layer may be p-doped when the first actinide oxide layer is n-doped, and the second actinide oxide layer may be n-doped when the first actinide oxide layer is p-doped. The first actinide oxide layer and the second actinide oxide layer may form a p/n junction therebetween. Photodiodes including actinide oxides are better light absorbers, can be used in thinner films, and are more thermally stable than silicon, germanium, and gallium arsenide.

  8. Comparative concentrations of 137Cs, 90Sr, /sup 239,240/Pu, and 241Am in tissues of fish from the Marshall Islands and calculated dose commitments from their consumption

    International Nuclear Information System (INIS)

    Noshkin, V.E.; Wong, K.M.; Eagle, R.J.; Robison, W.L.

    1987-01-01

    Body burdens of 90 Sr, 137 Cs, and the transuranics in bottom-feeding fish from Marshall Island atolls are derived, in part, from the quantities of the radionuclides irreversibly fixed to ingested carbonate material. Radionuclide concentration factors for different species of fish are characterized by relating tissue concentrations to those in filtered seawater. For bottom-feeding fish, the values are lower at the lesser contaminated atolls than those values determined for the same species at the more contaminated atolls. These fish have the ability to lower their gut pH during feeding. When this occurs, there is a dissolution of a fraction of the ingested calcium carbonate containing radionuclides that were fixed or fused internally to the material during nuclear testing. Fractions of the radionuclides released during solution in carbonate matrix are available for passage across the gut wall. Amounts released to solution in the gut are proportional to the levels of contamination at the different atolls. Concentration factors for higher trophic level species, which do not rely on sediments or coral for their source of food, show no such trends between differentially contaminated atolls. A two-source model used to compute the internal concentrations is described. Americium-241 seems to be more biologically available than /sup 239,240/Pu to higher trophic level species from the lagoons, whereas at lower trophic levels the opposite seems to be the case. Cesium-137 is now the largest contributor of the small radiological dose to man from the marine fish pathway, with the transuranics contributing from 2 to 30% of the total dose. 22 references, 1 figure, 19 tables

  9. Actinide recycling in reactors

    International Nuclear Information System (INIS)

    Kuesters, H.; Wiese, H.W.; Krieg, B.

    1995-01-01

    The objective is an assessment of the transmutation of long-lived actinides and fission products and the incineration of plutonium for reducing the risk potential of radioactive waste from reactors in comparison to direct waste disposal. The contribution gives an interim account on homogeneous and heterogeneous recycling of 'risk nuclides' in thermal and fast reactors. Important results: - A homogeneous 5 percent admixture of minor actinides (MA) from N4-PWRs to EFR fuel would allow a transmutation not only of the EFR MA, but in addition of the MA from 5 or 6 PWRs of equal power. However, the incineration is restricted by safety considerations. - LWR have only a very low MA incineration potential, due to their disadvantageous neutron capture/fission ratio. - In order to keep the Cm inventory at a low level, it is advantageous to concentrate the Am heterogeneously in particular fuel elements or rods. (orig./HP)

  10. Photochemistry of the actinides

    International Nuclear Information System (INIS)

    Toth, L.M.; Bell, J.T.; Friedman, H.A.

    1979-01-01

    It has been found that all three major actinides have a useful variety of photochemical reactions which could be used to achieve a separations process that requires fewer reagents. Several features merit enumerating: (1) Laser photochemistry is not now as uniquely important in fuel reprocessing as it is in isotopic enrichment. The photochemistry can be successfully accomplished with conventional light sources. (2) The easiest place to apply photo-reprocessing is on the three actinides U, Pu, and Np. The solutions are potentially cleaner and more amenable to photoreactions. (3) Organic-phase photoreactions are probably not worth much attention because of the troublesome solvent redox chemistry associated with the photochemical reaction. (4) Upstream process treatment on the raffinate (dissolver solution) may never be too attractive since the radiation intensity precludes the usage of many optical materials and the nature of the solution is such that light transmission into it might be totally impossible

  11. Analytical chemistry of actinides

    International Nuclear Information System (INIS)

    Chollet, H.; Marty, P.

    2001-01-01

    Different characterization methods specifically applied to the actinides are presented in this review such as ICP/OES (inductively coupled plasma-optical emission spectrometry), ICP/MS (inductively coupled plasma spectroscopy-mass spectrometry), TIMS (thermal ionization-mass spectrometry) and GD/OES (flow discharge optical emission). Molecular absorption spectrometry and capillary electrophoresis are also available to complete the excellent range of analytical tools at our disposal. (authors)

  12. Actinides: why are they important biologically

    International Nuclear Information System (INIS)

    Durbin, P.W.

    1978-01-01

    The following topics are discussed: actinide elements in energy systems; biological hazards of the actinides; radiation protection standards; and purposes of actinide biological research with regard to toxicity, metabolism, and therapeutic regimens

  13. Actinide science with soft x-ray synchrotron radiation

    International Nuclear Information System (INIS)

    Shuh, D.

    2002-01-01

    Several workshops, some dating back more than fifteen years, recognised both the potential scientific impact and opportunities that would be made available by the capability to investigate actinide materials in the vacuum ultraviolet (VUV)/soft X-ray region of the synchrotron radiation (SR) spectrum. This spectral region revolutionized the approach to surface materials chemistry and physics nearly two decades ego. The actinide science community was unable to capitalize on these SR methodologies for the study of actinide materials until recently because of radiological safety concerns. ,The Advanced Light Source (ALS) at LBNL is a third-generation light source providing state-of-the-art performance in the VUV/soft X-ray region. Along with corresponding improvements in detector and vacuum technology, the ALS has rendered experiments with small amounts of actinide materials possible. In particular, it has been the emergence and development of micro-spectroscopic techniques that have enabled investigations of actinide materials at the ALS. The primary methods for the experimental investigation of actinide materials in the VUV/soft X-ray region are the complementary photoelectron spectroscopies, near-edge X-ray absorption fine structure (NEXAFS) and X-ray emission spectroscopy (XES) techniques. Resonant photo-emission is capable of resolving the 5f electron contributions to actinide bonding and can be used to characterise the electronic structure of actinide materials. This technique is clearly a most important methodology afforded by the tunable SR source. Core level and valence band photoelectron spectroscopies are valuable for the characterisation of the electronic properties of actinide materials, as well as for general analytical purposes. High-resolution core-level photo-emission and resonant photo-emission measurements from the a (monoclinic) and δ (FCC) allotropic phases of plutonium metal have been collected on beam line 7.0 at the ALS and the spectra show

  14. Diglycolamide based dendrimers for sequestration of trivalent actinides: solvent extraction and liquid membrane studies

    International Nuclear Information System (INIS)

    Ansari, S.A.; Mohapatra, P.K.; Leoncini, A.; Verboom, W.

    2017-01-01

    Three diglycolamide-functionalized (poly(propylene imine)) diaminobutane dendrimers, viz. zero generation (L_I), first generation (L_I_I), and second generation (L_I_I_I), were synthesized and evaluated for their extraction ability towards trivalent actinides. The distribution ratio (D) of Am"3"+ with 1.0 mmol/L ligand at 3 M HNO_3 followed the order: 0.1 (L_I) < 42 (L_I_I) < 110 (L_I_I_I). The D values of Am(_I_I_I) at lower acidity (0.01 M HNO_3) were significantly low, giving good stripping option with the dilute acid solution. Extraction of other metal ions from 3 M HNO_3 indicated good selectivity of Am(III) over U(VI), Sr(II) and Cs(I). Supported liquid membrane (SLM) studies were explored for the transport of Am(III) from acidic feed solution, where ligand inventory is extremely low. (author)

  15. Thermal neutron actinide data

    International Nuclear Information System (INIS)

    Tellier, H.

    1992-01-01

    During the 70's, the physicists involved in the cross section measurements for the low energy neutrons were almost exclusively interested in the resonance energy range. The thermal range was considered as sufficiently known. In the beginning of the 80's, reactor physicists had again to deal with the delicate problem of the power reactor temperature coefficient, essentially for the light water reactors. The measured value of the reactivity temperature coefficient does not agree with the computed one. The later is too negative. For obvious safety reasons, it is an important problem which must be solved. Several causes were suggested to explain this discrepancy. Among all these causes, the spectral shift in the thermal energy range seems to be very important. Sensibility calculations shown that this spectral shift is very sensitive to the shape of the neutron cross sections of the actinides for energies below one electron-volt. Consequently, reactor physicists require new and accurate measurements in the thermal and subthermal energy ranges. A part of these new measurement results were recently released and reviewed. The purpose of this study is to complete the preceding review with the new informations which are now available. In reactor physics the major actinides are the fertile nuclei, uranium 238, thorium 232 and plutonium 240 and the fissile nuclei, uranium 233, uranium 235 and plutonium 239. For the fertile nuclei the main datum is the capture cross section, for the fissile nuclei the data of interest are nu-bar, the fission and capture cross sections or a combination of these data such as η or α. In the following sections, we will review the neutron data of the major actinides for the energy below 1 eV

  16. Actinide Separation Demonstration Facility, Tarapur

    International Nuclear Information System (INIS)

    Vishwaraj, I.

    2017-01-01

    Partitioning of minor actinide from high level waste could have a substantial impact in lowering the radio toxicity associated with high level waste as well as it will reduce the burden on geological repository. In Indian context, the partitioned minor actinide could be routed into the fast breeder reactor systems scheduled for commissioning in the near period. The technological breakthrough in solvent development has catalyzed the partitioning programme in India, leading to the setting up and hot commissioning of the Actinide Separation Demonstration Facility (ASDF) at BARC, Tarapur. The engineering scale Actinide Separation Demonstration Facility (ASDF) has been retrofitted in an available radiological hot cell situated adjacent to the Advanced Vitrification Facility (AVS). This location advantage ensures an uninterrupted supply of high-level waste and facilitates the vitrification of the high-level waste after separation of minor actinides

  17. Recovery actinide values

    International Nuclear Information System (INIS)

    Horwitz, E.P.; Delphin, W.H.; Mason, G.W.

    1979-01-01

    A process is described for partitioning and recovering actinide values from acidic waste solutions resulting from reprocessing of irradiated nuclear fuels by adding hydroxylammonium nitrate and hydrazine to the waste solution to adjust the valence of the neptunium and plutonium values in the solution to the +4 oxidation state, thus forming a feed solution and contacting the feed solution with an extractant of di-hexoxyethyl phosphoric acid in an organic diluent whereby the actinide values, most of the rare earth values and some fission product values are taken up by the extractant. Separation is achieved by contacting the loaded extractant with two aqueous strip solutions, a nitric acid solution to selectively strip the americium, curium and rare earth values and an oxalate solution of tetramethylammonium hydrogen oxalate and oxalic acid or trimethylammonium hydrogen oxalate to selectively strip the neptunium, plutonium and fission product values. Uranium values remain in the extractant and may be recovered with a phosphoric acid strip. The neptunium and plutonium values are recovered from the oxalate by adding sufficient nitric acid to destroy the complexing ability of the oxalate, forming a second feed, and contacting the second feed with a second extractant of tricaprylmethylammonium nitrate in an inert diluent whereby the neptunium and plutonium values are selectively extracted. The values are recovered from the extractant with formic acid. (author)

  18. Actinide AMS at DREAMS

    Energy Technology Data Exchange (ETDEWEB)

    Khojasteh, Nasrin B.; Merchel, Silke; Rugel, Georg; Scharf, Andreas; Ziegenruecker, Rene [HZDR, Dresden (Germany); Pavetich, Stefan [HZDR, Dresden (Germany); ANU, Canberra (Australia)

    2016-07-01

    Radionuclides such as {sup 236}U and {sup 239}Pu were introduced into the environment by atmospheric nuclear weapon tests, reactor accidents (Chernobyl, Fukushima), releases from nuclear reprocessing facilities (Sellafield, La Hague), radioactive waste disposal, and accidents with nuclear devices (Palomares, Thule) [1]. Accelerator Mass Spectrometry (AMS) is the most sensitive method to measure these actinides. The DREsden AMS (DREAMS) facility is located at a 6 MV accelerator, which is shared with ion beam analytics and implantation users, preventing major modifications of the accelerator and magnetic analyzers. DREAMS was originally designed for {sup 10}Be, {sup 26}Al, {sup 36}Cl, {sup 41}Ca, and {sup 129}I. To modify the system for actinide AMS, a Time-of-Flight (TOF) beamline at the high-energy side has been installed and performance tests are on-going. Ion beam and detector simulations are carried out to design a moveable ionization chamber. Especially, the detector window and anode dimensions have to be optimized. This ionization chamber will act as an energy detector of the system and its installation is planned as closely as possible to the stop detector of the TOF beamline for highest detection efficiency.

  19. Rare earths and actinides

    International Nuclear Information System (INIS)

    Coqblin, B.

    1982-01-01

    This paper reviews the different properties of rare-earths and actinides, either as pure metals or as in alloys or compounds. Three different cases are considered: (i) First, in the case of 'normal' rare-earths which are characterized by a valence of 3, we discuss essentially the magnetic ordering, the coexistence between superconductivity and magnetism and the properties of amorphous rare-earth systems. (ii) Second, in the case of 'anomalous' rare-earths, we distinguish between either 'intermediate-valence' systems or 'Kondo' systems. Special emphasis is given to the problems of the 'Kondo lattice' (for compounds such as CeAl 2 ,CeAl 3 or CeB 6 ) or the 'Anderson lattice' (for compounds such as TmSe). The problem of neutron diffraction in these systems is also discussed. (iii) Third, in the case of actinides, we can separate between the d-f hybridized and almost magnetic metals at the beginning of the series and the rare-earth like the metals after americium. (orig.)

  20. Concentration of actinides in the food chain

    International Nuclear Information System (INIS)

    Bulman, R.A.

    1976-06-01

    Considerable concern is now being expressed over the discharge of actinides into the environment. This report presents a brief review of the chemistry of the actinides and examines the evidence for interaction of the actinides with some naturally-occurring chelating agents and other factors which might stimulate actinide concentration in the food chain of man. This report also reviews the evidence for concentration of actinides in plants and for uptake through the gastrointestinal tract. (author)

  1. Lanthanide/Actinide Opacities

    Science.gov (United States)

    Hungerford, Aimee; Fontes, Christopher J.

    2018-06-01

    Gravitational wave observations benefit from accompanying electromagnetic signals in order to accurately determine the sky positions of the sources. The ejecta of neutron star mergers are expected to produce such electromagnetic transients, called macronovae (e.g. the recent and unprecedented observation of GW170817). Characteristics of the ejecta include large velocity gradients and the presence of heavy r-process elements, which pose significant challenges to the accurate calculation of radiative opacities and radiation transport. Opacities include a dense forest of bound-bound features arising from near-neutral lanthanide and actinide elements. Here we present an overview of current theoretical opacity determinations that are used by neutron star merger light curve modelers. We will touch on atomic physics and plasma modeling codes that are used to generate these opacities, as well as the limited body of laboratory experiments that may serve as points of validation for these complex atomic physics calculations.

  2. Relativistic studies in actinides

    International Nuclear Information System (INIS)

    Weinberger, P.; Gonis, A.

    1987-01-01

    In this review the theoretical background is given for a relativistic description for actinide systems. A short introduction is given of the density functional theory which forms the basis for a fully relativistic single-particle theory. A section on the Dirac Hamiltonian is followed by a brief summary on group theoretical concepts. Single site scattering is presented such that formal extensions to the case of the presence of an internal (external) magnetic field and/or anisotropic scattering are evident. Multiple scattering is discussed such that it can readily be applied also to the problem of dislocations. In connection with the problem of selfconsistency particular attention is drawn to the use of complex energies. Finally the various theoretical aspects discussed are illustrated through the results of numerical calculations. 101 refs.; 37 figs.; 5 tabs

  3. Projected benefits of actinide partitioning

    International Nuclear Information System (INIS)

    Braun, C.; Goldstein, M.

    1976-05-01

    Possible benefits that could accrue from actinide separation and transmutations are presented. The time frame for implementing these processes is discussed and the expected benefits are qualitatively described. These benefits are provisionally quantified in a sample computation

  4. Environmental research on actinide elements

    International Nuclear Information System (INIS)

    Pinder, J.E. III; Alberts, J.J.; McLeod, K.W.; Schreckhise, R.G.

    1987-08-01

    The papers synthesize the results of research sponsored by DOE's Office of Health and Environmental Research on the behavior of transuranic and actinide elements in the environment. Separate abstracts have been prepared for the 21 individual papers

  5. Properties of minor actinide nitrides

    International Nuclear Information System (INIS)

    Takano, Masahide; Itoh, Akinori; Akabori, Mitsuo; Arai, Yasuo; Minato, Kazuo

    2004-01-01

    The present status of the research on properties of minor actinide nitrides for the development of an advanced nuclear fuel cycle based on nitride fuel and pyrochemical reprocessing is described. Some thermal stabilities of Am-based nitrides such as AmN and (Am, Zr)N were mainly investigated. Stabilization effect of ZrN was cleary confirmed for the vaporization and hydrolytic behaviors. New experimental equipments for measuring thermal properties of minor actinide nitrides were also introduced. (author)

  6. Actinide colloid generation in groundwater. Part 2

    International Nuclear Information System (INIS)

    Kim, J.I.

    1991-01-01

    The progress made in the investigation of actinide colloid generation in groundwater is summarized and discussed with particular examples relevant to an understanding of the migration behaviour of actinides in natural aquifer systems. The first part deals with the characterization of colloids: groundwater colloids, actinide real-colloids and actinide pseudocolloids. The second part concentrates on the generation processes and migration behaviour of actinide pseudo colloids, which are discussed with some notable experimental examples. Importance is stressed more on the chemical aspects of the actinide colloid generation in groundwater. This work is a contribution to the CEC Mirage II project, in particular the complexation and colloids research area

  7. Actinides and heavy fermions

    International Nuclear Information System (INIS)

    Smith, J.L.; Fisk, Z.; Ott, H.R.

    1987-01-01

    The actinide series of elements begins with f-shell electrons forming energy bands, contributing to the bonding, and possessing no magnetic moments. At americium the series switches over to localized f electrons with magnetic moments. In metallic compounds this crossover of behavior can be modified and studied. In this continuum of behavior a few compounds on the very edge of localized f-electron behavior exhibit enormous electronic heat capacities at low temperatures. This is associated with an enhanced thermal mass of the conduction electrons, which is well over a hundred times the free electron mass, and is what led to the label heavy fermion for such compounds. A few of these become superconducting at even lower temperatures. The excitement in this field comes from attempting to understand how this heaviness arises and from the likelihood that the superconductivity is different from that of previously known superconductors. The effects of thorium impurities in UBe 13 were studied as a representative system for studying the nature of the superconductivity

  8. Actinide burning and waste disposal

    Energy Technology Data Exchange (ETDEWEB)

    Pigford, T H [University of California, Berkeley, CA (United States)

    1990-07-01

    Here we review technical and economic features of a new proposal for a synergistic waste-management system involving reprocessing the spent fuel otherwise destined for a U.S. high-level waste repository and transmuting the recovered actinides in a fast reactor. The proposal would require a U.S. fuel reprocessing plant, capable of recovering and recycling all actinides, including neptunium americium, and curium, from LWR spent fuel, at recoveries of 99.9% to 99.999%. The recovered transuranics would fuel the annual introduction of 14 GWe of actinide-burning liquid-metal fast reactors (ALMRs), beginning in the period 2005 to 2012. The new ALMRs would be accompanied by pyrochemical reprocessing facilities to recover and recycle all actinides from discharged ALMR fuel. By the year 2045 all of the LWR spent fuel now destined f a geologic repository would be reprocessed. Costs of constructing and operating these new reprocessing and reactor facilities would be borne by U.S. industry, from the sale of electrical energy produced. The ALMR program expects that ALMRs that burn actinides from LWR spent fuel will be more economical power producers than LWRs as early as 2005 to 2012, so that they can be prudently selected by electric utility companies for new construction of nuclear power plants in that era. Some leaders of DOE and its contractors argue that recovering actinides from spent fuel waste and burning them in fast reactors would reduce the life of the remaining waste to about 200-300 years, instead of 00,000 years. The waste could then be stored above ground until it dies out. Some argue that no geologic repositories would be needed. The current view expressed within the ALMR program is that actinide recycle technology would not replace the need for a geologic repository, but that removing actinides from the waste for even the first repository would simplify design and licensing of that repository. A second geologic repository would not be needed. Waste now planned

  9. Actinide speciation in the environment

    International Nuclear Information System (INIS)

    Choppin, G.R.

    2007-01-01

    Nuclear test explosions and nuclear reactor wastes and accidents have released large amounts of radioactivity into the environment. Actinide ions in waters often are not in a state of thermodynamic equilibrium and their solubility and migration behavior is related to the form in which the nuclides are introduced into the aquatic system. Chemical speciation, oxidation state, redox reactions, and sorption characteristics are necessary in predicting solubility of the different actinides, their migration behaviors and their potential effects on marine biota. The most significant of these variables is the oxidation state of the metal ion as the simultaneous presence of more than one oxidation state for some actinides in a solution complicates actinide environmental behavior. Both Np(V)O 2 + and Pu(V)O 2 + , the most significant soluble states in natural oxic waters, are relatively noncomplexing and resistant to hydrolysis and subsequent precipitation. The solubility of NpO 2 + can be as high as 10 -4 M while that of PuO 2 + is much more limited by reduction to the insoluble tetravalent species, Pu(OH) 4 , (pK sp ≥56) but which can be present in the pentavalent form in aqautic phases as colloidal material. The solubility of hexavalent UO 2 2+ in sea water is relatively high due to formation of carbonate complexes. The insoluble trivalent americium hydroxocarbonate, Am(OH)(CO 3 ) is the limiting species for the solubility of Am(III) in sea water. Thorium(IV) is present as Th(OH) 4 , in colloidal form. The chemistry of actinide ions in the environment is reviewed to show the spectrum of reactions that can occur in natural waters which must be considered in assessing the environmental behavior of actinides. Much is understood about sorption of actinides on surfaces, the mode of migration of actinides in such waters and the potential effects of these radioactive species on marine biota, but much more understanding of the behavior of the actinides in the environment is

  10. Actinide burning and waste disposal

    International Nuclear Information System (INIS)

    Pigford, T.H.

    1990-01-01

    Here we review technical and economic features of a new proposal for a synergistic waste-management system involving reprocessing the spent fuel otherwise destined for a U.S. high-level waste repository and transmuting the recovered actinides in a fast reactor. The proposal would require a U.S. fuel reprocessing plant, capable of recovering and recycling all actinides, including neptunium americium, and curium, from LWR spent fuel, at recoveries of 99.9% to 99.999%. The recovered transuranics would fuel the annual introduction of 14 GWe of actinide-burning liquid-metal fast reactors (ALMRs), beginning in the period 2005 to 2012. The new ALMRs would be accompanied by pyrochemical reprocessing facilities to recover and recycle all actinides from discharged ALMR fuel. By the year 2045 all of the LWR spent fuel now destined f a geologic repository would be reprocessed. Costs of constructing and operating these new reprocessing and reactor facilities would be borne by U.S. industry, from the sale of electrical energy produced. The ALMR program expects that ALMRs that burn actinides from LWR spent fuel will be more economical power producers than LWRs as early as 2005 to 2012, so that they can be prudently selected by electric utility companies for new construction of nuclear power plants in that era. Some leaders of DOE and its contractors argue that recovering actinides from spent fuel waste and burning them in fast reactors would reduce the life of the remaining waste to about 200-300 years, instead of 00,000 years. The waste could then be stored above ground until it dies out. Some argue that no geologic repositories would be needed. The current view expressed within the ALMR program is that actinide recycle technology would not replace the need for a geologic repository, but that removing actinides from the waste for even the first repository would simplify design and licensing of that repository. A second geologic repository would not be needed. Waste now planned

  11. NEW METHOD FOR DETERMINATION OF ACTINIDES AND STRONTIUM IN ANIMAL TISSUE

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S; Jay Hutchison, J; Don Faison, D

    2007-05-07

    The analysis of actinides in animal tissue samples is very important for environmental monitoring. There is a need to measure actinide isotopes with very low detection limits in animal tissue samples, including fish, deer, hogs, beef and shellfish. A new, rapid actinide separation method has been developed and implemented that allows the measurement of plutonium, neptunium, uranium, americium, curium and strontium isotopes in large animal tissue samples (100-200 g) with high chemical recoveries and effective removal of matrix interferences. This method uses stacked TEVA Resin{reg_sign}, TRU Resin{reg_sign} and DGA-Resin{reg_sign} cartridges from Eichrom Technologies (Darien, IL, USA) that allows the rapid separation of plutonium (Pu), neptunium (Np), uranium (U), americium (Am), and curium (Cm) using a single multi-stage column combined with alpha spectrometry. Sr-90 is collected on Sr Resin{reg_sign} from Eichrom Technologies (Darien, IL, USA). After acid digestion and furnace heating of the animal tissue samples, the actinides and Sr-89/90 are separated using column extraction chromatography. This method has been shown to be effective over a wide range of animal tissue matrices. By using vacuum box cartridge technology with rapid flow rates, sample preparation time is minimized.

  12. 33rd Actinide Separations Conference

    Energy Technology Data Exchange (ETDEWEB)

    McDonald, L M; Wilk, P A

    2009-05-04

    Welcome to the 33rd Actinide Separations Conference hosted this year by the Lawrence Livermore National Laboratory. This annual conference is centered on the idea of networking and communication with scientists from throughout the United States, Britain, France and Japan who have expertise in nuclear material processing. This conference forum provides an excellent opportunity for bringing together experts in the fields of chemistry, nuclear and chemical engineering, and actinide processing to present and discuss experiences, research results, testing and application of actinide separation processes. The exchange of information that will take place between you, and other subject matter experts from around the nation and across the international boundaries, is a critical tool to assist in solving both national and international problems associated with the processing of nuclear materials used for both defense and energy purposes, as well as for the safe disposition of excess nuclear material. Granlibakken is a dedicated conference facility and training campus that is set up to provide the venue that supports communication between scientists and engineers attending the 33rd Actinide Separations Conference. We believe that you will find that Granlibakken and the Lake Tahoe views provide an atmosphere that is stimulating for fruitful discussions between participants from both government and private industry. We thank the Lawrence Livermore National Laboratory and the United States Department of Energy for their support of this conference. We especially thank you, the participants and subject matter experts, for your involvement in the 33rd Actinide Separations Conference.

  13. 33rd Actinide Separations Conference

    International Nuclear Information System (INIS)

    McDonald, L.M.; Wilk, P.A.

    2009-01-01

    Welcome to the 33rd Actinide Separations Conference hosted this year by the Lawrence Livermore National Laboratory. This annual conference is centered on the idea of networking and communication with scientists from throughout the United States, Britain, France and Japan who have expertise in nuclear material processing. This conference forum provides an excellent opportunity for bringing together experts in the fields of chemistry, nuclear and chemical engineering, and actinide processing to present and discuss experiences, research results, testing and application of actinide separation processes. The exchange of information that will take place between you, and other subject matter experts from around the nation and across the international boundaries, is a critical tool to assist in solving both national and international problems associated with the processing of nuclear materials used for both defense and energy purposes, as well as for the safe disposition of excess nuclear material. Granlibakken is a dedicated conference facility and training campus that is set up to provide the venue that supports communication between scientists and engineers attending the 33rd Actinide Separations Conference. We believe that you will find that Granlibakken and the Lake Tahoe views provide an atmosphere that is stimulating for fruitful discussions between participants from both government and private industry. We thank the Lawrence Livermore National Laboratory and the United States Department of Energy for their support of this conference. We especially thank you, the participants and subject matter experts, for your involvement in the 33rd Actinide Separations Conference.

  14. Study on the leaching behavior of actinides from nuclear fuel debris

    Science.gov (United States)

    Kirishima, Akira; Hirano, Masahiko; Akiyama, Daisuke; Sasaki, Takayuki; Sato, Nobuaki

    2018-04-01

    For the prediction of the leaching behavior of actinides contained in the nuclear fuel debris generated by the Fukushima Daiichi nuclear power plant accident in Japan, simulated fuel debris consisting of a UO2-ZrO2 solid solution doped with 137Cs, 237Np, 236Pu, and 241Am tracers was synthesized and investigated. The synthesis of the debris was carried out by heat treatment at 1200 °C at different oxygen partial pressures, and the samples were subsequently used for leaching tests with Milli-Q water and seawater. The results of the leaching tests indicate that the leaching of actinides depends on the redox conditions under which the debris was generated; for example, debris generated under oxidative conditions releases more actinide nuclides to water than that generated under reductive conditions. Furthermore, we found that, as Zr(IV) increasingly substituted U(IV) in the fluorite crystal structure of the debris, the actinide leaching from the debris decreased. In addition, we found that seawater leached more actinides from the debris than pure water, which seems to be caused by the complexation of actinides by carbonate ions in seawater.

  15. Thermal-hydraulics of actinide burner reactors

    International Nuclear Information System (INIS)

    Takizuka, Takakazu; Mukaiyama, Takehiko; Takano, Hideki; Ogawa, Toru; Osakabe, Masahiro.

    1989-07-01

    As a part of conceptual study of actinide burner reactors, core thermal-hydraulic analyses were conducted for two types of reactor concepts, namely (1) sodium-cooled actinide alloy fuel reactor, and (2) helium-cooled particle-bed reactor, to examine the feasibility of high power-density cores for efficient transmutation of actinides within the maximum allowable temperature limits of fuel and cladding. In addition, calculations were made on cooling of actinide fuel assembly. (author)

  16. Fusion barrier characteristics of actinides

    Science.gov (United States)

    Manjunatha, H. C.; Sridhar, K. N.

    2018-03-01

    We have studied fusion barrier characteristics of actinide compound nuclei with atomic number range 89 ≤ Z ≤ 103 for all projectile target combinations. After the calculation of fusion barrier heights and positions, we have searched for their parameterization. We have achieved the empirical formula for fusion barrier heights (VB), positions (RB), curvature of the inverted parabola (ħω) of actinide compound nuclei with atomic number range 89 ≤ Z ≤ 103 for all projectile target combinations (6 projectile target combinations. The values produced by the present formula are also compared with experiments. The present pocket formula produces fusion barrier characteristics of actinides with the simple inputs of mass number (A) and atomic number (Z) of projectile-targets.

  17. ALMR potential for actinide consumption

    International Nuclear Information System (INIS)

    Cockey, C.L.; Thompson, M.L.

    1992-01-01

    The Advanced Liquid Metal Reactor (ALMR) is a US Department of Energy (DOE) sponsored fast reactor design based on the Power Reactor, Innovative Small Module (PRISM) concept originated by General Electric. This reactor combines a high degree of passive safety characteristics with a high level of modularity and factory fabrication to achieve attractive economics. The current reference design is a 471 MWt modular reactor fueled with ternary metal fuel. This paper discusses actinide transmutation core designs that fit the design envelope of the ALMR and utilize spent LWR fuel as startup material and for makeup. Actinide transmutation may be accomplished in the ALMR core by using either a breeding or burning configuration. Lifetime actinide mass consumption is calculated as well as changes in consumption behavior throughout the lifetime of the reactor. Impacts on system operational and safety performance are evaluated in a preliminary fashion. Waste disposal impacts are discussed. (author)

  18. Thin layers in actinide research

    International Nuclear Information System (INIS)

    Gouder, T.

    1998-01-01

    Surface science research at the ITU is focused on the synthesis and surface spectroscopy studies of thin films of actinides and actinide compounds. The surface spectroscopies used are X-ray and ultra violet photoelectron spectroscopy (XPS and UPS, respectively), and Auger electron spectroscopy (AES). Thin films of actinide elements and compounds are prepared by sputter deposition from elemental targets. Alloy films are deposited from corresponding alloy targets and could be used, in principle, as replicates of these targets. However, there are deviations between alloy film and target composition, which depend on the deposition conditions, such as pressure and target voltage. Mastering of these effects may allow us to study stoichiometric film replicates instead of thick bulk compounds. As an example, we discuss the composition of U-Ni films prepared from a UNi 5 target. (orig.)

  19. Nuclear waste forms for actinides

    Science.gov (United States)

    Ewing, Rodney C.

    1999-01-01

    The disposition of actinides, most recently 239Pu from dismantled nuclear weapons, requires effective containment of waste generated by the nuclear fuel cycle. Because actinides (e.g., 239Pu and 237Np) are long-lived, they have a major impact on risk assessments of geologic repositories. Thus, demonstrable, long-term chemical and mechanical durability are essential properties of waste forms for the immobilization of actinides. Mineralogic and geologic studies provide excellent candidate phases for immobilization and a unique database that cannot be duplicated by a purely materials science approach. The “mineralogic approach” is illustrated by a discussion of zircon as a phase for the immobilization of excess weapons plutonium. PMID:10097054

  20. Extraction chromatogrpahy of actinides, ch. 7

    International Nuclear Information System (INIS)

    Mueller, W.

    1975-01-01

    This review on extraction chromatography of actinides emphasizes the important usage of neutral (Tributylphosphate), basic (substituted ammonium salts), and acidic (HDEHP) extractants, and their application to separations of actinides in the di-to hexavalent oxidation state. Furthermore, the actinide extraction by ketones, ethers, alcohols and β-diketones is discussed

  1. Actinides integral measurements on FCA assemblies

    International Nuclear Information System (INIS)

    Mukaiyama, Takehiko; Okajima, Shigeaki

    1984-01-01

    Actinide integral measurements were performed on eight assemblies of FCA where neutron energy spectra were shifted systematically from soft to hard in order to evaluate and modify the nuclear cross section data of major actinides. Experimental values on actinide fission rates and sample reactivity worths are compared with the calculated values using JENDL-2 and ENDF/B-V (or IV) data sets. (author)

  2. Moessbauer effect studies with actinides

    International Nuclear Information System (INIS)

    Stone, J.A.

    1966-01-01

    Moessbauer resonance studies in the actinide elements offer a new technique for measuring solid-state properties to a region of the periodic chart where such information is relatively sparse. It is well known that the actinides, the elements with atomic numbers from 90 to 103, form a transition series due to filling of the 5f electron shell, analogous to the rare-earth series in which the 4f shell is filled. Like the rare earths, the actinide metals and compounds are expected to exhibit a variety of interesting magnetic properties, but, unlike the rare earths, there have been few studies of the magnetic behaviour of actinides, and these properties are largely unknown. The chemical properties of the actinides have been studied somewhat more extensively, and, in contrast to the rare earths, form a multiplicity of stable valence states, especially in the lighter members of the series. It is just these properties, magnetic and chemical, for which the Moessbauer effect is a valuable probe, sensitive to the magnetic and electric environment of an atom. The rare-earth series has been a particularly fruitful region in terms of the number of elements which have been shown to exhibit the Moessbauer effect, and for this reason the exploitation of the Moessbauer effect to yield new solid-state and chemical information on the rare earths is a highly active field of research today. There is every reason to believe that the actinides can be similarly studied by the Moessbauer effect. 43 refs, 6 figs, 4 tabs

  3. Actinide cation-cation complexes

    International Nuclear Information System (INIS)

    Stoyer, N.J.; Seaborg, G.T.

    1994-12-01

    The +5 oxidation state of U, Np, Pu, and Am is a linear dioxo cation (AnO 2 + ) with a formal charge of +1. These cations form complexes with a variety of other cations, including actinide cations. Other oxidation states of actinides do not form these cation-cation complexes with any cation other than AnO 2 + ; therefore, cation-cation complexes indicate something unique about AnO 2 + cations compared to actinide cations in general. The first cation-cation complex, NpO 2 + ·UO 2 2+ , was reported by Sullivan, Hindman, and Zielen in 1961. Of the four actinides that form AnO 2 + species, the cation-cation complexes of NpO 2 + have been studied most extensively while the other actinides have not. The only PuO 2 + cation-cation complexes that have been studied are with Fe 3+ and Cr 3+ and neither one has had its equilibrium constant measured. Actinides have small molar absorptivities and cation-cation complexes have small equilibrium constants; therefore, to overcome these obstacles a sensitive technique is required. Spectroscopic techniques are used most often to study cation-cation complexes. Laser-Induced Photacoustic Spectroscopy equilibrium constants for the complexes NpO 2 + ·UO 2 2+ , NpO 2 + ·Th 4+ , PuO 2 + ·UO 2 2+ , and PuO 2 + ·Th 4+ at an ionic strength of 6 M using LIPAS are 2.4 ± 0.2, 1.8 ± 0.9, 2.2 ± 1.5, and ∼0.8 M -1

  4. Chernobyl 90Sr in bilberries from Poland

    International Nuclear Information System (INIS)

    Mietelski, J.W.; Vajda, N.

    1997-01-01

    As part of a detailed survey on the contamination of Polish forests 90 Sr activity concentrations were determined in bilberries. Elevated 90 Sr levels were found in several samples from north-eastern Poland. The calculated maximum 90 Sr surface contamination was 2 kBq*m -2 . The correlation between 90 Sr and 137 Cs concentrations in bilberries was good for two sets of samples originating from two geographical areas of Poland indicating the local differences in radionuclide depositions from Chernobyl fallout. (author)

  5. Preliminary considerations concerning actinide solubilities

    International Nuclear Information System (INIS)

    Newton, T.W.; Bayhurst, B.P.; Daniels, W.R.; Erdal, B.R.; Ogard, A.E.

    1980-01-01

    Work at the Los Alamos Scientific Laboratory on the fundamental solution chemistry of the actinides has thus far been confined to preliminary considerations of the problems involved in developing an understanding of the precipitation and dissolution behavior of actinide compounds under environmental conditions. Attempts have been made to calculate solubility as a function of Eh and pH using the appropriate thermodynamic data; results have been presented in terms of contour maps showing lines of constant solubility as a function of Eh and pH. Possible methods of control of the redox potential of rock-groundwater systems by the use of Eh buffers (redox couples) is presented

  6. Orbital effects in actinide systems

    International Nuclear Information System (INIS)

    Lander, G.H.

    1983-01-01

    Actinide magnetism presents a number of important challenges; in particular, the proximity of 5f band to the Fermi energy gives rise to strong interaction with both d and s like conduction electrons, and the extended nature of the 5f electrons means that they can interact with electron orbitals from neighboring atoms. Theory has recently addressed these problems. Often neglected, however, is the overwhelming evidence for large orbital contributions to the magnetic properties of actinides. Some experimental evidence for these effects are presented briefly in this paper. They point, clearly incorrectly, to a very localized picture for the 5f electrons. This dichotomy only enhances the nature of the challenge

  7. PLANTS AS BIO-MONITORS FOR 137CS, 238PU, 239, 240PU AND 40K AT THE SAVANNAH RIVER SITE

    Energy Technology Data Exchange (ETDEWEB)

    Caldwell, E.; Duff, M.; Ferguson, C.

    2010-12-16

    The nuclear fuel cycle generates a considerable amount of radioactive waste, which often includes nuclear fission products, such as strontium-90 ({sup 90}Sr) and cesium-137 ({sup 137}Cs), and actinides such as uranium (U) and plutonium (Pu). When released into the environment, large quantities of these radionuclides can present considerable problems to man and biota due to their radioactive nature and, in some cases as with the actinides, their chemical toxicity. Radionuclides are expected to decay at a known rate. Yet, research has shown the rate of elimination from an ecosystem to differ from the decay rate due to physical, chemical and biological processes that remove the contaminant or reduce its biological availability. Knowledge regarding the rate by which a contaminant is eliminated from an ecosystem (ecological half-life) is important for evaluating the duration and potential severity of risk. To better understand a contaminants impact on an environment, consideration should be given to plants. As primary producers, they represent an important mode of contamination transfer from sediments and soils into the food chain. Contaminants that are chemically and/or physically sequestered in a media are less likely to be bio-available to plants and therefore an ecosystem.

  8. Safe actinide disposition in molten salt reactors

    International Nuclear Information System (INIS)

    Gat, U.

    1997-01-01

    Safe molten salt reactors (MSR) can readily accommodate the burning of all fissile actinides. Only minor compromises associated with plutonium are required. The MSRs can dispose safely of actinides and long lived isotopes to result in safer and simpler waste. Disposing of actinides in MSRs does increase the source term of a safety optimized MSR. It is concluded that the burning and transmutation of actinides in MSRs can be done in a safe manner. Development is needed for the processing to handle and separate the actinides. Calculations are needed to establish the neutron economy and the fuel management. 9 refs

  9. Burning actinides in very hard spectrum reactors

    International Nuclear Information System (INIS)

    Robinson, A.H.; Shirley, G.W.; Prichard, A.W.; Trapp, T.J.

    1978-01-01

    The major unresolved problem in the nuclear industry is the ultimate disposition of the waste products of light water reactors. The study demonstrates the feasibility of designing a very hard spectrum actinide burner reactor (ABR). A 1100 MW/sub t/ ABR design fueled entirely with actinides reprocessed from light water reactor (LWR) wastes is proposed as both an ultimate disposal mechanism for actinides and a means of concurrently producing usable power. Actinides from discharged ABR fuel are recycled to the ABR while fission products are routed to a permanent repository. As an integral part of a large energy park, each such ABR would dispose of the waste actinides from 2 LWRs

  10. CS Informativeness Governs CS-US Associability

    Science.gov (United States)

    Ward, Ryan D.; Gallistel, C. R.; Jensen, Greg; Richards, Vanessa L.; Fairhurst, Stephen; Balsam, Peter D

    2012-01-01

    In a conditioning protocol, the onset of the conditioned stimulus (CS) provides information about when to expect reinforcement (the US). There are two sources of information from the CS in a delay conditioning paradigm in which the CS-US interval is fixed. The first depends on the informativeness, the degree to which CS onset reduces the average expected time to onset of the next US. The second depends only on how precisely a subject can represent a fixed-duration interval (the temporal Weber fraction). In three experiments with mice, we tested the differential impact of these two sources of information on rate of acquisition of conditioned responding (CS-US associability). In Experiment 1, we show that associability (the inverse of trials to acquisition) increases in proportion to informativeness. In Experiment 2, we show that fixing the duration of the US-US interval or the CS-US interval or both has no effect on associability. In Experiment 3, we equated the increase in information produced by varying the C̅/T̅ ratio with the increase produced by fixing the duration of the CS-US interval. Associability increased with increased informativeness, but, as in Experiment 2, fixing the CS-US duration had no effect on associability. These results are consistent with the view that CS-US associability depends on the increased rate of reward signaled by CS onset. The results also provide further evidence that conditioned responding is temporally controlled when it emerges. PMID:22468633

  11. Research on the chemical speciation of actinides

    International Nuclear Information System (INIS)

    Jung, Euo Chang; Park, K. K.; Cho, H. R.

    2010-04-01

    A demand for the safe and effective management of spent nuclear fuel and radioactive waste generated from nuclear power plant draws increasing attention with the growth of nuclear power industry. The objective of this project is to establish the basis of research on the actinide chemistry by using advanced laser-based highly sensitive spectroscopic systems. Researches on the chemical speciation of actinides are prerequisite for the development of technologies related to nuclear fuel cycles, especially, such as the safe management of high level radioactive wastes and the chemical examination of irradiated nuclear fuels. For supporting these technologies, laser-based spectroscopies have been performed for the chemical speciation of actinide in an aqueous solutions and the quantitative analysis of actinide isotopes in spent nuclear fuels. In this report, results on the following subjects have been summarized. (1) Development of TRLFS technology for chemical speciation of actinides, (2) Development of LIBD technology for measuring solubility of actinides, (3) Chemical speciation of plutonium complexes by using a LWCC system, (4) Development of LIBS technology for the quantitative analysis of actinides, (5) Development of technology for the chemical speciation of actinides by CE, (6) Evaluation on the chemical reactions between actinides and humic substances, (7) Chemical speciation of actinides adsorbed on metal oxides surfaces, (8) Determination of actinide source terms of spent nuclear fuel

  12. ENDF/B-V actinides

    International Nuclear Information System (INIS)

    Kocherov, N.; Lemmel, H.D.

    1981-01-01

    This document summarizes the contents of the actinides part of the ENDF/B-V nuclear data library released by the US National Nuclear Data Center. This library or selective retrievals of it, are available from the IAEA Nuclear Data Section. (author)

  13. Environmental research on actinide elements

    Energy Technology Data Exchange (ETDEWEB)

    Pinder, J.E. III; Alberts, J.J.; McLeod, K.W.; Schreckhise, R.G. (eds.)

    1987-08-01

    The papers synthesize the results of research sponsored by DOE's Office of Health and Environmental Research on the behavior of transuranic and actinide elements in the environment. Separate abstracts have been prepared for the 21 individual papers. (ACR)

  14. Photochemical reactions of actinide ions

    International Nuclear Information System (INIS)

    Tomiyasu, Hiroshi

    1995-01-01

    This paper reviews the results of photochemical studies of actinide ions, which have been performed in our research group for past several years as follows: I) behavior of the excited uranyl(VI) ion; II) photo-reductions of the uranyl ion with organic and inorganic compounds; III) photo-oxidations of uranium(IV) and plutonium(III) in nitric acid solutions. (author)

  15. Angular overlap model in actinides

    International Nuclear Information System (INIS)

    Gajek, Z.; Mulak, J.

    1991-01-01

    Quantitative foundations of the Angular Overlap Model in actinides based on ab initio calculations of the crystal field effect in the uranium (III) (IV) and (V) ions in various crystals are presented. The calculations justify some common simplifications of the model and fix up the relations between the AOM parameters. Traps and limitations of the AOM phenomenology are discussed

  16. Angular overlap model in actinides

    Energy Technology Data Exchange (ETDEWEB)

    Gajek, Z.; Mulak, J. (Polska Akademia Nauk, Wroclaw (PL). Inst. Niskich Temperatur i Badan Strukturalnych)

    1991-01-01

    Quantitative foundations of the Angular Overlap Model in actinides based on ab initio calculations of the crystal field effect in the uranium (III) (IV) and (V) ions in various crystals are presented. The calculations justify some common simplifications of the model and fix up the relations between the AOM parameters. Traps and limitations of the AOM phenomenology are discussed.

  17. Calibration techniques for the in vivo measurement of alpha-emitting actinides

    International Nuclear Information System (INIS)

    Fleming, R.R.

    1976-01-01

    Reliable interpretation of in vivo measurements for alpha-emitting actinides deposited in the lungs is largely dependent on three factors: correction of observed count rates for background contributions; correction for photon absorption in the body; and accurate calibration of the counting system. Terrestrial and cosmic radiation contributions can be minimized by extensive shielding and good pulse-shape discrimination. Techniques are available to minimize errors inherent in the calibration of an in vivo counting system. Minimum amounts of alpha-emitting actinides detectable in the lungs are primarily affected by the accuracy of two factors: predicted body background due to 137 Cs and 40 K, and estimated photon absorption in chest-wall tissue. A matched pair of 12.5-cm-dia phoswich detectors, purchased from the Harshaw Chemical Company, are used to measure low-energy photons emitted by the radioactive actinides

  18. Recent development in computational actinide chemistry

    International Nuclear Information System (INIS)

    Li Jun

    2008-01-01

    Ever since the Manhattan project in World War II, actinide chemistry has been essential for nuclear science and technology. Yet scientists still seek the ability to interpret and predict chemical and physical properties of actinide compounds and materials using first-principle theory and computational modeling. Actinide compounds are challenging to computational chemistry because of their complicated electron correlation effects and relativistic effects, including spin-orbit coupling effects. There have been significant developments in theoretical studies on actinide compounds in the past several years. The theoretical capabilities coupled with new experimental characterization techniques now offer a powerful combination for unraveling the complexities of actinide chemistry. In this talk, we will provide an overview of our own research in this field, with particular emphasis on applications of relativistic density functional and ab initio quantum chemical methods to the geometries, electronic structures, spectroscopy and excited-state properties of small actinide molecules such as CUO and UO 2 and some large actinide compounds relevant to separation and environment science. The performance of various density functional approaches and wavefunction theory-based electron correlation methods will be compared. The results of computational modeling on the vibrational, electronic, and NMR spectra of actinide compounds will be briefly discussed as well [1-4]. We will show that progress in relativistic quantum chemistry, computer hardware and computational chemistry software has enabled computational actinide chemistry to emerge as a powerful and predictive tool for research in actinide chemistry. (authors)

  19. Study of oxygenated compounds of rhenium VII: actinide perrhenates, molybdo- and tungstoperrhenates

    International Nuclear Information System (INIS)

    Silvestre, J.-P.

    1978-01-01

    Crystallographic data for the perrhenates of the actinides and their hydrates. Study of the thermal stability of the perrhenates of the actinides. Double perrhenates of thorium and monovalent elements: Th 5 M 2 (ReO 4 ) 22 , ThM(ReO 4 ) 5 , ThM 2 (ReO 4 ) 6 with M = Na, K, Rb, Cs and Tl; ThM 3 (ReO 4 ) 7 with M=K, Rb, Cs and Tl are showing up in the study of the systems Th(ReO 4 ) 4 -M(ReO 4 ). Study of the possibilities of substitution Re 7+ -Mo 6+ and Re 7+ -W 6+ : non stoechiometric cubic compounds Thsub(1/2-x/4)(Msub(1-x)Resub(x)O 4 ) with 1/6 3 (MO 4 )(ReO 4 ) (M = Mo, W) are disclosed [fr

  20. Study of Cs recovery by extraction chromatography (2)

    International Nuclear Information System (INIS)

    Hoshi, Harutaka; Zhang, Anyun; Uchida, Hiromi; Kuraoka, Etsushu

    2005-02-01

    In order to apply CalixR14 extractant to extraction chromatography for Cs separation, basic characteristics of CalixR14 adsorbent were studied. CalixR14 impregnated resin and CalixR14 + TBP impregnated resin were prepared. CalixR14 extractant showed no adsorption for Cs by liquid-liquid extraction and CalixR14 impregnated resin also showed no adsorption for Cs. Therefore, it is concluded that CalixR14 itself has no affinity for Cs. On the other hand, Cs was adsorbed onto CalixR14-TBP impregnated resin from a concentrated nitric acid solution. The distribution coefficients of Cs were more than 10 cm 3 /g from 2 to 6 M nitric acid. While Rb showed week adsorption, Na, K, Sr and La showed no adsorption and separation factor was over 100. A slight amount of CalixR14 and TBP was leaked from impregnated resin into the aqueous phase. Separation from simulated liquid waste was carried out by using a column packed with CalixR14-TBP adsorbent. Na, K, Sr and La were not adsorbed onto the column, however, Cs and Rb were adsorbed onto the column. Cs and Rb were eluted from the column by water. Cs and Rb were quantitatively recovered. (author)

  1. Effect of Wood Aging on Wine Mineral Composition and 87Sr/86Sr Isotopic Ratio.

    Science.gov (United States)

    Kaya, Ayse D; Bruno de Sousa, Raúl; Curvelo-Garcia, António S; Ricardo-da-Silva, Jorge M; Catarino, Sofia

    2017-06-14

    The evolution of mineral composition and wine strontium isotopic ratio 87 Sr/ 86 Sr (Sr IR) during wood aging were investigated. A red wine was aged in stainless steel tanks with French oak staves (Quercus sessiliflora Salisb.), with three industrial scale replicates. Sampling was carried out after 30, 60, and 90 days of aging, and the wines were evaluated in terms of general analysis, phenolic composition, total polysaccharides, multielement composition, and Sr IR. Li, Be, Mg, Al, Sc, Ti, V, Mn, Co, Ni, Cu, Zn, Ga, Ge, As, Rb, Sr, Y, Zr, Mo, Sb, Cs, Ba, Pr, Nd, Sm, Eu, Dy, Ho, Er, Yb, Lu, Tl, and Pb elements and 87 Sr/ 86 Sr were determined by quadrupole inductively coupled plasma mass spectrometry (Q-ICP-MS) and Na, K, Ca, and Fe by flame atomic absorption spectrometry (FAAS). Two-way ANOVA was applied to assess wood aging and time effect on Sr IR and mineral composition. Wood aging resulted in significantly higher concentrations of Mg, V, Co, Ni, and Sr. At the end of the aging period, wine exhibited statistically identical Sr IR compared to control. Study suggests that wood aging does not affect 87 Sr/ 86 Sr, not precluding the use of this parameter for wine traceability purposes.

  2. Actinide recovery techniques utilizing electromechanical processes

    International Nuclear Information System (INIS)

    Westphal, B.R.; Benedict, R.W.

    1994-01-01

    Under certain conditions, the separation of actinides using electromechanical techniques may be an effective means of residue processing. The separation of granular mixtures of actinides and other materials is based on appreciable differences in the magnetic and electrical properties of the actinide elements. In addition, the high density of actinides, particularly uranium and plutonium, may render a simultaneous separation based on mutually complementary parameters. Both high intensity magnetic separation and electrostatic separation have been investigated for the concentration of an actinide waste stream. Waste stream constituents include an actinide metal alloy and broken quartz shards. The investigation of these techniques is in support of the Integral Fast Reactor (IFR) concept currently being developed at Argonne National Laboratory under the auspices of the Department of Energy

  3. Actinide recovery techniques utilizing electromechanical processes

    International Nuclear Information System (INIS)

    Westphal, B.R.; Benedict, R.W.

    1994-01-01

    Under certain conditions, the separation of actinides using electromechanical techniques may be an effective means of residue processing. The separation of granular mixtures of actinides and other materials discussed in this report is based on appreciable differences in the magnetic and electrical properties of the actinide elements. In addition, the high density of actinides, particularly uranium and plutonium, may render a simultaneous separation based on mutually complementary parameters. Both high intensity magnetic separation and electrostatic separation have been investigated for the concentration of an actinide waste stream. Waste stream constituents include an actinide metal alloy and broken quartz shards. The investigation of these techniques is in support of the Integral Fast Reactor (IFR) concept currently being developed at Argonne National Laboratory under the auspices of the Department of Energy

  4. Analytical evaluation of actinide sensitivities

    International Nuclear Information System (INIS)

    Sola, A.

    1977-01-01

    The analytical evaluation of the sensitivities of actinides to various parameters such as cross sections, decay constants, flux and time is presented. The formulae are applied to isotopes of the Uranium, Neptunium, Plutonium and Americium series. The agreement between analytically obtained and computer evaluated sensitivities being always good, it is throught that the formulation includes all the important parameters entering in the evaluation of sensitivities. A study of the published data is made

  5. Research on the chemical speciation of actinides

    International Nuclear Information System (INIS)

    Jung, Euo Chang; Park, K. K.; Cho, H. R.

    2012-04-01

    A demand for the safe and effective management of spent nuclear fuel and radioactive waste generated from nuclear power plant draws increasing attention with the growth of nuclear power industry. The objective of this project is to establish the basis of research on the actinide chemistry by using highly sensitive and advanced laser-based spectroscopic systems. Researches on the chemical speciation of actinides are prerequisite for the development of technologies related to nuclear fuel cycles, especially, such as the safe management of high level radioactive wastes and the chemical examination of irradiated nuclear fuels. For supporting these technologies, laser-based spectroscopies have been applied for the chemical speciation of actinide in aqueous solutions and the quantitative analysis of actinide isotopes in spent nuclear fuels. In this report, results on the following subjects have been summarized. Development of TRLFS technology for the chemical speciation of actinides, Development of laser-induced photo-acoustic spectroscopy (LPAS) system, Application of LIBD technology to investigate dynamic behaviors of actinides dissolution reactions, Development of nanoparticle analysis technology in groundwater using LIBD, Chemical speciation of plutonium complexes by using a LWCC system, Development of LIBS technology for the quantitative analysis of actinides, Evaluation on the chemical reactions between actinides and humic substances, Spectroscopic speciation of uranium-ligand complexes in aqueous solution, Chemical speciation of actinides adsorbed on metal oxides surfaces

  6. Chemistry of actinides and fission products

    International Nuclear Information System (INIS)

    Pruett, D.J.; Sherrow, S.A.; Toth, L.M.

    1988-01-01

    This task is concerned primarily with the fundamental chemistry of the actinide and fission product elements. Special efforts are made to develop research programs in collaboration with researchers at universities and in industry who have need of national laboratory facilities. Specific areas currently under investigation include: (1) spectroscopy and photochemistry of actinides in low-temperature matrices; (2) small-angle scattering studies of hydrous actinide and fission product polymers in aqueous and nonaqueous solvents; (3) kinetic and thermodynamic studies of complexation reactions in aqueous and nonaqueous solutions; and (4) the development of inorganic ion exchange materials for actinide and lanthanide separations. Recent results from work in these areas are summarized here

  7. 137Cs contamination of Techa river flood plain in Brodokalmak settlement

    International Nuclear Information System (INIS)

    Chesnokov, A.V.; Govorun, A.P.; Liksonov, V.I.; Shcherbak, S.B.; Ivanitskaya, M.V.

    1999-01-01

    137 Cs contamination of the Techa river flood plain inside the Brodokalmak settlement has been mapped. The collimated scintillated detector technique was used for 137 Cs deposit measurements. The 137 Cs contamination is very heterogeneous. A comparison of this technique with the traditional sample method was performed at selected locations. The sampling data are in good agreement with in-situ data. Soil surface activity of 90 Sr was determined from the samples. It was shown that 137 Cs contamination correlates with 90 Sr contamination within the flood plain of the settlement

  8. Analysis of large soil samples for actinides

    Science.gov (United States)

    Maxwell, III; Sherrod, L [Aiken, SC

    2009-03-24

    A method of analyzing relatively large soil samples for actinides by employing a separation process that includes cerium fluoride precipitation for removing the soil matrix and precipitates plutonium, americium, and curium with cerium and hydrofluoric acid followed by separating these actinides using chromatography cartridges.

  9. Burn of actinides in MOX fuel cells

    International Nuclear Information System (INIS)

    Martinez C, E.; Ramirez S, J. R.; Alonso V, G.

    2017-09-01

    The spent fuel from nuclear reactors is stored temporarily in dry repositories in many countries of the world. However, the main problem of spent fuel, which is its high radio-toxicity in the long term, is not solved. A new strategy is required to close the nuclear fuel cycle and for the sustain ability of nuclear power generation, this strategy could be the recycling of plutonium to obtain more energy and recycle the actinides generated during the irradiation of the fuel to transmute them in less radioactive radionuclides. In this work we evaluate the quantities of actinides generated in different fuels and the quantities of actinides that are generated after their recycling in a thermal reactor. First, we make a reference calculation with a regular enriched uranium fuel, and then is changed to a MOX fuel, varying the plutonium concentrations and determining the quantities of actinides generated. Finally, different amounts of actinides are introduced into a new fuel and the amount of actinides generated at the end of the fuel burn is calculated, in order to determine the reduction of minor actinides obtained. The results show that if the concentration of plutonium in the fuel is high, then the production of minor actinides is also high. The calculations were made using the cell code CASMO-4 and the results obtained are shown in section 6 of this work. (Author)

  10. Environmental chemistry of the actinide elements

    International Nuclear Information System (INIS)

    Rao Linfeng

    1986-01-01

    The environmental chemistry of the actinide elements is a new branch of science developing with the application of nuclear energy on a larger and larger scale. Various aspects of the environmental chemistry of the actinide elements are briefly reviewed in this paper, such as its significance in the nuclear waste disposal, its coverage of research fields and possible directions for future study

  11. Calculated Atomic Volumes of the Actinide Metals

    DEFF Research Database (Denmark)

    Skriver, H.; Andersen, O. K.; Johansson, B.

    1979-01-01

    The equilibrium atomic volume is calculated for the actinide metals. It is possible to account for the localization of the 5f electrons taking place in americium.......The equilibrium atomic volume is calculated for the actinide metals. It is possible to account for the localization of the 5f electrons taking place in americium....

  12. Minor Actinides Recycling in PWRs

    International Nuclear Information System (INIS)

    Delpech, M.; Golfier, H.; Vasile, A.; Varaine, F.; Boucher, L.; Greneche, D.

    2006-01-01

    Recycling of minor actinides in current and near future PWR is considered as one of the options of the general waste management strategy. This paper presents the analysis of this option both from the core physics and fuel cycle point of view. A first indicator of the efficiency of different neutron spectra for transmutation purposes is the capture to fission cross sections ratio which is less favourable by a factor between 5 to 10 in PWRs compared to fast reactors. Another indicator presented is the production of high ranking isotopes like Curium, Berkelium or Californium in the thermal or epithermal spectrum conditions of PWR cores by successive neutron captures. The impact of the accumulation of this elements on the fabrication process of such PWR fuels strongly penalizes this option. The main constraint on minor actinides loadings in PWR (or fast reactors) fuels are related to their direct impact (or the impact of their transmutation products) on the reactivity coefficients, the reactivity control means and the core kinetics parameters. The main fuel cycle physical parameters like the neutron source, the alpha decay power, the gamma and neutrons dose rate and the criticality aspects are also affected. Recent neutronic calculations based on a reference core of the Evolutionary Pressurized Reactor (EPR), indicates typical maximum values of 1 % loadings. Different fuel design options for minor actinides transmutation purposes in PWRs are presented: UOX and MOX, homogeneous and heterogeneous assemblies. In this later case, Americium loading is concentrated in specific pins of a standard UOX assembly. Recycling of Neptunium in UOX and MOX fuels was also studied to improve the proliferation resistance of the fuel. The impact on the core physics and penalties on Uranium enrichment were underlined in this case. (authors)

  13. 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).

  14. PIE analysis for minor actinide

    International Nuclear Information System (INIS)

    Suyama, Kenya

    2005-01-01

    Minor actinide (MA) is generated in nuclear fuel during the operation of power reactor. For fuel design, reactivity decrease due to it should be considered. Out of reactors, MA plays key role to define the property of spent fuel (SF) such as α-radioactivity, neutron emission rate, and criticality of SF. In order to evaluate the calculation codes and libraries for predicting the amount of MA, comparison between calculation results and experimentally obtained data has been conducted. In this report, we will present the status of PIE data of MA taken by post irradiation examinations (PIE) and several calculation results. (author)

  15. Review of actinide decorporation with chelating agents

    Energy Technology Data Exchange (ETDEWEB)

    Ansoborlo, E. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DRCP/CETAMA), 30 - Marcoule (France); Amekraz, B.; Moulin, Ch. [CEA Saclay, Dept. de Physico-Chimie (DEN/DPC/SECR), 91 - Gif sur Yvette (France); Moulin, V. [CEA Saclay, Dir. du Developpement et de l' Innovation Nucleares (DEN/DDIN/MR), 91 - Gif Sur Yvette (France); Taran, F. [CEA Saclay (DSV/DBJC/SMMCB), 91 - Gif-sur-Yvette (France); Bailly, Th.; Burgada, R. [Centre National de la Recherche Scientifique (CNRS/LCSB/UMR 7033), 93 - Bobigny (France); Henge-Napoli, M.H. [CEA Valrho, Site de Marcoule (INSTN), 30 (France); Jeanson, A.; Den Auwer, Ch.; Bonin, L.; Moisy, Ph. [CEA Valrho, Dir. de l' Energie Nucleaire (DEN/DRCP/SCPS), 30 - Marcoule (France)

    2007-10-15

    In case of accidental release of radionuclides in a nuclear facility or in the environment, internal contamination (inhalation, ingestion or wound) with actinides represents a severe health risk to human beings. It is therefore important to provide effective chelation therapy or decorporation to reduce acute radiation damage, chemical toxicity, and late radiation effects. Speciation governs bioavailability and toxicity of elements and it is a prerequisite tool for the design and success of new ligands or chelating agents. The purpose of this review is to present the state-of-the-art of actinide decorporation within biological media, to recall briefly actinide metabolism, to list the basic constraints of actinide-ligand for development, to describe main tools developed and used for decorporation studies, to review mainly the chelating agents tested for actinides, and finally to conclude on the future trends in this field. (authors)

  16. Catalytic Organic Transformations Mediated by Actinide Complexes

    Directory of Open Access Journals (Sweden)

    Isabell S. R. Karmel

    2015-10-01

    Full Text Available This review article presents the development of organoactinides and actinide coordination complexes as catalysts for homogeneous organic transformations. This chapter introduces the basic principles of actinide catalysis and deals with the historic development of actinide complexes in catalytic processes. The application of organoactinides in homogeneous catalysis is exemplified in the hydroelementation reactions, such as the hydroamination, hydrosilylation, hydroalkoxylation and hydrothiolation of alkynes. Additionally, the use of actinide coordination complexes for the catalytic polymerization of α-olefins and the ring opening polymerization of cyclic esters is presented. The last part of this review article highlights novel catalytic transformations mediated by actinide compounds and gives an outlook to the further potential of this field.

  17. Real-time {sup 90}Sr Counter

    Energy Technology Data Exchange (ETDEWEB)

    Kaneko, Naomi; Kawai, Hideyuki; Kodama, Satoshi; Kobayashi, Atsushi; Tabata, Makoto; Ito, Hiroshi [Graduate School of Science, Chiba University, Chiba, (Japan); Han, Soorim [Graduate School of Science, Chiba University, Chiba, (Japan); National Institute of Radiological Science, Chiba, (Japan)

    2015-07-01

    Radioisotopes have been emitted around Japan due to a nuclear accident at the Fukushima Daiichi nuclear power station in March 2011. A problem is the contaminated water including the atomic nucleus which relatively has a long half- life time and soluble such as {sup 90}Sr, {sup 137}Cs. Internal exposures by {sup 90}Sr are more dangerous than {sup 137}Cs's because Sr has effective half-life time of 18 years and property of accumulation in a born. We have developed real-time {sup 90}Sr counter which is sensitive beta-ray of maximum kinematic energy of 2.28 MeV from {sup 90}Sr and insensitive of beta-ray of maximum kinematic energy of 1.17 MeV and gamma-ray from {sup 90}Sr by Cherenkov detection. This counter composes of Cerenkov counter, trigger scintillation counter and veto counter. Silica aerogel for Cherenkov counter can obtain refractive index between 1.017 and 1.049 easily. And wavelength shifting fiber (WLSF) is used as a light guide for extending effective area and producing lower cost. A mechanism of the identification of {sup 90}Sr is explained in following. In case of {sup 90}Sr, when the trigger counter reacts on the beta-ray from {sup 90}Sr, aerogel emits the Cherenkov light and WLSF reacts and read the Cherenkov light. On the other hand, in case of {sup 137}Cs, the trigger counter reacts on the beta-ray, aerogel stops the beta- ray and Cherenkov light is not emitted. Therefore, aerogel has a function as a radiator and shielding material. the gamma-ray is not reacted on the lower density detector. Cosmic rays would be also reacted by the veto counter. A prototype counter whose the effective area is 30 cm x 10 cm was obtained (2.0±1.2){sup 3} of mis-identification as {sup 137}Cs/{sup 90}Sr. Detection limit in the surface contamination inspection depends on measurement time and effective area mainly. The sensitivity of wide range, 10{sup -2} - 10{sup 4} Bq/cm{sup 2}, is obtained by adjustment of detection level in circuit of this counter. A lower

  18. Minor actinide transmutation - a waste management option

    International Nuclear Information System (INIS)

    Koch, L.

    1986-01-01

    The incentive to recycle minor actinides results from the reduction of the long-term α-radiological risk rather than from a better utilization of the uranium resources. Nevertheless, the gain in generated electricity by minor actinide transmutation in a fast breeder reactor can compensate for the costs of their recovery and make-up into fuel elements. Different recycling options of minor actinides are discussed: transmutation in liquid metal fast breeder reactors (LMFBRs) is possible as long as plutonium is not recycled in light water reactors (LWRs). In this case a minor actinide burner with fuel of different composition has to be introduced. The development of appropriate minor actinide fuels and their properties are described. The irradiation experiments underway or planned are summarized. A review of minor actinide partitioning from the PUREX waste stream is given. From the present constraints of LMFBR technology a reduction of the long-term α-radiological risk by a factor of 200 is deduced relative to that from the direct storage of spent LWR fuel. Though the present accumulation of minor actinides is low, nuclear transmutation may be needed when nuclear energy production has grown. (orig.)

  19. Criteria for achieving actinide reduction goals

    International Nuclear Information System (INIS)

    Liljenzin, J.O.

    1996-01-01

    In order to discuss various criteria for achieving actinide reduction goals, the goals for actinide reduction must be defined themselves. In this context the term actinides is interpreted to mean plutonium and the so called ''minor actinides'' neptunium, americium and curium, but also protactinium. Some possible goals and the reasons behind these will be presented. On the basis of the suggested goals it is possible to analyze various types of devices for production of nuclear energy from uranium or thorium, such as thermal or fast reactors and accelerator driven system, with their associated fuel cycles with regard to their ability to reach the actinide reduction goals. The relation between necessary single cycle burn-up values, fuel cycle processing losses and losses to waste will be defined and discussed. Finally, an attempt is made to arrange the possible systems on order of performance with regard to their potential to reduce the actinide inventory and the actinide losses to wastes. (author). 3 refs, 3 figs, 2 tabs

  20. Actinides burnup in a sodium fast reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ramirez S, J. R.; Pineda A, R.; Martinez C, E.; Alonso, G., E-mail: ramon.ramirez@inin.gob.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2017-09-15

    The burnup of actinides in a nuclear reactor is been proposed as part of an advanced nuclear fuel cycle, this process would close the fuel cycle recycling some of the radioactive material produced in the open nuclear fuel cycle. These actinides are found in the spent nuclear fuel from nuclear power reactors at the end of their burnup in the reactor. Previous studies of actinides recycling in thermal reactors show that would be possible reduce the amounts of actinides at least in 50% of the recycled amounts. in this work, the amounts of actinides that can be burned in a fast reactor is calculated, very interesting results surge from the calculations, first, the amounts of actinides generated by the fuel is higher than for thermal fuel and the composition of the actinides vector is different as in fuel for thermal reactor the main isotope is the {sup 237}Np in the fuel for fast reactor the main isotope is the {sup 241}Am, finally it is concluded that the fast reactor, also generates important amounts of waste. (Author)

  1. Rapid column extraction method for actinides and strontium in fish and other animal tissue samples

    International Nuclear Information System (INIS)

    Maxwell III, S.L.; Faison, D.M.

    2008-01-01

    The analysis of actinides and radiostrontium in animal tissue samples is very important for environmental monitoring. There is a need to measure actinide isotopes and strontium with very low detection limits in animal tissue samples, including fish, deer, hogs, beef and shellfish. A new, rapid separation method has been developed that allows the measurement of plutonium, neptunium, uranium, americium, curium and strontium isotopes in large animal tissue samples (100-200 g) with high chemical recoveries and effective removal of matrix interferences. This method uses stacked TEVA Resin R , TRU Resin R and DGA Resin R cartridges from Eichrom Technologies (Darien, IL, USA) that allows the rapid separation of plutonium (Pu), neptunium (Np), uranium (U), americium (Am), and curium (Cm) using a single multi-stage column combined with alphaspectrometry. Strontium is collected on Sr Resin R from Eichrom Technologies (Darien, IL, USA). After acid digestion and furnace heating of the animal tissue samples, the actinides and 89/90 Sr are separated using column extraction chromatography. This method has been shown to be effective over a wide range of animal tissue matrices. Vacuum box cartridge technology with rapid flow rates is used to minimize sample preparation time. (author)

  2. Soft X-ray synchrotron radiation investigations of actinide materials systems utilizing X-ray emission spectroscopy and resonant inelastic X-ray scattering

    International Nuclear Information System (INIS)

    Shuh, D.K.; Butorin, S.M.; Guo, J.-H.; Nordgren, J.

    2004-01-01

    Synchrotron radiation (SR) methods have been utilized with increasing frequency over the past several years to study topics in actinide science, ranging from those of a fundamental nature to those that address a specifically-targeted technical need. In particular, the emergence of microspectroscopic and fluorescence-based techniques have permitted investigations of actinide materials at sources of soft x-ray SR. Spectroscopic techniques with fluorescence-based detection are useful for actinide investigations since they are sensitive to small amounts of material and the information sampling depth may be varied. These characteristics also serve to simplify both sample preparation and safety considerations. Examples of investigations using these fluorescence techniques will be described along with their results, as well as the prospects for future investigations utilizing these methodologies

  3. Experimental studies of actinides in molten salts

    International Nuclear Information System (INIS)

    Reavis, J.G.

    1985-06-01

    This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen-containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of actinide elements and compounds, and measurements of various properties of the molten volts. Property measurements discussed are phase relationships, vapor pressure, density, viscosity, absorption spectra, electromotive force, and conductance. 188 refs., 17 figs., 6 tabs

  4. Experimental studies of actinides in molten salts

    Energy Technology Data Exchange (ETDEWEB)

    Reavis, J.G.

    1985-06-01

    This review stresses techniques used in studies of molten salts containing multigram amounts of actinides exhibiting intense alpha activity but little or no penetrating gamma radiation. The preponderance of studies have used halides because oxygen-containing actinide compounds (other than oxides) are generally unstable at high temperatures. Topics discussed here include special enclosures, materials problems, preparation and purification of actinide elements and compounds, and measurements of various properties of the molten volts. Property measurements discussed are phase relationships, vapor pressure, density, viscosity, absorption spectra, electromotive force, and conductance. 188 refs., 17 figs., 6 tabs.

  5. Neutron nuclear data evaluation for actinide nucleic

    International Nuclear Information System (INIS)

    Chen Guochang; Yu Baosheng; Duan Junfeng; Ge Zhigang; Cao Wentian; Tang Guoyou; Shi Zhaomin; Zou Yubin

    2010-01-01

    The nuclear data with high accuracy for minor actinides are playing an important role in nuclear technology applications, including reactor design and operation, fuel cycle concepts, estimation of the amount of minor actinides in high burn-up reactors and the minor actinides transmutation. Through describe the class of nuclear data and nuclear date library, and introduce the procedure of neutron nuclear data evaluation. 234 U(n, f) and 237 Np(n, 2n) reaction experimental data evaluation was evaluated. The fission nuclear data are updated and improved. (authors)

  6. Actinide chemistry in the far field

    International Nuclear Information System (INIS)

    Livens, F.R.; Morris, K.; Parkman, R.; Moyes, L.

    1996-01-01

    The environmental chemistry of the actinides is complicated due both to the extensive redox and coordination chemistry of the elements and also to the complexity of the reactive phases encountered in natural environments. In the far field, interactions with reactive surfaces, coatings and colloidal particles will play a crucial role in controlling actinide mobility. By virtue of both their abundance and reactivity; clays and other layer aluminosilicate minerals, hydrous oxides and organic matter (humic substances) are all identified as having the potential to react with actinide ions and some possible modes of interaction are described, together with experimental evidence for their occurrence. (author)

  7. Spin and orbital moments in actinide compounds

    DEFF Research Database (Denmark)

    Lebech, B.; Wulff, M.; Lander, G.H.

    1991-01-01

    The extended spatial distribution of both the transition-metal 3d electrons and the actinide 5f electrons results in a strong interaction between these electron states when the relevant elements are alloyed. A particular interesting feature of this hybridization, which is predicted by single...... experiments designed to determine the magnetic moments at the actinide and transition-metal sublattice sites in compounds such as UFe2, NpCo2, and PuFe2 and to separate the spin and orbital components at the actinide sites. The results show, indeed, that the ratio of the orbital to spin moment is reduced...

  8. Actinide recovery from pyrochemical residues

    International Nuclear Information System (INIS)

    Avens, L.R.; Clifton, D.G.; Vigil, A.R.

    1984-01-01

    A new process for recovery of plutonium and americium from pyrochemical waste has been demonstrated. It is based on chloride solution anion exchange at low acidity, which eliminates corrosive HCl fumes. Developmental experiments of the process flowsheet concentrated on molten salt extraction (MSE) residues and gave >95% plutonium and >90% americium recovery. The recovered plutonium contained 6 = from high chloride-low acid solution. Americium and other metals are washed from the ion exchange column with 1N HNO 3 -4.8M NaCl. The plutonium is recovered, after elution, via hydroxide precipitation, while the americium is recovered via NaHCO 3 precipitation. All filtrates from the process are discardable as low-level contaminated waste. Production-scale experiments are now in progress for MSE residues. Flow sheets for actinide recovery from electrorefining and direct oxide reduction residues are presented and discussed

  9. Actinide recovery from pyrochemical residues

    International Nuclear Information System (INIS)

    Avens, L.R.; Clifton, D.G.; Vigil, A.R.

    1985-05-01

    We demonstrated a new process for recovering plutonium and americium from pyrochemical waste. The method is based on chloride solution anion exchange at low acidity, or acidity that eliminates corrosive HCl fumes. Developmental experiments of the process flow chart concentrated on molten salt extraction (MSE) residues and gave >95% plutonium and >90% americium recovery. The recovered plutonium contained 6 2- from high-chloride low-acid solution. Americium and other metals are washed from the ion exchange column with lN HNO 3 -4.8M NaCl. After elution, plutonium is recovered by hydroxide precipitation, and americium is recovered by NaHCO 3 precipitation. All filtrates from the process can be discardable as low-level contaminated waste. Production-scale experiments are in progress for MSE residues. Flow charts for actinide recovery from electro-refining and direct oxide reduction residues are presented and discussed

  10. Subsurface interactions of actinide species and microorganisms. Implications for the bioremediation of actinide-organic mixtures

    International Nuclear Information System (INIS)

    Banaszak, J.E.; Rittmann, B.E.; Reed, D.T.

    1999-01-01

    By reviewing how microorganisms interact with actinides in subsurface environments, the way how bioremediation controls the fate of actinides is assessed. Actinides often are co-contaminants with strong organic chelators, chlorinated solvents, and fuel hydrocarbons. Bioremediation can immobilize the actinides, biodegrade the co-contaminants, or both. Actinides at the IV oxidation state are the least soluble, and microorganisms accelerate precipitation by altering the actinide's oxidation state or its speciation. The way how microorganisms directly oxidize or reduce actinides and how microbiological reactions that biodegrade strong organic chelators, alter the pH, and consume or produce precipitating anions strongly affect actinide speciation and, therefore, mobility is described. Why inhibition caused by chemical or radiolytic toxicities uniquely affects microbial reactions is explained. Due to the complex interactions of the microbiological and chemical phenomena, mathematical modeling is an essential tool for research on and application of bioremediation involving co-contamination with actinides. Development of mathematical models that link microbiological and geochemical reactions is described. Throughout, the key research needs are identified. (author)

  11. Subsurface interactions of actinide species and microorganisms : implications for the bioremediation of actinide-organic mixtures

    International Nuclear Information System (INIS)

    Banaszak, J.E.; Reed, D.T.; Rittmann, B.E.

    1999-01-01

    By reviewing how microorganisms interact with actinides in subsurface environments, we assess how bioremediation controls the fate of actinides. Actinides often are co-contaminants with strong organic chelators, chlorinated solvents, and fuel hydrocarbons. Bioremediation can immobilize the actinides, biodegrade the co-contaminants, or both. Actinides at the IV oxidation state are the least soluble, and microorganisms accelerate precipitation by altering the actinide's oxidation state or its speciation. We describe how microorganisms directly oxidize or reduce actinides and how microbiological reactions that biodegrade strong organic chelators, alter the pH, and consume or produce precipitating anions strongly affect actinide speciation and, therefore, mobility. We explain why inhibition caused by chemical or radiolytic toxicities uniquely affects microbial reactions. Due to the complex interactions of the microbiological and chemical phenomena, mathematical modeling is an essential tool for research on and application of bioremediation involving co-contamination with actinides. We describe the development of mathematical models that link microbiological and geochemical reactions. Throughout, we identify the key research needs

  12. Subsurface interactions of actinide species and microorganisms : implications for the bioremediation of actinide-organic mixtures.

    Energy Technology Data Exchange (ETDEWEB)

    Banaszak, J.E.; Reed, D.T.; Rittmann, B.E.

    1999-02-12

    By reviewing how microorganisms interact with actinides in subsurface environments, we assess how bioremediation controls the fate of actinides. Actinides often are co-contaminants with strong organic chelators, chlorinated solvents, and fuel hydrocarbons. Bioremediation can immobilize the actinides, biodegrade the co-contaminants, or both. Actinides at the IV oxidation state are the least soluble, and microorganisms accelerate precipitation by altering the actinide's oxidation state or its speciation. We describe how microorganisms directly oxidize or reduce actinides and how microbiological reactions that biodegrade strong organic chelators, alter the pH, and consume or produce precipitating anions strongly affect actinide speciation and, therefore, mobility. We explain why inhibition caused by chemical or radiolytic toxicities uniquely affects microbial reactions. Due to the complex interactions of the microbiological and chemical phenomena, mathematical modeling is an essential tool for research on and application of bioremediation involving co-contamination with actinides. We describe the development of mathematical models that link microbiological and geochemical reactions. Throughout, we identify the key research needs.

  13. Improving CS regulations.

    Energy Technology Data Exchange (ETDEWEB)

    Nesse, R.J.; Scheer, R.M.; Marasco, A.L.; Furey, R.

    1980-10-01

    President Carter issued Executive Order 12044 (3/28/78) that required all Federal agencies to distinguish between significant and insignificant regulations, and to determine whether a regulation will result in major impacts. This study gathered information on the impact of the order and the guidelines on the Office of Conservation and Solar Energy (CS) regulatory practices, investigated problems encountered by the CS staff when implementing the order and guidelines, and recommended solutions to resolve these problems. Major tasks accomplished and discussed are: (1) legislation, Executive Orders, and DOE Memoranda concerning Federal administrative procedures relevant to the development and analysis of regulations within CS reviewed; (2) relevant DOE Orders and Memoranda analyzed and key DOE and CS staff interviewed in order to accurately describe the current CS regulatory process; (3) DOE staff from the Office of the General Counsel, the Office of Policy and Evaluation, the Office of the Environment, and the Office of the Secretary interviewed to explore issues and problems encountered with current CS regulatory practices; (4) the regulatory processes at five other Federal agencies reviewed in order to see how other agencies have approached the regulatory process, dealt with specific regulatory problems, and responded to the Executive Order; and (5) based on the results of the preceding four tasks, recommendations for potential solutions to the CS regulatory problems developed. (MCW)

  14. Advanced Aqueous Separation Systems for Actinide Partitioning

    Energy Technology Data Exchange (ETDEWEB)

    Nash, Kenneth L.; Clark, Sue; Meier, G Patrick; Alexandratos, Spiro; Paine, Robert; Hancock, Robert; Ensor, Dale

    2012-03-21

    One of the most challenging aspects of advanced processing of spent nuclear fuel is the need to isolate transuranium elements from fission product lanthanides. This project expanded the scope of earlier investigations of americium (Am) partitioning from the lanthanides with the synthesis of new separations materials and a centralized focus on radiochemical characterization of the separation systems that could be developed based on these new materials. The primary objective of this program was to explore alternative materials for actinide separations and to link the design of new reagents for actinide separations to characterizations based on actinide chemistry. In the predominant trivalent oxidation state, the chemistry of lanthanides overlaps substantially with that of the trivalent actinides and their mutual separation is quite challenging.

  15. Electronic structure and correlation effects in actinides

    International Nuclear Information System (INIS)

    Albers, R.C.

    1998-01-01

    This report consists of the vugraphs given at a conference on electronic structure. Topics discussed are electronic structure, f-bonding, crystal structure, and crystal structure stability of the actinides and how they are inter-related

  16. BWR Assembly Optimization for Minor Actinide Recycling

    Energy Technology Data Exchange (ETDEWEB)

    G. Ivan Maldonado; John M. Christenson; J.P. Renier; T.F. Marcille; J. Casal

    2010-03-22

    The Primary objective of the proposed project is to apply and extend the latest advancements in LWR fuel management optimization to the design of advanced boiling water reactor (BWR) fuel assemblies specifically for the recycling of minor actinides (MAs).

  17. Research for actinides extractants from various wastes

    International Nuclear Information System (INIS)

    Musikas, C.; Cuillerdier, C.; Condamines, N.

    1990-01-01

    This paper is an overview of the actinides solvent extraction research undertaken in Fontenay-aux-Roses. Two kinds of extractants are investigated; those usable for the improvement of the nowadays nuclear fuels reprocessing and those necessary for advanced fuels cycles which include the minor actinides (Np, Am) recovery for a further elimination through nuclear reactions. In the first class the mono and diamides, alternative to the organophosphorus extractants, TBP and polyfunctional phosphonates, showed promising properties. The main results are discussed. For the future efficient extractants for trivalent actinides-lanthanides group separations are suitable. The point about the actinides (III) - lanthanides (III) group separation chemistry and the development of some of these extractants are given

  18. Actinide isotopes in the marine environment

    International Nuclear Information System (INIS)

    Holm, E.; Fukai, R.

    1986-01-01

    Studies of actinide isotopes in the environment are important not only from the viewpoint of their radiological effects on human life, but also from the fact that they act as excellent biochemical and geochemical tracers especially in the marine environment. For several of the actinide isotopes there is still a lack of basic data on concentration levels and further investigations on their chemical and physical speciation are required to understand their behaviour in the marine environment. The measured and estimated activity concentration levels of artificial actinides are at present in general a few orders of magnitude lower than those of the natural ones and their concentration factors in biota are relatively low, except in a few species of macroalgae and phytoplankton. The contribution from seafood to total ingestion of actinides by the world population is a few per cent and, therefore, the dose to man from these long-lived radionuclides caused by seafood ingestion is usually low. (orig.)

  19. Robust membrane systems for actinide separations

    International Nuclear Information System (INIS)

    Jarvinen, Gordon D.; McCleskey, T. Mark; Bluhm, Elizabeth A.; Abney, Kent D.; Ehler, Deborah S.; Bauer, Eve; Le, Quyen T.; Young, Jennifer S.; Ford, Doris K.; Pesiri, David R.; Dye, Robert C.; Robison, Thomas W.; Jorgensen, Betty S.; Redondo, Antonio; Pratt, Lawrence R.; Rempe, Susan L.

    2000-01-01

    Our objective in this project is to develop very stable thin membrane structures containing ionic recognition sites that facilitate the selective transport of target metal ions, especially the actinides

  20. Possible existence of backbending in actinide nuclei

    International Nuclear Information System (INIS)

    Dudek, J.; Nazarewicz, W.; Szymanski, Z.

    1982-01-01

    The possibilities for the backbending effect to occur in actinide nuclei are studied using the pairing-self-consistent independent quasiparticle method. The Hamiltonian used is that of the deformed Woods-Saxon potential plus monopole pairing term. The results of the calculations explain why there is no backbending in most actinide nuclei and simultaneously suggest that in some light neutron deficient nuclei around Th and 22 Ra a backbending effect may occur

  1. Lattice effects in the light actinides

    International Nuclear Information System (INIS)

    Lawson, A.C.; Cort, B.; Roberts, J.A.; Bennett, B.I.; Brun, T.O.; Dreele, R.B. von; Richardson, J.W. Jr.

    1998-01-01

    The light actinides show a variety of lattice effects that do not normally appear in other regions of the periodic table. The article will cover the crystal structures of the light actinides, their atomic volumes, their thermal expansion behavior, and their elastic behavior as reflected in recent thermal vibration measurements made by neutron diffraction. A discussion of the melting points will be given in terms of the thermal vibration measurements. Pressure effects will be only briefly indicated

  2. Transmutation of actinides in power reactors.

    Science.gov (United States)

    Bergelson, B R; Gerasimov, A S; Tikhomirov, G V

    2005-01-01

    Power reactors can be used for partial short-term transmutation of radwaste. This transmutation is beneficial in terms of subsequent storage conditions for spent fuel in long-term storage facilities. CANDU-type reactors can transmute the main minor actinides from two or three reactors of the VVER-1000 type. A VVER-1000-type reactor can operate in a self-service mode with transmutation of its own actinides.

  3. Predictive Modeling in Actinide Chemistry and Catalysis

    Energy Technology Data Exchange (ETDEWEB)

    Yang, Ping [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-05-16

    These are slides from a presentation on predictive modeling in actinide chemistry and catalysis. The following topics are covered in these slides: Structures, bonding, and reactivity (bonding can be quantified by optical probes and theory, and electronic structures and reaction mechanisms of actinide complexes); Magnetic resonance properties (transition metal catalysts with multi-nuclear centers, and NMR/EPR parameters); Moving to more complex systems (surface chemistry of nanomaterials, and interactions of ligands with nanoparticles); Path forward and conclusions.

  4. Subcritical limits for special fissile actinides

    International Nuclear Information System (INIS)

    Clark, H.K.

    1980-01-01

    Critical masses and subcritical mass limits in oxide-water mixtures were calculated for actinide nuclides other than /sup 233/U, /sup 235/U, and /sup 239/Pu that have an odd number of neutrons in the nucleus; S/sub n/ transport theory was used together with cross sections, drawn from the GLASS multigroup library, developed to provide accurate forecasts of actinide production at Savannah River

  5. Proposal for experiments with actinide elements

    International Nuclear Information System (INIS)

    Sanchez, R.G.

    1994-01-01

    An analytical study was conducted in which critical masses for some actinide isotopes were calculated with the Monte Carlo Neutron Photon (MCNP) Transport computer code. Different spherical computer models were used for even- and odd-neutron nuclides. Critical masses obtained are tabulated for Np-237, Pu-242, Am-241, Am-243, Pu-241, and Am-242m, together with indirect experimental data. Experimental data are needed for actinides with odd number of neutrons

  6. Interaction between actinides and protein: the calmodulin

    International Nuclear Information System (INIS)

    Brulfert, Florian

    2016-01-01

    Considering the environmental impact of the Fukushima nuclear accident, it is fundamental to study the mechanisms governing the effects of the released radionuclides on the biosphere and thus identify the molecular processes generating the transport and deposition of actinides, such as neptunium and uranium. However, the information about the microscopic aspect of the interaction between actinides and biological molecules (peptides, proteins...) is scarce. The data being mostly reported from a physiological point of view, the structure of the coordination sites remains largely unknown. These microscopic data are indeed essential for the understanding of the interdependency between structural aspect, function and affinity.The Calmodulin (CaM) (abbreviation for Calcium-Modulated protein), also known for its affinity towards actinides, acts as a metabolic regulator of calcium. This protein is a Ca carrier, which is present ubiquitously in the human body, may also bind other metals such as actinides. Thus, in case of a contamination, actinides that bind to CaM could avoid the protein to perform properly and lead to repercussions on a large range of vital functions.The complexation of Np and U was studied by EXAFS spectroscopy which showed that actinides were incorporated in a calcium coordination site. Once the thermodynamical and structural aspects studied, the impact of the coordination site distortion on the biological efficiency was analyzed. In order to evaluate these consequences, a calorimetric method based on enzyme kinetics was developed. This experiment, which was conducted with both uranium (50 - 500 nM) and neptunium (30 - 250 nM) showed a decrease of the heat produced by the enzymatic reaction with an increasing concentration of actinides in the medium. Our findings showed that the Calmodulin actinide complex works as an enzymatic inhibitor. Furthermore, at higher neptunium (250 nM) and uranium (500 nM) concentration the metals seem to have a poison

  7. Positron Spectroscopy of Hydrothermally Grown Actinide Oxides

    Science.gov (United States)

    2014-03-27

    actinide oxides . The work described here is an attempt to characterize the quality of crystals using positron annihilation spectroscopy (PALS). The...Upadhyaya, R. V. Muraleedharan, B. D. Sharma and K. G. Prasad, " Positron lifetime studies on thorium oxide powders," Philosohical Magazine A, vol. 45... crystals . A strong foundation for actinide PALS studies was laid, but further work is required to build a more effective system. Positron Spectroscopy

  8. Separation of actinides and their transmutation

    International Nuclear Information System (INIS)

    Bouchard, M.; Bathelier, M.; Cousin, M.

    1978-08-01

    Neutron irradiation of long-half-life actinides for transmutation into elements with shorter half-life is investigated as a means to reduce the long-term hazards of these actinides. The effectiveness of the method is analysed by applying it to fission product solutions from the first extraction cycle of fuel reprocessing plants. Basic principles, separation techniques and transmutation efficiencies are studied and discussed in detail

  9. The removal of actinide metals from solution

    International Nuclear Information System (INIS)

    Hancock, R.D.; Howell, I.V.

    1980-01-01

    A process is specified for removing actinide metals (e.g. uranium) from solutions. The solution is contacted with a substrate comprising the product obtained by reacting an inorganic solid containing surface hydroxyl groups (e.g. silica gel) with a compound containing a silane grouping, a nitrogen-containing group (e.g. an amine) and other specified radicals. After treatment, the actinide metal is recovered from the substrate. (U.K.)

  10. PREPARATION OF ACTINIDE-ALUMINUM ALLOYS

    Science.gov (United States)

    Moore, R.H.

    1962-09-01

    BS>A process is given for preparing alloys of aluminum with plutonium, uranium, and/or thorium by chlorinating actinide oxide dissolved in molten alkali metal chloride with hydrochloric acid, chlorine, and/or phosgene, adding aluminum metal, and passing air and/or water vapor through the mass. Actinide metal is formed and alloyed with the aluminum. After cooling to solidification, the alloy is separated from the salt. (AEC)

  11. 512-S Facility, Actinide Removal Process Radiological Design Summary Report

    International Nuclear Information System (INIS)

    Nathan, S.J.

    2004-01-01

    This report contains top-level requirements for the various areas of radiological protection for workers. Detailed quotations of the requirements for applicable regulatory documents can be found in the Radiological Design Summary Report Implementation Guide. For the purposes of demonstrating compliance with these requirements, per Engineering Standard 01064, ''shall consider / shall evaluate'' indicates that the designer must examine the requirement for the design and either incorporate or provide a technical justification as to why the requirement is not incorporated. This report describes how the Building 512-S, Actinide Removal Process meets the required radiological design criteria and requirements based on 10CFR835, DOE Order 420.1A, WSRC Manual 5Q and various other DOE guides and handbooks. The analyses supporting this Radiological Design Summary Report initially used a source term of 10.6 Ci/gallon of Cs-137 as the basis for bulk shielding calculations. As the project evolved, the source term was reduced to 1.1 Ci/gallon of Cs-137. This latter source term forms the basis for later dose rate evaluations

  12. Features of contamination with 137Cs, 90Sr of higher water plants of reservoirs in different types in the exclusion zone of the Chernobyl NPP; Особенности загрязнения 137Cs, 90 Sr высшей водной растительности водоемов различных типов зоны отчуждения Чернобыльской АЭС

    Energy Technology Data Exchange (ETDEWEB)

    Kalinichenko, S. A.; Nenashev, R. A. [Polesye State Radiation Ecological Reserve (Belarus)

    2012-07-01

    In the conditions of the Republic of Belarus the realized research of peculiar features of accumulation of 137Cs and 90Sr by the higher water plants made it possible to establish features of their behavior in reservoirs the exclusion zone of Chernobyl NPP. There were analysed levels of the content of radioactive nuclides in the higher water plants, positioned quotients of concentrating and discrimination. There were investigated the processes of seasonal dynamics depending on reservoir phylum. In the course of experiments there were establish the kinds concentrators of radioactive substances and antagonists. The most susceptible to changes of pH environment was strontium. Its transition into biological objects substantially increased in accordance with the increasing of acidity.

  13. Evaluation of actinide partitioning and transmutation

    International Nuclear Information System (INIS)

    1982-01-01

    After a few centuries of radioactive decay the long-lived actinides, the elements of atomic numbers 89-103, may constitute the main potential radiological health hazard in nuclear wastes. This is because all but a very few fission products (principally technetium-99 and iodine-129) have by then undergone radioactive decay to insignificant levels, leaving the actinides as the principal radionuclides remaining. It was therefore at first sight an attractive concept to recycle the actinides to nuclear reactors, so as to eliminate them by nuclear fission. Thus, investigations of the feasibility and potential benefits and hazards of the concept of 'actinide partitioning and transmutation' were started in numerous countries in the mid-1970s. This final report summarizes the results and conclusions of technical studies performed in connection with a four-year IAEA Co-ordinated Research Programme, started in 1976, on the ''Environmental Evaluation and Hazard Assessment of the Separation of Actinides from Nuclear Wastes followed by either Transmutation or Separate Disposal''. Although many related studies are still continuing, e.g. on waste disposal, long-term safety assessments, and waste actinide management (particularly for low and intermediate-level wastes), some firm conclusions on the overall concept were drawn by the programme participants, which are reflected in this report

  14. Rapid determination of actinides in seawater samples

    International Nuclear Information System (INIS)

    Maxwell, S.L.; Culligan, B.K.; Hutchison, J.B.; Utsey, R.C.; McAlister, D.R.

    2014-01-01

    A new rapid method for the determination of actinides in seawater samples has been developed at the Savannah River National Laboratory. The actinides can be measured by alpha spectrometry or inductively-coupled plasma mass spectrometry. The new method employs novel pre-concentration steps to collect the actinide isotopes quickly from 80 L or more of seawater. Actinides are co-precipitated using an iron hydroxide co-precipitation step enhanced with Ti +3 reductant, followed by lanthanum fluoride co-precipitation. Stacked TEVA Resin and TRU Resin cartridges are used to rapidly separate Pu, U, and Np isotopes from seawater samples. TEVA Resin and DGA Resin were used to separate and measure Pu, Am and Cm isotopes in seawater volumes up to 80 L. This robust method is ideal for emergency seawater samples following a radiological incident. It can also be used, however, for the routine analysis of seawater samples for oceanographic studies to enhance efficiency and productivity. In contrast, many current methods to determine actinides in seawater can take 1-2 weeks and provide chemical yields of ∼30-60 %. This new sample preparation method can be performed in 4-8 h with tracer yields of ∼85-95 %. By employing a rapid, robust sample preparation method with high chemical yields, less seawater is needed to achieve lower or comparable detection limits for actinide isotopes with less time and effort. (author)

  15. CS Bond formation by

    Indian Academy of Sciences (India)

    2017-02-02

    Feb 2, 2017 ... a thiol substituent at position-2 of the quinazoline ring. ... coupling reactions represent great contribution to the recent growth of organic synthesis.2 ... Difficulties in C-S ...... Experimental Advances (Amsterdam: Elsevier) 19; (b).

  16. Recovery of Actinides from Actinide-Aluminium Alloys: Chlorination Route

    International Nuclear Information System (INIS)

    Mendes, E.; Malmbeck, R.; Soucek, P.; Jardin, R.; Glatz, J.P.; Cassayre, L.

    2008-01-01

    A method for recovery of actinides (An) from An-Al alloys formed by electrochemical separation of metallic spent nuclear fuel on solid aluminium electrodes in molten chloride salts is described. The proposed route consists of three main steps: -) vacuum distillation of salt adhered on the electrodes, -) chlorination of An-Al alloy by pure chlorine gas and -) sublimation of formed AlCl 3 . A thermochemical study of the route was performed to determine important chemical reactions and to find optimum experimental conditions for all process steps. Vacuum distillation of the electrode is efficient for complete removal of remaining salt and most fission products, full chlorination of the An-Al alloys is possible at any working temperature and evaporation of AlCl 3 is achieved by heating under argon. Experiments have been carried out using U-Al alloy in order to define parameters providing full alloy chlorination without formation of volatile UCl 5 and UCl 6 . It was shown that full chlorination of An-Al alloys without An losses should be possible at a temperature approx. 150 deg. C. (authors)

  17. Recovery of Actinides from Actinide-Aluminium Alloys: Chlorination Route

    Energy Technology Data Exchange (ETDEWEB)

    Mendes, E.; Malmbeck, R.; Soucek, P.; Jardin, R.; Glatz, J.P. [European Commission, JRC, Institute for Transuranium Elements, Postfach 2340, 76125 Karlsruhe (Germany); Cassayre, L. [Laboratoire de Genie Chimique (LGC), Universite Paul Sabatier, UMR CNRS 5503, 118 route de Narbonne, 31062 Toulouse Cedex 04 (France)

    2008-07-01

    A method for recovery of actinides (An) from An-Al alloys formed by electrochemical separation of metallic spent nuclear fuel on solid aluminium electrodes in molten chloride salts is described. The proposed route consists of three main steps: -) vacuum distillation of salt adhered on the electrodes, -) chlorination of An-Al alloy by pure chlorine gas and -) sublimation of formed AlCl{sub 3}. A thermochemical study of the route was performed to determine important chemical reactions and to find optimum experimental conditions for all process steps. Vacuum distillation of the electrode is efficient for complete removal of remaining salt and most fission products, full chlorination of the An-Al alloys is possible at any working temperature and evaporation of AlCl{sub 3} is achieved by heating under argon. Experiments have been carried out using U-Al alloy in order to define parameters providing full alloy chlorination without formation of volatile UCl{sub 5} and UCl{sub 6}. It was shown that full chlorination of An-Al alloys without An losses should be possible at a temperature approx. 150 deg. C. (authors)

  18. Reactor physics aspects of burning actinides in a nuclear reactor

    International Nuclear Information System (INIS)

    Hage, W.; Schmidt, E.

    1978-01-01

    A short review of the different recycling strategies of actinides other than fuel treated in the literature, is given along with nuclear data requirements for actinide build-up and transmutation studies. The effects of recycling actinides in a nuclear reactor on the flux distribution, the infinite neutron multiplication factor, the reactivity control system, the reactivity coefficients and the delayed neutron fraction are discussed considering a notional LWR or LMFBR as an Actinide Trasmutaton Reactor. Some operational problems of Actinide Transmutation reactors are mentioned, which are caused by the α-decay heat and the neutron sources of Actinide Target Elements

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

    International Nuclear Information System (INIS)

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

    1998-01-01

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

  20. Actinide transmutation in nuclear reactors

    International Nuclear Information System (INIS)

    Bultman, J.H.

    1995-01-01

    An optimization method is developed to maximize the burning capability of the ALMR while complying with all constraints imposed on the design for reliability and safety. This method leads to a maximal transuranics enrichment, which is being limited by constraints on reactivity. The enrichment can be raised by using the neutrons less efficiently by increasing leakage from the fuel. With the developed optimization method, a metallic and an oxide fueled ALMR were optimized. Both reactors perform equally well considering the burning of transuranics. However, metallic fuel has a much higher heat conductivity coefficient, which in general leads to better safety characteristics. In search of a more effective waste transmuter, a modified Molten Salt Reactor was designed. A MSR operates on a liquid fuel salt which makes continuous refueling possible, eliminating the issue of the burnup reactivity loss. Also, a prompt negative reactivity feedback is possible for an overmoderated reactor design, even when the Doppler coefficient is positive, due to the fuel expansion with fuel temperature increase. Furthermore, the molten salt fuel can be reprocessed based on a reduction process which is not sensitive to the short-lived spontaneously fissioning actinides. (orig./HP)

  1. Actinide/crown ether chemistry

    International Nuclear Information System (INIS)

    Benning, M.M.

    1988-01-01

    A structural survey of actinide/crown ether compounds was conducted in order to investigate the solid state chemistry of these complexes. Several parameters - the metal size, crown type, counterion, solvent systems and reaction and crystallization conditions - were varied to correlate their importance in complexation. Under atmospheric conditions, two types of complexes were isolated, those containing only hydrogen-bonded crown interactions and instances where the crown interacts directly with the metal center. In both cases, water seems to play a very important role. When coordinated to the metal, water molecules exhibit the necessary donor properties required for the formation of hydrogen-bonded contacts. The water molecules also provide fierce competition with the crown ethers for metal-binding sites and in most cases prohibit the formation of complexes in which direct metal-ligand association exists. The results of this study indicate that direct interaction between the metal atoms and the crown ethers, in the presence of water, can only occur with polyether conformations which limit the steric replusions within the metal coordination sphere

  2. Actinide transmutation in nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Bultman, J H

    1995-01-17

    An optimization method is developed to maximize the burning capability of the ALMR while complying with all constraints imposed on the design for reliability and safety. This method leads to a maximal transuranics enrichment, which is being limited by constraints on reactivity. The enrichment can be raised by using the neutrons less efficiently by increasing leakage from the fuel. With the developed optimization method, a metallic and an oxide fueled ALMR were optimized. Both reactors perform equally well considering the burning of transuranics. However, metallic fuel has a much higher heat conductivity coefficient, which in general leads to better safety characteristics. In search of a more effective waste transmuter, a modified Molten Salt Reactor was designed. A MSR operates on a liquid fuel salt which makes continuous refueling possible, eliminating the issue of the burnup reactivity loss. Also, a prompt negative reactivity feedback is possible for an overmoderated reactor design, even when the Doppler coefficient is positive, due to the fuel expansion with fuel temperature increase. Furthermore, the molten salt fuel can be reprocessed based on a reduction process which is not sensitive to the short-lived spontaneously fissioning actinides. (orig./HP).

  3. Lithium actinide recycle process demonstration

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.K.; Pierce, R.D.; McPheeters, C.C. [Argonne National Laboratory, IL (United States)

    1995-10-01

    Several pyrochemical processes have been developed in the Chemical Technology Division of Argonne Laboratory for recovery of actinide elements from LWR spent fuel. The lithium process was selected as the reference process from among the options. In this process the LWR oxide spent fuel is reduced by lithium at 650{degrees}C in the presence of molten LiCl. The Li{sub 2}O formed during the reduction process is soluble in the salt. The spent salt and lithium are recycled after the Li{sub 2}O is electrochemically reduced. The oxygen is liberated as CO{sub 2} at a carbon anode or oxygen at an inert anode. The reduced metal components of the LWR spent fuel are separated from the LiCL salt phase and introduced into an electrorefiner. The electrorefining step separates the uranium and transuranium (TRU) elements into two product streams. The uranium product, which comprises about 96% of the LWR spent fuel mass, may be enriched for recycle into the LWR fuel cycle, stored for future use in breeder reactors, or converted to a suitable form for disposal as waste. The TRU product can be recycled as fast reactor fuel or can be alloyed with constituents of the LWR cladding material to produce a stable waste form.

  4. 90Sr and 137Cs in total diet

    International Nuclear Information System (INIS)

    1978-01-01

    Under the commission of Science and Technology Agency, Japan Chemical Analysis Center has analyzed total diet samples collected from 30 prefectures, and determined the content of strontium-90 and cesium-137 in these samples. Each prefectural public health laboratory and institute have collected 2 times a year all the daily regular diet consumed for five persons, namely three meals and other eating between meals. These samples were collected at Japan Chemical Analysis Center after carbonation without smoke rising. At Japan Chemical Analysis Center, these samples were ashed in an electric muffle furnace. And the ash to which both some carriers and hydrochloric acid were added, was destroyed under heating. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid and heated to dryness. The filtrate was radiochemically analyzed for strontium-90 and cesium-137. (author)

  5. 90Sr and 137Cs in powdered milk

    International Nuclear Information System (INIS)

    1978-01-01

    Japan Chemical Analysis Center has analyzed the contents of strontium-90 and cesium-137 in powdered milk under the commission of Science and Technology Agency. The samples were purchased on the open market in Tokyo from the powdered milk producers. The analysis of strontium-90 and cesium-137 content was radiochemically carried out using the method applied for the analysis of fresh milk. (author)

  6. Plutonium isotopes/137Cs activity ratios for soil in Montenegro

    International Nuclear Information System (INIS)

    Antovic, N. M.; Vukotic, P.; Svrkota, N.; Andrukhovich, S.K.

    2011-01-01

    Plutonium isotopes/ 137 Cs activity ratios were determined for six soil samples from Montenegro, using the results of alpha-spectrometric measurements of 239+240 Pu and 238 Pu, as well as gamma-spectrometric cesium measurements. An average 239+240 Pu/ 137 Cs activity ratio is found to be 0.02, as the 238 Pu/ 137 Cs and 238 Pu/ 239+240 Pu one - 0.0006 and 0.03, respectively. It follows from the results that the source of plutonium in Montenegro soil is nuclear weapon testing during the fifties and sixties of the twentieth century. On the other hand, there is a contribution of the accident at the Chernobyl nuclear power plant to the soil contamination with 137 Cs isotope. [sr

  7. The release of cesium and the actinides from spent fuel under unsaturated conditions

    International Nuclear Information System (INIS)

    Finn, P.A.; Hoh, J.C.; Wolf, S.F.; Slater, S.A.; Bates, J.K.

    1995-01-01

    Tests designed to be similar to the unsaturated and oxidizing conditions expected in the candidate repository at Yucca Mountain are in progress with spent fuel at 90 degree C. The similarities and the differences in release behavior for 137 Cs during the first 2.6 years and the actinides during the first 1.6 years of testing are presented for tests done with (1) water dripped on the fuel at a rate of 0.075 and 0.75 mL every 3.5 days and (2) in a saturated water vapor environment

  8. Structural stability, electronic structure and mechanical properties of actinide carbides AnC (An = U, Np)

    International Nuclear Information System (INIS)

    Manikandan, M.; Santhosh, M.; Rajeswarapalanichamy, R.

    2016-01-01

    Ab initio calculations are performed to investigate the structural stability, electronic structure and mechanical properties of actinide carbides AnC (An=U, Np) for three different crystal structures, namely NaCl, CsCl and ZnS. Among the considered structures, NaCl structure is found to be the most stable structure for these carbides at normal pressure. A pressure induced structural phase transition from NaCl to ZnS is observed. The electronic structure reveals that these carbides are metals. The calculated elastic constants indicate that these carbides are mechanically stable at normal pressure.

  9. Study of actinide paramagnetism in solution

    International Nuclear Information System (INIS)

    Autillo, Matthieu

    2015-01-01

    The physiochemical properties of actinide (An) solutions are still difficult to explain, particularly the behavioral differences between An(III) and Ln(III). The study of actinide paramagnetic behavior may be a 'simple' method to analyze the electronic properties of actinide elements and to obtain information on the ligand-actinide interaction. The objective of this PhD thesis is to understand the paramagnetic properties of these elements by magnetic susceptibility measurements and chemical shift studies. Studies on actinide electronic properties at various oxidation states in solution were carried out by magnetic susceptibility measurements in solution according to the Evans method. Unlike Ln(III) elements, there is no specific theory describing the magnetic properties of these ions in solution. To obtain accurate data, the influence of experimental measurement technique and radioactivity of these elements was analyzed. Then, to describe the electronic structure of their low energy states, the experimental results were complemented with quantum chemical calculations from which the influence of the ligand field was studied. Finally, these interpretations were applied to better understand the variations in the magnetic properties of actinide cations in chloride and nitrate media. Information about ligand-actinide interactions may be determined from an NMR chemical shift study of actinide complexes. Indeed, modifications induced by a paramagnetic complex can be separated into two components. The first component, a Fermi contact contribution (δ_c) is related to the degree of covalency in coordination bonds with the actinide ions and the second, a dipolar contribution (δ_p_c) is related to the structure of the complex. The paramagnetic induced shift can be used only if we can isolate these two terms. To achieve this study on actinide elements, we chose to work with the complexes of dipicolinic acid (DPA). Firstly, to characterize the geometrical parameters, a

  10. Actinide science. Fundamental and environmental aspects

    International Nuclear Information System (INIS)

    Choppin, Gregory R.

    2005-01-01

    Nuclear test explosions and reactor wastes have deposited an estimated 16x10 15 Bq of plutonium into the world's aquatic systems. However, plutonium concentration in open ocean waters is orders of magnitude less, indicating that most of the plutonium is quite insolvable in marine waters and has been incorporated into sediments. Actinide ions in waters often are not in a state of thermodynamic equilibrium and their solubility and migration behavior is related to the form in which the nuclides were introduced into the aquatic system. Actinide solubility depends on such factors as pH(hydrolysis), E H (oxidation state), reaction with complexants (e.g. carbonate, phosphate, humic acid, etc.) sorption to surfaces of minerals and/or colloids, etc., in the water. The most significant of these variables is the oxidation sate of the metal ion. The simultaneous presence of more than one oxidation state for some actinides (e.g. plutonium) in a solution complicates actinide environmental behavior. Both Np(V)O 2 + and Pu(V)O 2 + , the most significant soluble states in natural oxic waters are relatively noncomplexing and resistant to hydrolysis and subsequent precipitation but can undergo reduction to the Pu(IV) oxidation state with its different elemental behavior. The solubility of NpO 2 + can be as high as 10 -4 M while that of PuO 2 + is more limited by reduction to the insoluble tetravalent species, Pu(OH) 4 , (pK SP - 56). The net solubility of hexavalent UO 2 2+ in sea water is also limited by hydrolysis; however, it has a relatively high concentration due to formation of carbonate complexes. The insoluble trivalent americium hydroxocarbonate, Am(CO) 3 (OH), is the limiting species for the solubility of Am(III) in sea water. Thorium is found exclusively as the tetravalent species and its solubility is limited by the formation of quite insoluble Th(OH) 4 . The chemistry of actinide ions in the environment is reviewed to show the spectrum of reactions that can occur in

  11. Optimization of 90Sr/89Sr measurements

    Directory of Open Access Journals (Sweden)

    Legarda F.

    2012-04-01

    Full Text Available One of the key points in the double measurement method for the measurement of both, 89Sr and 90Sr, by using a proportional counter is the choice of the times at which the measurements should be done. In this paper, the formulae to calculate the 89Sr and 90Sr detection limits in conditions of radioactive equilibrium between 90Y and 90Sr are derived, and an analysis of them as a function of the time between the two measurements is done. The choice for the time of the second measurement is going to depend on the desired quality of the results to be obtained.

  12. Use of fast reactors for actinide transmutation

    International Nuclear Information System (INIS)

    1993-03-01

    The management of radioactive waste is one of the key issues in today's discussions on nuclear energy, especially the long term disposal of high level radioactive wastes. The recycling of plutonium in liquid metal fast breeder reactors (LMFBRs) would allow 'burning' of the associated extremely long life transuranic waste, particularly actinides, thus reducing the required isolation time for high level waste from tens of thousands of years to hundreds of years for fission products only. The International Working Group on Fast Reactors (IWGFR) decided to include the topic of actinide transmutation in liquid metal fast breeder reactors in its programme. The IAEA organized the Specialists Meeting on Use of Fast Breeder Reactors for Actinide Transmutation in Obninsk, Russian Federation, from 22 to 24 September 1992. The specialists agree that future progress in solving transmutation problems could be achieved by improvements in: Radiochemical partitioning and extraction of the actinides from the spent fuel (at least 98% for Np and Cm and 99.9% for Pu and Am isotopes); technological research and development on the design, fabrication and irradiation of the minor actinides (MAs) containing fuels; nuclear constants measurement and evaluation (selective cross-sections, fission fragments yields, delayed neutron parameters) especially for MA burners; demonstration of the feasibility of the safe and economic MA burner cores; knowledge of the impact of maximum tolerable amount of rare earths in americium containing fuels. Refs, figs and tabs

  13. TUCS/phosphate mineralization of actinides

    Energy Technology Data Exchange (ETDEWEB)

    Nash, K.L. [Argonne National Lab., IL (United States)

    1997-10-01

    This program has as its objective the development of a new technology that combines cation exchange and mineralization to reduce the concentration of heavy metals (in particular actinides) in groundwaters. The treatment regimen must be compatible with the groundwater and soil, potentially using groundwater/soil components to aid in the immobilization process. The delivery system (probably a water-soluble chelating agent) should first concentrate the radionuclides then release the precipitating anion, which forms thermodynamically stable mineral phases, either with the target metal ions alone or in combination with matrix cations. This approach should generate thermodynamically stable mineral phases resistant to weathering. The chelating agent should decompose spontaneously with time, release the mineralizing agent, and leave a residue that does not interfere with mineral formation. For the actinides, the ideal compound probably will release phosphate, as actinide phosphate mineral phases are among the least soluble species for these metals. The most promising means of delivering the precipitant would be to use a water-soluble, hydrolytically unstable complexant that functions in the initial stages as a cation exchanger to concentrate the metal ions. As it decomposes, the chelating agent releases phosphate to foster formation of crystalline mineral phases. Because it involves only the application of inexpensive reagents, the method of phosphate mineralization promises to be an economical alternative for in situ immobilization of radionuclides (actinides in particular). The method relies on the inherent (thermodynamic) stability of actinide mineral phases.

  14. Band structure studies of actinide systems

    International Nuclear Information System (INIS)

    Koelling, D.D.

    1976-01-01

    The nature of the f-orbitals in an actinide system plays a crucial role in determining the electronic properties. It has long been realized that when the actinide separation is small enough for the f-orbitals to interact directly, the system will exhibit itinerant electron properties: an absence of local moment due to the f-orbitals and sometimes even superconductivity. However, a number of systems with the larger actinide separation that should imply local moment behavior also exhibit intinerant properties. Such systems (URh 3 , UIr 3 , UGe 3 , UC) were examined to learn something about the other f-interactions. A preliminary observation made is that there is apparently a very large and ansiotropic mass enhancement in these systems. There is very good reason to believe that this is not solely due to large electron--electron correlations but to a large electron--phonon interaction as well. These features of the ''non-magnetic'', large actinide separation systems are discussed in light of our results to date. Finally, the results of some recent molecular calculations on actinide hexafluorides are used to illustrate the shielding effects on the intra-atomic Coulomb term U/sub f-f/ which would appear in any attempt to study the formation of local moments. As one becomes interested in materials for which a band structure is no longer an adequate model, this screened U/sub ff/ is the significant parameter and efforts must be made to evaluate it in solid state systems

  15. Nonaqueous method for dissolving lanthanide and actinide metals

    International Nuclear Information System (INIS)

    Crisler, L.R.

    1975-01-01

    Lanthanide and actinide beta-diketonate complex molecular compounds are produced by reacting a beta-diketone compound with a lanthanide or actinide element in the elemental metallic state in a mixture of carbon tetrachloride and methanol

  16. Strategies for minority actinides transmutation in fast reactors

    International Nuclear Information System (INIS)

    Perez-Martin, S.; Martin-Fuertes, F.; Alvarez-Velarde, F.

    2010-01-01

    Presentation of the strategies that can be followed in fast reactors designed for the fourth generation to reduce the inventory of minority actinides generated in current light water reactors, as the actinides generation in fast reactor.

  17. Determination of Sr-90, Cs-137, Na, K, Cs, Ca, Sr and Ba in Milk Powder (A-7)

    International Nuclear Information System (INIS)

    1973-01-01

    The samples were made from fresh skim milk by spray drying. The homogeneity was achieved by stirring the original liquid milk and the powder itself. No spiking with active or inactive materials was made. Each participating laboratory received 800 g sub-samples of the material. 26 participants submitted a total of 99 laboratory means and 365 results of individual determinations. Some of the laboratories submitted two different sets of results for the same radionuclides or stable elements which were obtained either by different analysts. The results are presented separately for all the radionuclides and stable elements (except cesium)

  18. 1981 Annual Status Report. Plutonium fuels and actinide programme

    International Nuclear Information System (INIS)

    1981-01-01

    In this 1981 report the work carried out by the European Institute for Transuranium elements is reviewed. Main topics are: operation limits of plutonium fuels: swelling of advanced fuels, oxide fuel transients, equation of state of nuclear materials; actinide cycle safety: formation of actinides (FACT), safe handling of plutonium fuel (SHAPE), aspects of the head-end processing of carbide fuel (RECARB); actinide research: crystal chemistry, solid state studies, applied actinide research

  19. Ultratrace analysis of transuranic actinides by laser-induced fluorescence

    Science.gov (United States)

    Miller, S.M.

    1983-10-31

    Ultratrace quantities of transuranic actinides are detected indirectly by their effect on the fluorescent emissions of a preselected fluorescent species. Transuranic actinides in a sample are coprecipitated with a host lattice material containing at least one preselected fluorescent species. The actinide either quenches or enhances the laser-induced fluorescence of the preselected fluorescent species. The degree of enhancement or quenching is quantitatively related to the concentration of actinide in the sample.

  20. The cosmic ray actinide charge spectrum derived from a 10 m2 array of solid state nuclear track detectors in Earth orbit

    International Nuclear Information System (INIS)

    Donnelly, J.; Thompson, A.; O'Sullivan, D.; Drury, L.O'C.; Wenzel, K.-P.

    2001-01-01

    The DIAS-ESTEC Ultra Heavy Cosmic Ray Experiment (UHCRE) on the Long Duration Exposure Facility, collected approximately 3000 cosmic ray nuclei with Z>65 in the energy region E>1.5 GeV nucleon -1 during a six year exposure in Earth orbit. The entire accessible collecting area of the solid state nuclear track detector (SSNTD) array has been scanned for actinides, yielding a sample of 30 from an exposure of ∼150 m 2 sr yr. The UHCRE experimental setup is described and the observed charge spectrum presented. The current best value for the cosmic ray actinide relative abundance, (Z>88)/(74≤Z≤87), is reported