Strontium-90 and cesium-137 in powdered milk

International Nuclear Information System (INIS)

1977-01-01

Japan Chemical Analysis Center has analysed the strontium-90 and cesium-137 content in powdered milk. 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 carried out using the method recommended by Science and Technology Agency. (author)

Study of strontium and cesium migration in fractured crystalline rock

International Nuclear Information System (INIS)

Gustafsson, E.; Klockars, C.E.

1984-01-01

The purpose of this investigation has been to study the retardation and dilution of non-active strontium and cesium relative to a non-absorbing substance (iodide) in a well-defined fracture zone in the Finnsjoen field research area. The investigation was carried out in a previously tracer-tested fracture zone. The study has encompassed two separate test runs with prolonged injection of strontium and iodide and of cesium and iodide. The test have shown that: - Strontium is not retarded, but rather absorbed to about 40% at equilibrium. - At injection stop, 36.3% of the injected mass of strontium has been absorbed and there is no deabsorption. -Cesium is retarded a factor of 2-3 and absorbed to about 30% at equilibrium. - At injection stop, 39.4% of the injected mass of cesium has been absorbed. Cesium is deabsorbed after injection stop (400h) and after 1300 hours, only 22% of the injected mass of cesium is absorbed. (author)

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

International Nuclear Information System (INIS)

Nimmagadda, M.; Yu, C.

1993-04-01

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

Redistribution of strontium and cesium during alteration of smectite to illite

International Nuclear Information System (INIS)

Ohnuki, Toshihiko; Murakami, Takashi; Sato, Tsutomu; Isobe, Hiroshi

1994-01-01

The redistribution of strontium and cesium during the alteration of smectite to illite has been studied under hydrothermal conditions at 200 C using solutions of 1x10 -4 M Sr and Cs. Two different sorption conditions were applied for the hydrothermal experiments. One was the condition in which strontium and cesium were sorbed by smectite before the hydrothermal experiments (dynamic condition). The other was the condition in which strontium and cesium were sorbed by the alteration products, illite/smectite (I/S) interstratified minerals after the hydrothermal experiments (static condition). The sorption characteristics of strontium and cesium by smectite, I/S interstratified minerals were examined by a sequential extraction method. Most of the strontium was desorbed from smectite and the I/S interstratified minerals with a 1 M KCl solution under both the dynamic and static conditions. Less than 1% of cesium was desorbed from the I/S interstratified minerals with any solution of a 1 M KCl, a 1 M HCl and a 6 M HCl under the dynamic condition, while most of cesium was desorbed with either solution of a 1 M KCl and 1 M HCl from smectite and from the I/S interstratified minerals under the static condition. These suggest that cesium sorbed by smectite changes its sorption characteristic during the alteration process, but strontium does not. Possible sites for more strongly bounded cesium to the I/S interstratified minerals may be at the 'ditrigonal cavity' of adjacent tetrahedral layers. (orig.)

Magnetite effect in radionuclide retention : cesium, strontium, molybdenum and selenium; Efecto de la magnetita en la retencion de los radionucleidos en el campo proximo: cesio, estroncio, molibdeno y selenio

Energy Technology Data Exchange (ETDEWEB)

Rovira, M.; Casas, I.; Gimenez, J.; Clarens, F.; Pablo, J. de

2004-07-01

In this work we have investigated the interaction of magnetite with cesium, strontium, molybdenum and selenium, in the frame of radionuclide retention by canister corrosion products. For each radionuclide, the retention on magnetite has been studied as a function of pH and the mass/ volume ratio. The experimental results have been modeled by means of Surface Complexation Models (SCM), that constitute a tool that allows an approach to sorption mechanisms in a wide range of experimental conditions taking into account electrostatic interactions at the mineral-water interface.(Author)

Strontium-90 and cesium-137 in freshwater from May 1984

International Nuclear Information System (INIS)

1984-01-01

Strontium-90 and cesium-137 in freshwater measured in May 1984 are given in pCi/l. The sampling point is 1, Kasumigaura-Lake (Ibaraki). Collection and pretreatment of samples, preparation of samples for analysis, separation of strontium-90 and cesium-137, determination of stable strontium, calcium and potassium, and counting are described. The sample was passed through a cation exchange column. After the radiochemical separation, the mounted precipitates were counted for activity using low background beta counters normally for 60 minutes. (Mori, K.)

Lanthanide doped strontium-barium cesium halide scintillators

Science.gov (United States)

Bizarri, Gregory; Bourret-Courchesne, Edith; Derenzo, Stephen E.; Borade, Ramesh B.; Gundiah, Gautam; Yan, Zewu; Hanrahan, Stephen M.; Chaudhry, Anurag; Canning, Andrew

2015-06-09

The present invention provides for a composition comprising an inorganic scintillator comprising an optionally lanthanide-doped strontium-barium, optionally cesium, halide, useful for detecting nuclear material.

Application of crown-ethers to cesium and strontium removal from Marcoule reprocessing concentrate

International Nuclear Information System (INIS)

Dozol, J.F.; Casas I Garcia, J.

1990-01-01

The liquid wastes arising from reprocessing plants are treated by evaporation, the distillate is discharged into environment and the concentrate containing all the active and inactive salts must be stored in geological formation, after embedding, due to the activity of long life radionuclides (actinides, Cs, Sr). The objective of this work, is after removal actinides, to remove cesium/strontium from high sodium content acidic concentrates in order to sharply decrease the volume of wastes to be stored in geological formation

The role of microorganisms in the mobility of radionuclides in soil. I. Examination of resistance to strontium, cesium, cobalt and zinc

International Nuclear Information System (INIS)

Konyi, J.; Koska, P.; Berzsenyi, G.; Gazso, L.G.; Appanna, V.D.

1997-01-01

132 microorganisms were isolated from cultivated soils sampled near a nuclear power plant. Quantitative and qualitative analysis was made concerning the macro-morphology, micro-morphology and Gram staining. Resistance of microorganisms to strontium, cesium, cobalt and zinc was determined using agar plates containing metals. Cobalt and zinc proved to be toxic at a concentration of 100 mg/l, but strontium and cesium did not inhibit the growth even at the concentration up to 200 mg/l. Results of analyses of mechanisms of zinc resistance by photometry and spectral analysis also presented. (author)

Effects of mineralogy on sorption of strontium and cesium onto Calico Hills Tuff

International Nuclear Information System (INIS)

Meyer, R.E.; Arnold, W.D.; Case, F.I.; O'Kelley, G.D.; Land, J.F.

1990-04-01

The sorption properties of tuff formations at the proposed site for the high-level nuclear waste repository at Yucca Mountain, Nevada, have been extensively studied. Sorption and desorption measurements were made of strontium and cesium onto clinoptilolite and Calico Hills Tuff. The object was to see whether there was a correlation between sorption of strontium and cesium onto Calico Hills Tuff and the sorption of strontium and cesium onto clinoptilolite based on the content of clinoptilolite in the Calico Hills Tuff. 13 refs., 10 figs., 6 tabs

Water purification from cesium-137 and strontium-90 using natural and activated laminar and laminar-band silicates

International Nuclear Information System (INIS)

Kornilovich, B.Yu.; Pshinko, G.N.; Kosorukov, A.A.; Mas'ko, A.N.; Spasenova, L.N.; Dregval', T.N.

1991-01-01

Cesium-137 and strontium-90 radionuclides are studied for the process of their sorption from natural waters by basic representatives of disperse silicates: kaolinites of Glukhovetskoe and Glukhovskoe deposits (Ukraine), montmorillonites of the Cherkassy (Ukraine) and Oglanlin (Turkmenia) deposits, palygorskite and natural mixture of montmorillonite and palygorskite of the Cherkassy deposit. The best sorption properties are revealed for laminated silicates with a swelling structure (montmorillonites) and high-dispersive laminar-band silicates (palygorskite). It proved possible to improve sorption properties of silicate minerals for radionuclides by means of their mechanochemical activation

Strontium-90 and cesium-137 in freshwater (from September, 1982, to December, 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in fresh water measured at 4 locations across Japan from September to December, 1982, are given in pCi/l, respectively. The methods of the collection and pretreatment of samples, the preparation of samples for analysis, the separation of strontium-90 and cesium-137, and the counting are also described. The sample was passed through a cation exchange column. Strontium and cesium were eluted with hydrochloric acid from the cation exchange column. The sample solution prepared was neutralized with sodium hydroxide. After sodium carbonate was added, the precipitate of strontium and calcium carbonates was separated. The supernatant solution was retained for cesium-137 determination. After the radiochemical separation, the mounted precipitate was counted for activity using a low background beta counter normally for 60 min. The radioactivity ranged 0.08 to 0.22 pCi/l for Sr-90 and 0.003 to 0.020 pCi/l for Cs-137 in the freshwater. (J.P.N.)

The diffusivity of cesium, strontium, carbon and nickel in concrete and mixtures of sodium bentonite and crushed rock

International Nuclear Information System (INIS)

Muurinen, A.; Penttilae-Hiltunen, P.; Rantanen, J.

1986-07-01

The engineering barriers suggested to be used for the disposal of low and intermediate level wastes in Finland are concrete and crushed rock or mixtures of crushed rock and bentonite. In the repository the barriers are saturated by groundwater and radionuclides may be released by diffusion through the barries. For safety analysis, the mechanisms by which the nuclides migrate and corresponding parameters should be known. In this study diffusion measurements on different types of concrete and mixtures of sodium bentonite and crushed rock were carried out. Radioactive isotopes of cesium, strontium, carbon and nickel were used as tracers. The apparent diffusivities (Dsub(a)) were evaluated on the basis of the measurements. The apparent diffusivity of cesium in concretes was 10 -14 ...10 -15 m 2 /s. Strontium was mainly sorbed on cement where it diffuses slowly. Part of strontium propably penetrates in the rock ballast by diffusion. The diffusivities of carbon and nickel in the concrete was low. The upper limit was evaluated to be Dsub(a) -14 m 2 /s. The diffusivity of cesium in the mixtures of crushed rock and bentonite varies between 0.5x10 -12 and 7x10 -12 m 2 /s. Cesium was mainly sorbed on the rock. The diffusivity of strontium was 2x10 -11 ...2x10 -12 m 2 /s. Strontium was mainly sorbed on bentonite. The diffusion of the sorbed ions (surface diffusion) seems to be a additional migration mechanism in the case of cesium and strontium in the mixture of bentonite and crushed rock. The diffusivity of carbon in the mixtures of crushed rock and bentonite was 6x10 -11 ...4x10 -12 m 2 /s. No sorption was found in the case of carbon. The measured Dsub(a) of nickel in the mixtures of crushed rock and bentonite was 4x10 -14 ...2x10 -15 m 2 /s. The experimental arrangement was not, however, in the stationary state and the more correct values would propably be 10 -13 ...10 -14 m 2 /s. No surface diffusion was found in the case of nickel. (author)

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

International Nuclear Information System (INIS)

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

1990-01-01

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

Preliminary experiments for measuring Kd values for cesium and strontium. To be used in site evaluations

International Nuclear Information System (INIS)

Benischek, I.; Hess, V.; Metzker, E.

1992-03-01

In an underground dump not only technolgical barriers but also the natural geological formations are efficient in withholding radionuclides. Sites are to be chosen where the rocks have good sorption properties and where transportation due to various chemical interactions should be minimal. Minerals obtained from deep drilling - granodiorite, mylonite and granit gneis - were investigated. The liquid phase (cement leaching water) contained different amounts of cesium 137 and strontium 85. Details of the experiments and results are given

Physical barrier effect of geopolymeric waste form on diffusivity of cesium and strontium.

Science.gov (United States)

Jang, J G; Park, S M; Lee, H K

2016-11-15

The present study investigates the physical barrier effect of geopolymeric waste form on leaching behavior of cesium and strontium. Fly ash-based geopolymers and slag-blended geopolymers were used as solidification agents. The leaching behavior of cesium and strontium from geopolymers was evaluated in accordance with ANSI/ANS-16.1. The diffusivity of cesium and strontium in a fly ash-based geopolymer was lower than that in Portland cement by a factor of 10(3) and 10(4), respectively, showing significantly improved immobilization performance. The leaching resistance of fly ash-based geopolymer was relatively constant regardless of the type of fly ash. The diffusivity of water-soluble cesium and strontium ions were highly correlated with the critical pore diameter of the binder. The critical pore diameter of the fly ash-based geopolymer was remarkably smaller than those of Portland cement and slag-blended geopolymer; consequently, its ability physically to retard the diffusion of nuclides (physical barrier effect) was superior. Copyright © 2016 Elsevier B.V. All rights reserved.

Ion-exchange properties of cesium and strontium into zeolites from sodium salt solutions

International Nuclear Information System (INIS)

Kanno, Takuji; Hashimoto, Hiroyuki; Ohtani, Tozo.

1978-01-01

The ion-exchange properties of cesium and strontium into zeolite from sodium salt solution has been studied in zeolite A, zeolite X, zeolite Y, mordenite and clinoptilolite. The distribution of cesium into mordenite from about 1 -- 2 M sodium chloride and sodium hydroxide solutions is considerably larger than that into zeolite A. The distribution coefficient for 2 M solution of sodium salts was about 300. Therefore, the separation of cesium from sodium salt solution is possible by using mordenite. The distribution of strontium into zeolites form 1 -- 2 M solutions of sodium chloride and sodium nitrate were in the order of zeolite A>zeolite X>zeolite Y asymptoticaly equals mordenite. The distribution coefficient of 230 was obtained for 1 M solutions of sodium salts. The anion in solutions had no effect on the distribution of cesium and strontium into zeolite from sodium salt solution. (author)

Strontium-90 and cesium-137 in service water (from June, 1982, to December, 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in service water measured at 19 locations across Japan from June to December, 1982, are given in pCi/l, respectively. The methods of the collection and pretreatment of samples, the preparation of samples for analysis, the separation of strontium-90 and cesium-137, and the counting are also described. Service water was collected at an intake of the water-treatment plant and at the tap. The sample was then passed through a cation exchange column. Strontium and cesium were eluted with hydrochloric acid from the cation exchange column. The sample solution prepared was neutralized with sodium hydroxide. After sodium carbonate was added, the precipitate of strontium and calcium carbonates was separated. The supernatant solution was retained for cesium-137 determination. After the radiochemical separation, the mounted precipitate was counted for activity using a low background beta counter normally for 60 min. The radioactivity ranged 0.01 to 0.10 pCi/l for Sr-90 and 0.001 to 0.010 pCi/l for Cs-137 in the service water. (J.P.N.)

Removal of cesium and strontium from low active waste solutions by zeolites

International Nuclear Information System (INIS)

Jain, Savita; Ramaswamy, M.; Theyyunni, T.K.

1994-01-01

Ion exchange, crystallographic and thermal characteristics of sodium, cesium and strontium forms of locally available synthetic zeolites have been investigated. X-ray and differential thermal analyses have confirmed that the synthetic materials AR1 and 4A belonged to the mordenite and A type families of zeolites respectively. Equilibrium uptake of cesium and strontium ions by sodium forms of zeolite was studied as a function of time, pH and sodium concentration. It was found that the rate of sorption by AR1 was higher than that by 4A. In regard to pH, distribution of nuclides on zeolites was found to pass through maxima at a pH value of around 9. Sodium ion interfered with the sorption of cesium and strontium by zeolites. However, at sodium concentration ≤ 0.01 M, distribution coefficient values for these nuclides were sufficiently high to merit consideration of these zeolites for low level waste treatment. Lab-scale column runs using 5 ml beds of materials showed that the zeolites AR1 and 4A were very effective in removing cesium and strontium nuclides respectively from large volumes (a decontamination factor of 50 for a throughput of 6000 bed volumes) of actual low level waste solutions. Thus, the zeolite system has a potential future for large scale application in the treatment of low level wastes. (author). 6 refs., 5 figs., 6 tabs

Strontium-90 and cesium-137 in service water

International Nuclear Information System (INIS)

1979-01-01

Prefectural public health laboratories and institutes and Japan Chemical Analysis Center have analysed the contents of strontium-90 and cesium-137 in service water under the commission of Science and Technology Agency. At each prefectural public health laboratories and institutes, 100 literes of service water (8 prefectures, water from the intake of each station of water works) and tap water (32 prefectures) were collected as sample twice a year. The samples were filtrated with large filter papers after addition and mixture of both some carries. The filtration was then applied on a column filled the sodium cation exchange resin, and all the cations were absorbed on it. These resin and filter papers were collected at Japan Chemical Analysis Center. At Japan Chemical Analysis Center, these collected samples were radiochemically analysed for strontium-90 and cesium-137 using the method applied for the analysis of rain and dry fallout materials. (author)

Reduction of cesium levels in the diet through management of food

International Nuclear Information System (INIS)

Gerzabek, M.H.

1990-01-01

Several processes influence the radionuclide concentration of food products during processing: dilution, losses, concentration. Boiling of leaf vegetables yields a decontamination effect of up to 80% in the case of radioiodine. Peeling of potato tubers results in a reduction of the cesium concentration of 30%. The cesium and strontium concentration of flour is a factor of two lower as compared to the corresponding cereal grain due to the milling process. Significant discrimination occurs during the milk processing. The skimmed milk is significantly richer in cesium, iodine and especially in strontium than the cream. It follows that butter is depleted in its radionuclide contents as compared to other milk produce. Strontium is concentrated in the casein. Pressurized cooking in combination with salting or a treatment with acetic acid results in an Cs-activity loss of beef, veal and lamb meat of 50 to 90%. (Author) 3 figs., 7 tabs., 13 refs

Strontium-90 and cesium-137 in soil from May to July 1983

International Nuclear Information System (INIS)

1983-01-01

The measured values in soil of strontium-90 and cesium-137 at a total of 4 locations throughout Japan from May to July, 1983 are given in pCi/kg and mCi/km 2 in the tables. The method of measurement is also described: collection and pretreatment of samples, preparation of the samples for analysis, separation of strontium-90 and cesium-137, determination of stable strontium, calcium and potassium, and counting. Soil was collected from the location in the spacious and flat area without any past disturbance. Soil was taken from two layers having different depths: 0--5 cm and 5--20 cm. The sample solution was neutralized with sodium hydroxide. After sodium carbonate was added, the precipitate of strontium and calcium carbonates was separated. The supernatant solution was retained for cesium-137 determination. After the radiochemical separation, the mounted precipitates were counted for activity using a low background beta counter normally for 60 min. The maximum values were 690 pCi/kg for Sr-90 and 1300 pCi/kg for Cs-137, which were obtained from the samples in the 5-to-20 cm depth, in June 1983, at Akita-ken,Japan. (Mori, K.)

Strontium-90 and cesium-137 in tea (Japanese tea)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in tea (Japanese tea) were determined. Five hundred grams of manufactured green tea was collected from six sampling locations in Japan. The results are shown in a table. (Namekawa, K.)

Strontium 90 and cesium 137 content in the daily diet of two groups of people in Plovdiv

International Nuclear Information System (INIS)

Babakova, I.; Trendafilov, I.; Todorov, D.

1975-01-01

The contents of strontium 90 and cesium 137 in the daily diet of children, 7-11 years old, and teenagers, 14-18 years old, living under boarding house conditions is determined. The daily strontium 90 intake in the organism of children and teenagers amounts to 9,78 pCi, respectively 17,96 pCi and the daily intake of cesium 137 - to 13,21 pCi, respectively 21,33 pCi. The bigger part of the strontium 90 and cesium 137 intake comes from the bread, accounting for 4,85 pCi stroncium 90 and 5,08 to 7,0 pCi cesium 137. (author)

Innovative Highly Selective Removal of Cesium and Strontium Utilizing a Newly Developed Class of Inorganic Ion Specific Media - 16221

International Nuclear Information System (INIS)

Denton, Mark S.; Kanatzidis, Mercouri G.

2009-01-01

Highly selective removal of Cesium and Strontium is critical for waste treatment and environmental remediation. Cesium-137 is a beta-gamma emitter and Strontium-90 is a beta emitter with respective half-lives of 30 and 29 years. Both elements are present at many nuclear sites. Cesium and Strontium can be found in wastewaters at Washington State's Hanford Site, as well as in waste streams of many Magnox reactor sites. Cesium and Strontium are found in the Reactor Coolant System of light water reactors at nuclear power plants. Both elements are also found in spent nuclear fuel and in high-level waste (HLW) at DOE sites. Cesium and Strontium are further major contributors to the activity and the heat load. Therefore, technologies to extract Cesium and Strontium are critical for environmental remediation waste treatment and dose minimization. Radionuclides such as Cesium-137 and Strontium-90 are key drivers of liquid waste classification at light water reactors and within the DOE tank farm complexes. The treatment, storage, and disposal of these wastes represents a major cost for nuclear power plant operators, and comprises one of the most challenging technology-driven projects for the DOE Environmental Management (EM) program. Extraction technologies to remove Cesium and Strontium have been an active field of research. Four notable extraction technologies have been developed so far for HLW: solvent extraction, prussian blue, crystalline silico-titanate (CST) and organic ion-exchangers (e.g., resorcinol formaldehyde and SuperLig). The use of one technology over another depends on the specific application. For example, the waste treatment plant (WTP) at Hanford is planning on using a highly-selective organic ion-exchange resin to remove Cesium and Strontium. Such organic ion-exchangers use molecular recognition to selectively bind to Cesium and Strontium. However, these organic ion-exchangers are synthesized using multi-step organic synthesis. The associated cost to

Strontium-90 and cesium-137 in sea water (from Jul 1984 to Sep 1984)

International Nuclear Information System (INIS)

1984-01-01

Monitoring results are presented on strontium-90 and cesium-137 contents in sea water of 11 sampling points all over Japan from Hokkaido to Okinawa coast. Sampling points were selected by the criterion that the effect of terrestrial fresh water and atmospheric precipitation was expected to be ignorable. Sample collection was carried out in the Period from July to September, 1984. With a special care for prevention of any contamination. The collected sea water samples were acidified immediately and they were served for radiochemical separation and purification of strontium-90 and cesium-137. Radiation counting was made for yttrium-90 hydroxide sample and cesium chloroplatinate sample with a low background beta counter normally for 60 minutes. As for strontium-90 contents in sea water, they were ranged from 0.07 +- 0.010 pCi/l (Mutsu Bay, Aomori) to 0.11 +- 0.012 pCi/l (Off Niigata Port, Niigata) and the average value was 0.09 pCi/l. As for cesium-137 contents, they were ranged from 0.08 +- 0.011 pCi/l (Ise Bay, Aichi) to 0.14 +- 0.012 pCi/l (Yamaguchi Bay, Yamaguchi) and the average value was 0.106 pCi/l. It is clarified that no abnormal values were determined for strontium-90 or cesium-137 contents in coastal sea water around Japan from a fallout origin. (Takagi, S.)

Strontium-90 and cesium-137 in total diet

International Nuclear Information System (INIS)

1977-01-01

Under the commission of Science and Technology Agency, Japan Chemical Analysis Center has analysed total diet samples collected from 30 prefectures (2 times per year), and determined to content of strontium-90 and cesium-137 in these samples. Each Prefectural public health laboratories and institutes have collected all the daily regular diet consumed for five persons, namely three meals and other eating between meals, for radiochemical analysis in polyethylene containers. These samples were collected to Japan Chemical Analysis Center after carbonization without smoke rising in the large stainless dish. At Japan Chemical Analysis Center, these samples were asked in an electric muffle furnance. And the ask 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 filtrates was analysed for strontium-90 and cesium-137 using the method recommended by Science and Technology Agency. (author)

Strontium-90 and cesium-137 in freshwater (from Sept. 1983 to Dec. 1983)

International Nuclear Information System (INIS)

1983-01-01

Fresh water, 100 l each, was collected, and to which the carriers of strontium and cesium were added immediately after the sampling. The sample was vigorously stirred and filtered, and passed through a cation exchange column. Strontium and cesium were eluted with hydrochloric acid from the cation exchange column. The eluate was used for radiochemical analysis. The chemical separation of strontium-90 and cesium-137 was carried out, and the chemical yields were determined. The precipitates were counted for the activity using low background beta counters normally for 60 min. The net sample counting rate was corrected for the counter efficiency, recovery, self-absorption and decay, to obtain the radioactivity per sample aliquot, and the concentrations of these nuclides in the original samples were calculated. The data at six sampling locations in Japan from September to December, 1983, on fresh water are reported. (Kako, I.)

Strontium-90 and cesium-137 in soil (from Jun. 1983 to Sept. 1983)

International Nuclear Information System (INIS)

1983-01-01

Results are presented for the determination of strontium-90 and cesium-137 in soils in Japan. Twenty-seven sampling points were selected all over Japan from Hokkaido to Okinawa by the criteria that the points were spacious and flat without past disturbance and those located in a forest, in a stony area or inside of river banks should be avoided. Soils were taken from two layers of depth, 0 to 5 cm and 5 to 20 cm. After drying, soils were passed through a 2 mm sieve and were employed for radiochemical leaching, separation, and purification of strontium-90 or cesium-137. Radioactivity of strontium-90 or cesium-137 was determined with a low background beta counter normally for 60 minutes. Determined values are presented as pCi/kg and mCi/km 2 for two different depth layers. As for strontium-90 contents, they were ranged from 13.0 +- 3.3 pCi/kg-dry (Aomori, 5 to 20 cm) to 1300 +- 20 pCi/kg-dry (Oota, Shimane Pref., 0 to 5 cm), or from 1.1 +- 0.14 mCi/km 2 (Tsuyama, Okayama Pref., 0 to 5 cm) to 50.0 +- 1.7 mCi/km 2 (Sapporo, 5 to 20 cm). As for cesium-137 contents, they were ranged from 0.5 +- 2.2 pCi/kg-dry (Saga, 5 to 20 cm) to 4700 +- 40 pCi/kg-dry (Oota, Shimane Pref., 0 to 5 cm) or from 0.1 +- 0.42 mCi/km 2 (Saga, 5 to 20 cm) to 120.0 +- 2.0 mCi/km 2 (Oota, Shimane Pref., 5 to 20 cm), and the variance for cesium-137 values were larger than those for strontium-90. Seasonal or local tendency for the contents of the two nuclides were not clarified. (Takagi, S.)

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

International Nuclear Information System (INIS)

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

1980-11-01

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

Sorption and desorption of cesium and strontium on TA-2 and TA-41 soils and sediments

International Nuclear Information System (INIS)

Kung, K. Stephen; Li, Benjamin W.; Longmire, P.A.; Fowler, M.M.

1996-04-01

Current environmental monitoring has detected radioactive contaminants in alluvial groundwater, soils, and sediments in the TA-2 and TA-41 areas along the north central edge of Los Alamos National Laboratory. Because of this contamination, this study was initiated. The objective of this study is to quantify the sorptivity of cesium and strontium onto TA-2 and TA-41 site specific soil samples under a controlled environment in the laboratory. The purposes of this work are to determine cesium and strontium sorption coefficient for these sit specific soils and to evaluate the potential transport of cesium and strontium. Based on this information, a risk assessment and remediation strategy can be developed

Strontium-90 and cesium-137 in soil (from May, 1982, to September, 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in soil measured at 29 locations across Japan from May to September, 1982, are given in pCi/kg and mCi/km 2 , respectively. The methods of the collection and pretreatment of samples, the preparation of samples for analysis, the separation of strontium-90 and cesium-137, the determination of stable strontium, calcium and potassium, and the counting are also described. Soil was collected in the spacious and flat area without past disturbance on the surface. Soil was taken from two layers of different depths, 0 to 5 cm and 5 to 20 cm. The sample solution was prepared and was neutralized with sodium hydroxide. After sodium carbonate was added, the precipitate of strontium and calcium carbonates was separated. The supernatant solution was retained for cesium-137 determination. After the radiochemical separation, the mounted precipitate was counted for activity using a low background beta counter normally for 60 min. The radioactivity ranged 6 to 1300 pCi/Kg for Sr-90 and 1 to 5000 pCi/Kg for Cs-137 in the sampling depth of 0 to 5 cm. (J.P.N.)

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

Science.gov (United States)

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

1995-07-01

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

Effect of K-fertilization, liming and placement on crop uptake of cesium and strontium

International Nuclear Information System (INIS)

Haak, E.

1985-01-01

remedial measures to reduce crop uptake of cesium and strontium under Swedish field conditions have been investigated in micro plot experiments. For cesium the effect of K-fertilization was studied on three soils with oats, peas and mustard and, in combination with placement, on two other soils with wheat, barley and rape. For strontium the effect of liming was studied on three soils with oats, barley and peas and, in combination with placement, on two other soils with wheat, oats, barley and peas. In this paper results are summarized for the grain products. Deep placement of nuclides in combination with K-fertilization and liming reduced the crop uptake of cesium and strontium by a factor of 10 and 4, respectively. On the basis of the experimental results, the practical advantages of K-fertilization and liming, as well as deep ploughing of surface contaminated land are discussed

Strontium-90 and cesium-137 in soil from May 1984 to July 1984

International Nuclear Information System (INIS)

1984-01-01

Strontium-90 and cesium-137 in soil measured throughout Japan from May to July 1984 are given in pCi/kg and mCi/km 2 . Sampling points are total of 8 from Kawabe-gun (Akita) to Ibasuki-gun (Kagoshima). Collection and pretreatment of samples, preparation of samples for analysis, separation of strontium-90 and cesium-137, determination of stable strontium, calcium and potassium, and counting are described. Soil was collected from the location in the spacious and flat area without past disturbance on the surface. Soil was taken from two layers of different depths, 0 aproximately 5 cm and 5 approximately 20 cm. After the radiochemical separation, the mounted precipitates were counted for activity using low background beta counters normally for 60 minutes. (Mori, K.)

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Sorptive removal of cesium-137 and strontium-90 from water by unconventional sorbents. 2. Usage of coal fly ash

International Nuclear Information System (INIS)

Apak, R.; Atun, G.; Gueclue, K.; Tuetem, E.

1996-01-01

It has been shown that coal fly ash is a good adsorbent for both radionuclides of 137 Cs and 90 Sr. Radiocesium adsorption is maximal around the neutral region whereas radiostrontium adsorption increases with pH, especially above pH 8. Cesium retention sharply drops with ionic strength while strontium adsorption increases sharply and steadily at low and moderate concentrations of the inert electrolyte, respectively. The suggested mechanisms of radionuclide retention by fly ash is specific adsorption of Cs + and irreversible ion-exchange uptake of Sr 2+ . The isotherm of adsorption is a Langmuir approximation of the B.E.T. multi-layered sorption. Acid pretreatment of fly ash, though not increasing radionuclide sorption capacity, may be useful in preventing the leach-out of other contaminants from the sorbent into water during the adsorption process. (author)

Radionuclide - Soil Organic Matter Interactions

DEFF Research Database (Denmark)

Carlsen, Lars

1985-01-01

Interactions between soil organic matter, i.e. humic and fulvic acids, and radionuclides of primary interest to shallow land burial of low activity solid waste have been reviewed and to some extent studied experimentally. The radionuclides considered in the present study comprise cesium, strontium...

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

Science.gov (United States)

Ortega, Luis Humberto

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

Co-extraction of Strontium and Cesium by Dicyclohexano-18 Crown-6/25, 27-Bis(2- Propyloxy)Calix[4]-26, 28-Crown-6{sup ..}Cn-Octanol

Energy Technology Data Exchange (ETDEWEB)

Ye, W.L.; Wang, J.CH.; He, Q.G. [Institute of Nuclear and New Energy Technology, Tsinghua University, P.O. Box 1021, Beijing 102201 (China)

2009-06-15

The partitioning of {sup 90}Sr and {sup 137}Cs from high-level liquid waste(HLLW) is one of the important problems for the high-level waste volume reduction and the management of HLLW. The crown ether and calix-crown have the good extracting ability and selectivity to strontium and cesium respectively. Dicyclohexano-18Crown-6 (DCH18C-6) and 25, 27-Bis(2-propyloxy) Calix[4] -26, 28- Crown-6(IPR-C[4]C-6) were selected as extractants and n-octanol was selected as the common diluent to separate strontium and cesium from high-level liquid waste respectively in INET's Tsinghua University, China. But DCH18C- 6 and IPR-C[4]C-6 were used respectively in their processes to separate strontium and cesium. The strontium and cesium processes could be simplified if DCH18C-6 and IPR-C[4]C-6 processes are combined into one process to separate strontium and cesium together. In this paper, the co-extraction performance of strontium and cesium from nitric acid medium was studied by DCH18C-6 /IPR-C[4]C-6 and n-octanol as an diluent. Effects of extractant concentration, nitric concentration and temperature etc. on the extraction performance of strontium and cesium were studied. The results show that DCH18C-6 and IRP-C[4]C-6 in n-octanol has no synergistic extraction ability each other to strontium and cesium. Strontium and cesium were extracted independently by above two extractants. 0.1 mol/L DCH18C-6 and 0.025 mol/L /IPR-C[4]C-6 as extractants and n-octanol as a diluent were selected to separate strontium and cesium from HLLW. The cascade test in which was 10 stages for extraction, 2 stages for scrubbing and 8 stages for stripping was carried out on the miniature centrifugal contactor set. The results are the following: the removing ratios for strontium and cesium in the simulated HLLW were 98.93% and 99.93%, respectively; the stripping ratios of them were 99.80% and 99.79%, respectively. So the mixing extractants could be used to co-extract strontium and cesium from HLLW and

Phenolic cation exchange resin material for recovery of cesium and strontium

Science.gov (United States)

Ebra, Martha A.; Wallace, Richard M.

1983-01-01

A phenolic cation exchange resin with a chelating group has been prepared by reacting resorcinol with iminodiacetic acid in the presence of formaldehyde at a molar ratio of about 1:1:6. The material is highly selective for the simultaneous recovery of both cesium and strontium from aqueous alkaline solutions, such as, aqueous alkaline nuclear waste solutions. The organic resins are condensation polymers of resorcinol and formaldehyde with attached chelating groups. The column performance of the resins compares favorably with that of commercially available resins for either cesium or strontium removal. By combining Cs.sup.+ and Sr.sup.2+ removal in the same bed, the resins allow significant reduction of the size and complexity of facilities for processing nuclear waste.

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

International Nuclear Information System (INIS)

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

1994-12-01

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

Evaluation of distribution coefficients for the prediction of strontium and cesium migration in a uniform sand

International Nuclear Information System (INIS)

Reynolds, W.D.; Gillham, R.W.; Cherry, J.A.

1982-01-01

The validity of using a distribution coefficient (Ksub(d)) in the mathematical prediction of strontium and cesium transport through uniform saturated sand was investigated by comparing measured breakthrough curves with curves of simulations using the advection-dispersion and the advection equations. Values for Ksub(d) were determined by batch equilibration tests and, indirectly, by fitting the mathematical model to breakthrough data from column experiments. Although the advection-dispersion equation accurately represented the breakthrough curves for two nonreactive solutes (chloride and tritium), neither it nor the advection equation provided close representations of the strontium and cesium curves. The simulated breakthrough curves for strontium and cesium were nearly symmetrical, whereas the data curves were very asymmetrical, with long tails. Column experiments with different pore-water velocities indicated that the shape of the normalized breakthrough curves was not sensitive to velocity. This suggests that the asymmetry of the measured curves was the result of nonlinear partitioning of the cations between the solid and liquid phases, rather than nonequilibrium effects. The results indicate that the distribution coefficient, when used in advection-dispersion models for prediction of the migration of strontium and cesium in field situations, can result in significant error

Comparative study of the radionuclide uptake and distribution within plants for barley and maize varieties

International Nuclear Information System (INIS)

Kostyuk, O.

1998-01-01

Differences in the Cs-134 and Sr-85 uptake by three barley and two maize varieties were investigated in a water culture experiment. In barley, the maximum differences were about 30% for cesium and 50% for strontium. The differences between the maize varieties were negligible. The maximum difference between the varieties of the two species of crops was approximately 30% for cesium and 1 70% for strontium with higher radionuclide uptake by maize. All barley varieties accumulated cesium nearly 3.5 times more effectively than strontium, whereas for the maize varieties, cesium was accumulated about 2 times more effectively. There is a large difference in the radionuclide distribution within the plants: the amount of radiocesium in the green part of plants of both species was approximately 30% of the total, while for radiostrontium it was about 80%. As a result, approximately the same amount of the radionuclides were present in the green part of plants, despite the large difference in the uptake of the radionuclides by the whole plants. It is concluded that crop selection as a provision to reduce radionuclide contamination of the food chain should only be applied taking into account the different radionuclide distributions within the plants

Selective cesium and strontium removal for TRU-liquid waste including fission products and concentrated nitric acids

International Nuclear Information System (INIS)

Mimori, T.; Miyajima, K.; Kozeki, M.; Kubota, T.; Tusa, E.; Keskinen, A.

1996-01-01

A nuclide removal system was designed for treatment of liquid radioactive waste at the Japan Atomic Energy Research Institute (JAERI) Tokai site. Total system will include removal of plutonium, cesium and strontium. Removal of plutonium will be carried out by a method developed by JAERI. Removal of cesium and strontium will be carried out by the methods developed in Finland. The whole project will be implemented for JAERI in cooperation between Mitsui Engineering and Shipbuilding and IVO International. This project has been carried out under the Science and Technology Agency (STA) of Japan. The liquid to be treated includes 7.4x10 9 Bq/L of cesium and 7.4x10 9 Bq/L of strontium. The amount of alpha nuclides is 3.7x10 6 Bq/L. Nitric acid concentration is 1.74 mol/L. The volume of 11,000 liters had to be treated in 200 batches of operation. Removal of cesium and strontium is based on the use of new ion exchange materials developed in Finland. These inorganic ion exchange materials have extremely good properties to separate cesium and strontium from even very difficult liquids. Ion exchange material will be used in columns, where there are materials both for cesium and strontium. According to column tests with simulated waste, one 2 liter column will effectively reach the required DF during 10 batches of operation. Purified liquid can be led to further liquid treatment at the site. After treatment of liquids, both used particle filters and used ion exchange columns will be drained and stored to wait for final treatment and disposal. The designed treatment system has a special beneficial feature as it does not produce secondary waste. Final waste is in the form of particle filters or ion exchange columns with material. Used ion exchange columns and filters will be replaced with new ones by means of remote handling. Construction of the treatment system will be scheduled to commence in FY1995 and assemblying at the site in FY1996. (J.P.N.)

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

International Nuclear Information System (INIS)

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

1985-01-01

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

Sorptive removal of cesium-137 and strontium-90 from water by unconventional sorbents. 2. Usage of coal fly ash

Energy Technology Data Exchange (ETDEWEB)

Apak, R.; Atun, G.; Gueclue, K.; Tuetem, E. [Istanbul Univ. (Turkey). Faculty of Engineering

1996-05-01

It has been shown that coal fly ash is a good adsorbent for both radionuclides of {sup 137}Cs and {sup 90}Sr. Radiocesium adsorption is maximal around the neutral region whereas radiostrontium adsorption increases with pH, especially above pH 8. Cesium retention sharply drops with ionic strength while strontium adsorption increases sharply and steadily at low and moderate concentrations of the inert electrolyte, respectively. The suggested mechanisms of radionuclide retention by fly ash is specific adsorption of Cs{sup +} and irreversible ion-exchange uptake of Sr{sup 2+}. The isotherm of adsorption is a Langmuir approximation of the B.E.T. multi-layered sorption. Acid pretreatment of fly ash, though not increasing radionuclide sorption capacity, may be useful in preventing the leach-out of other contaminants from the sorbent into water during the adsorption process. (author).

Extraction of cesium and strontium from nuclear waste

Science.gov (United States)

Davis, Jr., Milton W.; Bowers, Jr., Charles B.

1988-01-01

Cesium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5) [1-hydroxy-2-ethylhexyl]benzo 18-crown-6 compound and a cation exchanger in a matrix solution. Strontium is extracted from acidified nuclear waste by contacting the waste with a bis 4,4'(5') [1-hydroxyheptyl]cyclohexo 18-crown-6 compound, and a cation exchanger in a matrix solution.

Strontium-90 and cesium-137 in soil (from May 1985 to Jul. 1985)

International Nuclear Information System (INIS)

1985-01-01

This report is aimed at listing measurements of strontium-90 and cesium-137 in soil made at eight places across Japan during the period from May to July in 1985. Collection and pretreatment methods are described for samples of rain and dry fallout, airborne dust, service water and freshwater, soil, sea water, sea sediments, total diet, rice, milk, vegetables, tea, as well as fish, shellfish and seaweeds. The methods for the preparation of these samples for analysis are also outlined. Sample solutions were neutralized with sodium hydroxide, and the precipitate of strontium and calcium carbonates was separated after sodium carbonate was added. The supernatant solution was retained for cesium-137 determination. After being precipitated as oxalates, strontium and calcium were separated by successive fuming nitric acid separations. For the determination of stable strontium, calcium and potassium, soil and sediment were treated with sodium hydroxide and hydrochloric acid for extraction while other samples were ashed and digested. Calcium, separated as oxalate, was determined by titration while stable strontium and potassium were determined by atomic absorption and flame emission spectroscopy, respectively. Couting for activity was carried out using low background beta counters normally for 60 min. (Nogami, K.)

Strontium-90 and cesium-137 in sea water (from July, 1982, to September, 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in sea water collected at 11 locations across Japan from July to September, 1982, are given in pCi/l, respectively. The methods of the collection and pretreatment of samples, the preparation of samples for analysis, the separation of strontium-90 and cesium-137, and the counting are also described. Sea water was collected at the fixed station where the effect of the terrestrial fresh water from rivers was negligibly small. The sampling was carried out when there was no rainfall for the last few days. The sample solution was prepared and was neutralized with sodium hydroxide. After sodium carbonate was added, the precipitate of strontium and calcium carbonates was separated. The supernatant solution was retained for cesium-137 determination. After the radiochemical separation, the mounted precipitate was counted for activity using a low background beta counter normally for 60 min. The radioactivity ranged 0.09 to 0.13 pCi/l for Sr-90 and 0.05 to 0.13 pCi/l for Cs-137 in the sea water. (Mori, K.)

Sorption and diffusion of cobalt, strontium, cesium and americium in natural fissure surfaces and drill core cups studied by autoradiography, 1

International Nuclear Information System (INIS)

Pinnioja, S.; Kaemaeraeinen, E.L.; Jaakkola, T.; Siitari, M.; Muuronen, S.; Lindberg, A.

1985-06-01

A method based on autoradiography was developed to determine the diffusion of radionuclides into the rock matrix. To investigate the diffusion the samples, which has been in contact with radioactive tracer solution up to 6 months, were splitted by sawing. From the autoradiograms of the cross sections the penetration depths of radionuclides were determined and the apparent diffusion coefficient Dsup(a) calculated. The filled and unfilled natural fissure surfaces chosen to this study were bars of drilling cores and drill core cups of tonalite, mica gneiss and rapakivi granite. After contact time of 3 months the highest penetration depths of cesium were observed for natural fissure surface sample of rapakivi granite up to 2.5 mm and of mica gneiss up to 3.7 mm. For strontium the penetration depths of 6 mm and 11 mm for unfilled and filled natural fissure samples of rapakivi granite were found. Dsup(a)-values for cesium varied between 1.5 x 10 -15 and 3.2 x 10 -14 , for strontium between 3.5 x 10 -14 and 2.1 x 10 -13 m 2 /s. D-value obtained for cobalt (drill core cup sample, tonalite) was 5.4 x 10 -17 m 2 /s. 241 Am was only sorbed on the surface of the sample and thus no apparent diffusion coefficient could be calculated. Filling materials, chlorite and secondary minerals in tonalite and rapakivi granite increased diffusion into the mother rock. Radionuclides were sorbed both into the filling material and through fillers into the rock matrix. Cs and Sr penetrated though calcite filling material in mica gneiss into the mother rock. Calcite didn't influence on diffusion of radionuclides. Penetration depths of Cs and Sr were about the same for filled and unfilled samples

Membrane-based separation technologies for cesium, strontium, and technetium

International Nuclear Information System (INIS)

Kafka, T.

1996-01-01

This work is one of two parallel projects that are part of an ESP task to develop high-capacity, selective, solid extractants for cesium, strontium, and technetium from nuclear wastes. In this subtask, Pacific Northwest National Laboratory (PNNL) is collaborating with 3M, St. Paul, Minnesota, working in cooperation with IBC Advanced Technologies, American Fork, Utah

A study of the properties of hexacyanoferrate sorbents and their use for sorption of caesium and strontium

International Nuclear Information System (INIS)

Kareta, V.I.; Grivkova, A.I.; Artemova, T.N.; Mizina, L.I.; Krasavina, E.P.

1997-01-01

A method of deposition of zinc, copper, and nickel hexacyanaferrates on silica-containing substrate (clinoptilolite) has been developed to produce mechanically strong sorbents for cesium and strontium separation from solutions of different compositions. The modification of clinoptilolite increases its sorption capacity for both cesium and strontium. Sorption behaviour of radionuclides was studied both in static and kinetic conditions. (author). 21 refs, 5 figs, 7 tabs

Transfer of some artificial (strontium 85 and caesium 137) and natural (potasium 40 and radium 226) radionuclides from milk to its products

International Nuclear Information System (INIS)

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

2004-12-01

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)

Phenolic cation-exchange resin material for recovery of cesium and strontium. [Patent application

Science.gov (United States)

Ebra, M.A.; Wallace, R.M.

1982-05-05

A phenolic cation exchange resin with a chelating group has been prepared by reacting resorcinol with iminodiacetic acid in the presence of formaldehyde at a molar ratio of about 1:1:6. The material is highly selective for the simultaneous recovery of both cesium and strontium from aqueous alkaline solutions, such as, aqueous alkaline nuclear wate solutions. The organic resins are condensation polymers of resorcinol and formaldehyde with attached chelating groups. The column performance of the resins compares favorably with that of commercially available resins for either cesium or strontium removal. By combining Cs/sup +/ and Sr/sup 2 +/ removal in the same bed, the resins allow significant reduction of the size and complexity of facilities for processing nuclear waste.

Strategic Design and Optimization of Inorganic Sorbents for Cesium, Strontium and Actinides

International Nuclear Information System (INIS)

Maginn, Edward J.

2009-01-01

The primary objective of the Notre Dame component of the project was computational in nature. The goal was to provide a design tool for the synthesis of optimized sorbents for the removal of cesium, strontium and actinides from nuclear waste solutions. Molecular modeling enables us to observe and better understand the molecular level interactions that govern the selectivity of specific radionuclides in a particular sorbent. The research focused on the development and validation of a suitable and transferable model for all the cations and ion exchangers of interest, nd then subsequent simulations which determined the siting and mobility of water and cations. Speciic accomplishments include: (1) improving existing intermolecular force fields to accurately model the sorbents of interest; (2) utilizing energy-minimizations and molecular dynamics simulations for structural prediction of CST and niobium-substituted CST materials; (3) determining Na+/water positions in polyoxoniobate materials using molecular dynamics simulations; and (4) developing Hybrid Monte Carlo methods for improved structural prediction.

Leachability of radionuclides from cement solidified waste forms produced at operating nuclear power plants

International Nuclear Information System (INIS)

Croney, S.T.

1985-03-01

This study determined the leachability indexes of radionuclides contained in solidified liquid wastes from operating nuclear power plants. Different sizes of samples of cement-solidified liquid wastes were collected from two nuclear power plants - a pressurized water reactor and a boiling water reactor - to correlate radionuclide leaching from small- and full-sized (55-gallon) waste forms. Diffusion-based model analysis (ANS 16.1) of measured radionuclide leach data from both small- and full-sized samples was performed and indicate that leach data from small samples can be used to determine leachability indexes for full-sizes waste forms. The leachability indexes for cesium, strontium, and cobalt isotopes were determined for waste samples from both plants according to the models used for ANS 16.1. The leachability indexes for the pressurized water reactor samples were 6.4 for cesium, 7.1 for strontium, and 10.4 for cobalt. Leachability indexes for the boiling water reactor samples were 6.5 for cesium, 8.6 for strontium, and 11.1 for cobalt

Removal efficiency of water purifier and adsorbent for iodine, cesium, strontium, barium and zirconium in drinking water.

Science.gov (United States)

Sato, Itaru; Kudo, Hiroaki; Tsuda, Shuji

2011-01-01

The severe incident of Fukushima Daiichi Nuclear Power Station has caused radioactive contamination of environment including drinking water. Radioactive iodine, cesium, strontium, barium and zirconium are hazardous fission products because of the high yield and/or relatively long half-life. In the present study, 4 pot-type water purifiers and several adsorbents were examined for the removal effects on these elements from drinking water. Iodide, iodate, cesium and barium were removed by all water purifiers with efficiencies about 85%, 40%, 75-90% and higher than 85%, respectively. These efficiencies lasted for 200 l, which is near the recommended limits for use of filter cartridges, without decay. Strontium was removed with initial efficiencies from 70% to 100%, but the efficiencies were slightly decreased by use. Zirconium was removed by two models, but hardly removed by the other models. Synthetic zeolite A4 efficiently removed cesium, strontium and barium, but had no effect on iodine and zirconium. Natural zeolite, mordenite, removed cesium with an efficiency as high as zeolite A4, but the removal efficiencies for strontium and barium were far less than those of zeolite A4. Activated carbon had little removal effects on these elements. In case of radioactive contamination of tap water, water purifiers may be available for convenient decontamination of drinking water in the home.

Strontium-90 and cesium-137 in service water from June to December, 1981

International Nuclear Information System (INIS)

1981-01-01

Service water, 100 l each, was collected at an intake of a water treatment plant and at a tap after water was left running for five minutes. The carriers of strontium and cesium were added to water immediately after sampling, and the sample was vigorously stirred and filtered. Then it was passed through a cation exchange column at a rate of 80 ml/min. Strontium and cesium were eluted with hydrochloric acid from the cation exchange column, and separated. After the radiochemical separation, the mounted precipitates were counted for activity using low background beta counters normally for 60 min. Net sample counting rates were corrected for counter efficiency, recovery, self absorption and decay to obtain the content of strontium-90 and cesium-137 radioactivity per sample aliquot. From the results, concentrations of these nuclides in the original sample were calculated. The maximum values obtained were 0.29 pCi/l of Sr-90 in Kyoto in August, 1981, and 0.02 pCi/l of Cs-137 in Kyoto in August and in Inuyama in December, 1981, in case of source water. In case of tap water, they were 0.18 pCi/l of Sr-90 in Kobe in December, 1981, and 0.02 pCi/l of Cs-137 in Kyoto in August, 1981. (Kako, I.)

Water-Mediated Differential Binding of Strontium and Cesium Cations in Fulvic Acid.

Science.gov (United States)

Sadhu, Biswajit; Sundararajan, Mahesh; Bandyopadhyay, Tusar

2015-08-27

The migration of potentially harmful radionuclides, such as cesium ((137)Cs) and strontium ((90)Sr), in soil is governed by the chemical and biological reactivity of soil components. Soil organic matter (SOM) that can be modeled through fulvic acid (FA) is known to alter the mobility of radionuclide cations, Cs(+) and Sr(2+). Shedding light on the possible interaction mechanisms at the atomic level of these two ions with FA is thus vital to explain their transport behavior and for the design of new ligands for the efficient extraction of radionuclides. Here we have performed molecular dynamics, metadynamics simulations, and density-functional-theory-based calculations to understand the binding mechanism of Sr(2+) and Cs(+) cations with FA. Our studies predict that interaction of Cs(+) to FA is very weak as compared with Sr(2+). While the water-FA interaction is largely responsible for the weak binding of Cs(+) to FA, leading to the outer sphere complexation of the ion with FA, the interaction between Sr(2+) and FA is stronger and thus can surpass the existing secondary nonbonding interaction between coordinated waters and FA, leading to inner sphere complexation of the ion with FA. We also find that entropy plays a dominant role for Cs(+) binding to FA, whereas Sr(2+) binding is an enthalpy-driven process. Our predicted results are found to be in excellent agreement with the available experimental data on complexation of Cs(+) and Sr(2+) with SOM.

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

International Nuclear Information System (INIS)

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

1991-09-01

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

Radioactivity: radionuclides in foods

International Nuclear Information System (INIS)

Simpson, R.E.; Baratta, E.J.; Jelinek, C.F.

1977-01-01

The results are summarized of the analysis for strontium-90, cesium-137, iodine-131, ruthenium-106, and potassium-40, a naturally occurring radionuclide, in samples of total diet and selected import commodities in the foods compliance program of the Food and Drug Administration. On the basis of the radionuclide intake guidelines established by the Federal Radiation Council (FRC), the low content of radionuclides found in the total diet samples for fiscal years 1973 and 1974 demonstrates the need for surveillance only at the present level. The low levels of radionuclides found in a limited number of edible imported commodities indicate that their contribution to the total diet would not increase the levels of these radionuclides above those recommended for only periodic surveillance by the FRC. The potassium levels, determined from potassium-40 activity, found in meats and fish agree with the value for normal muscle tissue for the reference man reported by the International Commission on Radiation Protection. Of the other commodities, nuts contained the highest levels, while sugar, beverages, and processed foods contained the lowest levels of potassium. Although cesium and potassium are chemical analogs with similar metabolic properties, because of their variable content in some leafy samples as a result of surface contamination, a correlation between cesium-137 levels and the cesium-137-to-potassium ratio was inconclusive

Solvent for the simultaneous recovery of radionuclides from liquid radioactive wastes

Science.gov (United States)

Romanovskiy, Valeriy Nicholiavich; Smirnov, Igor V.; Babain, Vasiliy A.; Todd, Terry A.; Brewer, Ken N.

2002-01-01

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

Ability of phytoremediation for absorption of strontium and cesium from soils using Cannabis sativa

Directory of Open Access Journals (Sweden)

Parisa Seyed Hoseini

2012-01-01

Conclusion: Our findings suggest that strontium can be absorbed by Cannabis sativa, with the highest absorption by the roots, stems, and leaves. However, cesium does not reach the plant because of its single capacity and inactive complex formation.

Strontium-90 and cesium-137 in milk (consuming districts) (from May 1982 to Aug. 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in milk (consuming districts from May to Aug. 1982) were determined. Commercial milk was purchased in 20 consuming districts. The results are shown in a table. (Namekawa, K.)

Recent developments in nanostructured inorganic materials for sorption of cesium and strontium: Synthesis and shaping, sorption capacity, mechanisms, and selectivity-A review.

Science.gov (United States)

Alby, Delhia; Charnay, Clarence; Heran, Marc; Prelot, Bénédicte; Zajac, Jerzy

2018-02-15

Liquid wastes containing non-ferrous heavy metal ions and some radionuclides, 137 Cs and 90 Sr in particular, represent one of the most dangerous sources of environmental contamination. The remediation of wastewater containing such pollutants continue to be among the biggest challenges of Sustainable Development and Environmental Safety. Sorption-based technologies have proven their efficiency also in reducing the radionuclide content in aqueous streams to low-level residual activity, with the concomitant decrease in the amount of ultimate solid waste generated. Although sorption of cesium and strontium by resins, clays, and zeolites has been investigated intensively and even used in real applications, there is still considerable scope for improvement in terms of retention capacity and selectivity. Recent progress in design and preparation of nanostructured inorganic materials has attracted growing interest based on the potential for improving the retention performance when coupling such functionalities as ion exchange capacity, structural flexibility that may result in steric retention effects, as well as the propensity to interact specifically with the target metal cations. Titanate, vanadate, and tungsten based materials, manganese oxides, hexacyanoferrates, metal sulfides, ammonium molybdophosphates, or hydroxyapatite, characterized by various structures and morphologies, are reviewed with the emphasis being put on synthesis and shaping of such materials, their structure in relationship with the capacity and selectivity of trapping cesium and strontium from either single or multi-component aqueous solutions, as well as the possible retention mechanism. The potential candidates for remediation uses are selected with regard to their sorption capacity and distribution coefficient towards target cations, and also the pH window for an optimum cation capture. Copyright © 2017 Elsevier B.V. All rights reserved.

Removal of cesium and separation of strontium the analysis of the leachate of spent fuel

International Nuclear Information System (INIS)

Kim, Seung Soo; Chun, Kwan Sik; Kang, Chul Hyung

2002-01-01

The selective removal of cesium by ammonium molybdophosphate (AMP) was studied in order to reduce an interference by high radioactivity of cesium on the determination of low radioactive elements in leachate of spent fuel. The removal of Cs, U, Ce, La, Co, Na Sr and K was investigated for the leachate and the bentonite in contact with a spent fuel. More than 90% of cesium was removed by AMP and Ca, Na, Co and Sr was remained in 0.1M HNO 3 . However, three valence elements such as La and Ce were also removed by AMP. Though a little of potassium of the bentonite components was adsorbed on AMP, the potassium in the bentonite solution diluted to its concentration in a real sample would not affect the capacity of AMP greatly. From another experiment for the separation of strontium as a leaching indicator of spent fuel, the recovery of strontium in 8.0 M HNO 3 solution by using Sr-resin (Eichrom, P/N SR-B50-A) was more than 95% by eluting with 0.05 M HNO 3

Bentonite-Clay Waste Form for the Immobilization of Cesium and Strontium from Fuel Processing Waste Streams

Energy Technology Data Exchange (ETDEWEB)

Kaminski, Michael D. [Argonne National Lab. (ANL), Argonne, IL (United States); Mertz, Carol J. [Argonne National Lab. (ANL), Argonne, IL (United States)

2016-01-01

The physical properties of a surrogate waste form containing cesium, strontium, rubidium, and barium sintered into bentonite clay were evaluated for several simulant feed streams: chlorinated cobalt dicarbollide/polyethylene glycol (CCD-PEG) strip solution, nitrate salt, and chloride salt feeds. We sintered bentonite clay samples with a loading of 30 mass% of cesium, strontium, rubidium, and barium to a density of approximately 3 g/cm³. Sintering temperatures of up to 1000°C did not result in volatility of cesium. Instead, there was an increase in crystallinity of the waste form upon sintering to 1000ºC for chloride- and nitrate-salt loaded clays. The nitrate salt feed produced various cesium pollucite phases, while the chloride salt feed did not produce these familiar phases. In fact, many of the x-ray diffraction peaks could not be matched to known phases. Assemblages of silicates were formed that incorporated the Sr, Rb, and Ba ions. Gas evolution during sintering to 1000°C was significant (35% weight loss for the CCD-PEG waste-loaded clay), with significant water being evolved at approximately 600°C.

Strontium-90 and cesium-137 in milk (consuming districts) (from May. 1982 to Mar. 1983)

International Nuclear Information System (INIS)

1983-01-01

Strontium-90 and cesium-137 in milk (consuming districts from May 1982 to Mar. 1983) were determined. Commercial milk was purchased in 25 consuming districts. The results are shown in a table. (J.P.N.)

Radionuclides in Canada goose eggs

International Nuclear Information System (INIS)

Rickard, W.H.; Sweany, H.A.

1975-01-01

Low levels of radionuclides were measured in Canada goose eggs taken from deserted nests from Columbia River islands on the Energy Research and Development Administration's Hanford Reservation. Potassium-40, a naturally occurring radionuclide, was the most abundant radionuclide measured in egg contents and egg shell. Strontium-90 was incorporated into egg shells and cesium-137 into inner egg contents. Manganese-54, cobalt-60, and zinc-65 were more abundant in inner egg contents than in egg shell. Cerium-144 was detected in egg shell but not in inner shell

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

Energy Technology Data Exchange (ETDEWEB)

Moore, J.G.

1976-09-01

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

Radionuclides in Tissues of Marine Birds

International Nuclear Information System (INIS)

Lebedeva, N.; Matishov, D.

2004-01-01

The birds are higher links of trophic nets of marine ecosystems and are capable to store in organs and tissues radionuclides. We can inspect radionuclides contents in marine ecosystems on a their contents of in birds. Objects of our research were marine birds, including seagull (the Herring gull Larus aregentatus, the Great Blackback Larus marinus), the Black guillemot Cepphus grylle, the Eider Somateria mollissima, the Cormorant Phalacrocorax carbo and the Arctic Stercorarius parasiticus. Researches were conducted in August 2000 and 2001 near to the biological station of Murmansk Marine Biological Institute in a point Dalnije Zelentsy on the cost of the Sea Barents. Contents of plutonium-239, 240, cesium-137 and strontium-90 in bones, skin and fatherless and muscles of birds were researched. The contents of cesium - 137 varied from 0,99 Bq/kg in a skin and feathers of the Herring gull up to 177 Bq/kg in muscles of the Great Blackback, the contents strontium-90 varied from 25 mBq/kg in a skin and feathers of the Cormorant up to 7140 mBq/kg in bones the Eider. The contents of plutonium-239,240 varied from 1,8 mBq/kg in muscles of the Eider up to 23 mBq/kg in skeleton of the Great Blackback. The content of this radionuclide was higher for adult, i.e. was enlarged with age. Higher concentrations in tissues are founded for the Eider and the Great Blackback. So, the average concentrations of cesium - 137 in muscles the Eider have constituted 1,5 Bq/kg, the Great Blackback -73,5 Bq/kg, the Black guillemot -16 Bq/kg, the Arctic scua - 1,3 Bq/kg, the Herring gull - 8,7 Bq/kg. Average concentrations of cesium - 137 in bones of the Eider were1,6 Bq/kg, the Great Blackback - 19,8Bq/kg, the Herring gull - 2,2 Bq/kg. The average concentrations strontium-90 in a skin and feathers of the Cormorant were 20 mBq/kg, the Great Blackback - 1288 mBq/kg, the Herring gull - 690 mBq/kg. It is founded that distribution the contents of strontium-90 in bones significantly varies from species

Behavior of strontium-90 and cesium-137 released into the pond of Office of Atomic Energy for Peace

International Nuclear Information System (INIS)

Milintawisamai, Mesak; Panyathipsakul, Yureeporn

1989-01-01

Strontium-90 and cesium-137 in liquid waste released from the waste disposal plant of Office of Atomic Energy for Peace(OAEP) have been followed since 1984. The concentration of both nuclides in surface water outside OAEP boundary is 2 to 30 times less than in the OAEP pond, the reservoir of liquid waste. This indicates that most of the nuclides are effectively absorbed by clay in the bottom of the pond. The nuclide concentration in fresh-water organisms in the pond such as fish, prawn and snail is also investigated to elucidate the behavior of strontium-90 and cesium-137 in a static fresh-water ecological system

Strontium-90 and cesium-137 in service water from December, 1981, to July, 1982

International Nuclear Information System (INIS)

1982-01-01

Service water, 100 liters each, was collected at an intake of a water-treatment plant and at a tap after water was left running for five minutes. Water, to which the carriers of strontium and cesium were added immediately after sampling, was vigorously stirred and filtered. The sample was then passed through a cation exchange column. After radiochemical separation, the precipitates were counted for the activity using a low-background beta counter, normally for 60 min. The measuring techniques are first described; i.e. the collection and pretreatment of samples, the preparation of samples for analysis, the separation of strontium-90 and cesium-137, and the counting. The measured results are given in a table for the following locations: source water - Tokyo, Osaka, Hokkaido, Kyoto, Kanagawa, Aichi, Fukuoka; tap water - Hokkaido, Akita, Fukushima, Tokyo, Fukui, Shizuoka, Shimane, Okayama, Fukuoka, Saga, Nagasaki, Kyoto, Wakayama, Okinawa, Hiroshima, Aomori, Yamagata, Ibaraki, Kanagawa, Niigata, Ishikawa, Nagano, Aichi, Osaka, Hyogo, Tottori, Yamaguchi, Ehime, Kochi, Kagoshima. (Mori, K.)

Method for the simultaneous recovery of radionuclides from liquid radioactive wastes using a solvent

Science.gov (United States)

Romanovskiy, Valeriy Nicholiavich; Smirnov, Igor V.; Babain, Vasiliy A.; Todd, Terry A.; Brewer, Ken N.

2001-01-01

The present invention relates to solvents, and methods, for selectively extracting and recovering radionuclides, especially cesium and strontium, rare earths and actinides from liquid radioactive wastes. More specifically, the invention relates to extracting agent solvent compositions comprising complex organoboron compounds, substituted polyethylene glycols, and neutral organophosphorus compounds in a diluent. The preferred solvent comprises a chlorinated cobalt dicarbollide, diphenyl-dibutylmethylenecarbamoylphosphine oxide, PEG-400, and a diluent of phenylpolyfluoroalkyl sulfone. The invention also provides a method of using the invention extracting agents to recover cesium, strontium, rare earths and actinides from liquid radioactive waste.

Strontium-90 and cesium-137 in rice (consuming districts) (from Nov. 1982 to Jan. 1983)

International Nuclear Information System (INIS)

1983-01-01

Strontium-90 and cesium-137 in rice (consuming districts from Nov. 1982 to Jan. 1983) were determined. Polished rice was collected in eight consuming areas when new crops were first put on sale. The results are shown in a table. (J.P.N.)

Comparison of inorganic ion exchange materials for removing cesium, strontium, and transuranic elements from K-basin water

International Nuclear Information System (INIS)

Brown, G.N.; Bontha, J.R.; Carson, K.J.; Elovich, R.J.; DesChane, J.R.

1997-10-01

The work presented in this report was conducted by the Pacific Northwest National Laboratory (PNNL) under the Efficient Separations and Crosscutting Program (ESP), Office of Science and Technology, U.S. Department of Energy (DOE). The objective of this work was to investigate radionuclide uptake by several newly produced ion exchange materials under actual waste conditions, and to compare the performance of those materials with that of commercially available ion exchangers. The equilibrium uptake data presented in this report are useful for identifying potential materials that are capable of removing cesium and strontium from 105-KE Basin water. The data show the relative selectivities of the ion exchange materials under similar operating conditions. Additional flow studies are needed to predict material capacities and to develop complete ion exchange process flow sheets. The materials investigated in this study include commercially available ion exchangers such as IONSIV reg-sign IE-911 (manufactured by UOP), clinoptilolite (a naturally occurring zeolite), and materials produced on an experimental basis by AlliedSignal (biotites and nonatitanates), 3M (hexacyanoferrates), Selion Technologies, Inc. (hexacyanoferrates and titanates), and Texas A ampersand M University (pharmacosiderites, biotites, and nonatitanates). In all, the performance of 14 ion exchange materials was evaluated at two solution-to-exchanger mass ratios (i.e., 10 4 and 10 5 ) using actual 105-KE Basin water. Evaluation consisted of determining cesium and strontium batch distribution coefficients, loading, and decontamination factors. Actual 105-KE Basin water was obtained from a sample collected during the sludge dissolution work conducted by PNNL in FY 1996. This sample was taken from the bottom of the basin and contained significantly higher concentrations of the radioactive constituents than do samples taken from the top of the basin

Comparison of inorganic ion exchange materials for removing cesium, strontium, and transuranic elements from K-basin water

Energy Technology Data Exchange (ETDEWEB)

Brown, G.N.; Bontha, J.R.; Carson, K.J.; Elovich, R.J.; DesChane, J.R.

1997-10-01

The work presented in this report was conducted by the Pacific Northwest National Laboratory (PNNL) under the Efficient Separations and Crosscutting Program (ESP), Office of Science and Technology, U.S. Department of Energy (DOE). The objective of this work was to investigate radionuclide uptake by several newly produced ion exchange materials under actual waste conditions, and to compare the performance of those materials with that of commercially available ion exchangers. The equilibrium uptake data presented in this report are useful for identifying potential materials that are capable of removing cesium and strontium from 105-KE Basin water. The data show the relative selectivities of the ion exchange materials under similar operating conditions. Additional flow studies are needed to predict material capacities and to develop complete ion exchange process flow sheets. The materials investigated in this study include commercially available ion exchangers such as IONSIV{reg_sign} IE-911 (manufactured by UOP), clinoptilolite (a naturally occurring zeolite), and materials produced on an experimental basis by AlliedSignal (biotites and nonatitanates), 3M (hexacyanoferrates), Selion Technologies, Inc. (hexacyanoferrates and titanates), and Texas A&M University (pharmacosiderites, biotites, and nonatitanates). In all, the performance of 14 ion exchange materials was evaluated at two solution-to-exchanger mass ratios (i.e., 10{sup 4} and 10{sup 5}) using actual 105-KE Basin water. Evaluation consisted of determining cesium and strontium batch distribution coefficients, loading, and decontamination factors. Actual 105-KE Basin water was obtained from a sample collected during the sludge dissolution work conducted by PNNL in FY 1996. This sample was taken from the bottom of the basin and contained significantly higher concentrations of the radioactive constituents than do samples taken from the top of the basin.

Strontium-90 and cesium-137 in total diet (from Jun. 1982 to Dec. 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in total diet (from Jun. to Dec. 1982) were determined. A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 22 sampling locations. The results are shown in a table. (Namekawa, K.)

Strontium-90 and cesium-137 in sea fish (from Oct. 1981 to Jun. 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in sea fishes (from Oct. 1981 to Jun. 1982) were determined. Fish was collected from eight sampling locations. Only the edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. The results are shown in a table. (Namekawa, K.)

Strontium-90 and cesium-137 in sea fish (from Jun. 1982 to Dec. 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in sea fish (from Jun. to Dec. 1982) were determined. Fish was collected from 22 sampling locations. Only the edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. The results are sown in a table. (Namekawa, K.)

Strontium-90 and cesium-137 in sea water from July, 1981, to January, 1982

International Nuclear Information System (INIS)

1981-01-01

Sea water was collected at fixed stations where the effect of terrestrial fresh water from rivers was expected to be negligibly small. Weather conditions were also considered, and the sampling was carried out after a few days in which rain did not fall. Attention was paid to avoid the contamination in sampling and storing. The sample was stored in 20 l polyethylene containers in the acidified state of pH lower than 3. 200 ml of sea water was also collected at the same stations for the determination of chlorinity. The radiochemical separation of strontium-90 and cesium-137 was performed, and the mounted precipitates were counted for activity using low background beta counters normally for 60 min. Net sample counting rates were corrected to obtain the content of strontium-90 and cesium-137 radioactivity per sample aliquot, and concentrations of these nuclides in the original sample were calculated. The maximum values obtained were 0.16 pCi/l of Sr-90 in Osaka-bay and 0.17 pCi/l of Cs-137 in Mutsu-bay in August, 1981. (Kako, I.)

Strontium-90 and cesium-137 in total diet (from Nov. 1982 to Jun. 1983)

International Nuclear Information System (INIS)

1983-01-01

Strontium-90 and cesium-137 in total diet (from Nov. 1982 to Jun. 1983) were determined. A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 26 sampling locations. The results are shown in a table. (J.P.N.)

Strontium-90 and cesium-137 in total diet (from Oct. 1981 to Jul. 1982)

International Nuclear Information System (INIS)

1982-01-01

Strontium-90 and cesium-137 in total diet (from Oct. 1981 to Jul. 1982) were determined. A full one day ordinary diet including three meals, water, tea and other in-between snacks for five persons was collected as a sample of ''total diet'' from 26 sampling locations. The results are shown in a table. (Namekawa, K.)

Strontium-90 and cesium-137 in sea fish (from Nov. 1982 to Jun. 1983)

International Nuclear Information System (INIS)

1983-01-01

Strontium-90 and cesium-137 in sea fish (from Nov. 1982 to Jun. 1983) were determined. Fishes were collected from eight sampling locations. Only the edible part was used in case of larger sized fish, and the whole part was used in case of smaller ones. The results are shown in a table. (J.P.N.)

DEVELOPMENT OF PROTOTYPE TITANATE ION EXCHANGE LOADED MEMBRANES FOR STRONTIUM, CESIUM AND ACTINIDE DECONTAMINATION FROM AQUEOUS MEDIA

Energy Technology Data Exchange (ETDEWEB)

Oji, L; Keisha Martin, K; David Hobbs, D

2008-05-30

We have successfully incorporated high surface area particles of titanate ion exchange materials (monosodium titanate and crystalline silicotitanate) with acceptable particle size distribution into porous and inert support membrane fibrils consisting of polytetrafluoroethylene (Teflon{reg_sign}), polyethylene and cellulose materials. The resulting membrane sheets, under laboratory conditions, were used to evaluate the removal of surrogate radioactive materials for cesium-137 and strontium-90 from high caustic nuclear waste simulants. These membrane supports met the nominal requirement for nonchemical interaction with the embedded ion exchange materials and were porous enough to allow sufficient liquid flow. Some of this 47-mm size stamped out prototype titanium impregnated ion exchange membrane discs was found to remove more than 96% of dissolved cesium-133 and strontium-88 from a caustic nuclear waste salt simulants. Since in traditional ion exchange based column technology monosodium titanate (MST) is known to have great affinity for the sorbing of other actinides like plutonium, neptunium and even uranium, we expect that the MST-based membranes developed here, although not directly evaluated for uptake of these three actinides because of costs associated with working with actinides which do not have 'true' experimental surrogates, would also show significant affinity for these actinides in aqueous media. It was also observed that crystalline silicotitanate impregnated polytetrafluoroethylene or polyethylene membranes became less selective and sorbed both cesium and strontium from the caustic aqueous salt simulants.

Sorption of cesium and strontium from concentrated brines by backfill barrier materials

International Nuclear Information System (INIS)

Winslow, C.D.

1981-03-01

The sorption of radionuclides from potentially intruding groundwater at a nuclear waste repository is a major chemical function of backfill barriers. In this study, various materials (including clays, zeolites and an inorganic ion exchanger) were screened for the sorption of the fission products cesium and strontium in concentrated brines. Representative brines A and B for the Waste Isolation Pilot Plant (WIPP), a proposed radioactive waste repository and test facility in bedded salt were used. Sorption properties were quantified using empirical distribution coefficients, k/sub d/. Of the materials examined, sodium titanate had the highest k/sub d/ for the sorption of Sr(II) in both brine A (k/sub d/ = 125 ml/g) and brine B(k/sub d/ = 500 to 600 ml/g). A mordenite-type zeolite was the most effective getter for Cs(I) in brine A (k/sub d = 27 ml/g), while illite yielded the highest k/sub d/ for Cs(I) in brine B (k/sub d/ = 115 ml/g). The relative merit of these k/sub d/ values is evaluated in terms of calculated estimates of breakthrough times for a backfill barrier containing the getter. Results show that a backfill mixture containing these getters is potentially an effective barrier to the migration of Sr(II) and Cs(I), although further study (especially for the sorption of cesium from brine A) is recommended. Initial mechanistic studies revealed competing ion effects which would support an ion exchange mechanism. K/sub d/'s were constant over a Sr(II) concentration range of 10 -11 to 10 -5 M and a Cs(I) concentration range of 10 -8 to 10 -5 M, supporting the choice of a linear sorption isotherm as a model for the results. Constant batch composition was shown to be attained within one week

Surveillance of Strontium-90 in Foods after the Fukushima Daiichi Nuclear Power Plant Accident.

Science.gov (United States)

Nabeshi, Hiromi; Tsutsumi, Tomoaki; Uekusa, Yoshinori; Hachisuka, Akiko; Matsuda, Rieko; Teshima, Reiko

2015-01-01

As a result of the Fukushima Daiichi nuclear power plant (NPP) accident, various radionuclides were released into the environment. In this study, we surveyed strontium-90 ((90)Sr) concentrations in several foodstuffs. Strontium-90 is thought to be the third most important residual radionuclide in food collected after the Fukushima Daiichi, NPP accident after following cesium-137 ((137)Cs) and cesium-134 ((134)Cs). Results of (90)Sr analyses indicated that (90)Sr was detect in 25 of the 40 radioactive cesium (r-Cs) positive samples collected in areas around the Fukushima Daiichi NPP, ranging in distance from 50 to 250 km. R-Cs positive samples were defined as containing both (134)Cs and (137)Cs which are considered to be indicators of the after-effects of the Fukushima Daiichi NPP accident. We also detected (90)Sr in 8 of 13 r-Cs negative samples, in which (134)Cs was not detected. Strontium-90 concentrations in the r-Cs positive samples did not significantly exceed the (90)Sr concentrations in r-Cs negative samples or the (90)Sr concentration ranges in comparable food groups found in previous surveys before the Fukushima Daiichi NPP accident. Thus, (90)Sr concentrations in r-Cs positive samples were indistinguishable from the background (90)Sr concentrations arising from global fallout prior to the Fukushima accident, suggesting that no marked increase of (90)Sr concentrations has occurred in r-Cs positive samples as a result of the Fukushima Daiichi NPP accident.

Performance evaluation of 24 ion exchange materials for removing cesium and strontium from actual and simulated N-Reactor storage basin water

Energy Technology Data Exchange (ETDEWEB)

Brown, G.N.; Carson, K.J.; DesChane, J.R.; Elovich, R.J.

1997-09-01

This report describes the evaluation of 24 organic and inorganic ion exchange materials for removing cesium and strontium from actual and simulated waters from the 100 Area 105 N-Reactor fuel storage basin. The data described in this report can be applied for developing and evaluating ion exchange pre-treatment process flowsheets. Cesium and strontium batch distribution ratios (K{sub d}`s), decontamination factors (DF), and material loadings (mmol g{sup -1}) are compared as a function of ion exchange material and initial cesium concentration. The actual and simulated N-Basin waters contain relatively low levels of aluminum, barium, calcium, potassium, and magnesium (ranging from 8.33E-04 to 6.40E-05 M), with slightly higher levels of boron (6.63E-03 M) and sodium (1.62E-03 M). The {sup 137}Cs level is 1.74E-06 Ci L-{sup 1} which corresponds to approximately 4.87E-10 M Cs. The initial Na/Cs ratio was 3.33E+06. The concentration of total strontium is 4.45E-06 M, while the {sup 90}Sr radioactive component was measured to be 6.13E-06 Ci L{sup -1}. Simulant tests were conducted by contacting 0.067 g or each ion exchange material with approximately 100 mL of either the actual or simulated N-Basin water. The simulants contained variable initial cesium concentrations ranging from 1.00E-04 to 2.57E- 10 M Cs while all other components were held constant. For all materials, the average cesium K{sub d} was independent of cesium concentration below approximately 1.0E-06 M. Above this level, the average cesium K{sub d} values decreased significantly. Cesium K{sub d} values exceeding 1.0E+07 mL g{sup -1} were measured in the simulated N-Basin water. However, when measured in the actual N-Basin water the values were several orders of magnitude lower, with a maximum of 1.24E+05 mL g{sup -1} observed.

Cesium removal flow studies using ion exchange

International Nuclear Information System (INIS)

Lee, D.D.; Walker, J.F. Jr.; Taylor, P.A.

1997-01-01

Cesium and strontium radionuclides are a small fraction of the mainly sodium and potassium salts in underground storage tank supernatant at US Department of Energy (DOE) sites at Hanford, Oak Ridge, Savannah River, and Idaho that DOE must remediate. Cesium-137 ( 137 Cs) is the primary gamma radiation source in the dissolved tank waste at these sites, and its removal from the supernatant can reduce the hazard and waste classification of the treated waste reducing the further treatment and disposal costs. Several cesium removal sorbents have been developed by private industry and the US DOE's Office of Science and Technology. Several of these removal technologies have been previously tested in small batch and column tests using simulated and a few actual supernatant under DOE's Environmental Management (EM) programs including the Tanks Focus Area (TFA) and the Efficient Separations and Processing (ESP) Cross-Cutting Program

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

Energy Technology Data Exchange (ETDEWEB)

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

2013-07-01

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

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

International Nuclear Information System (INIS)

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

2013-01-01

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

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

International Nuclear Information System (INIS)

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

2014-01-01

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

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

Energy Technology Data Exchange (ETDEWEB)

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

2014-07-01

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

Sorption of strontium on uranyl peroxide: implications for a high-level nuclear waste repository.

Science.gov (United States)

Sureda, Rosa; Martínez-Lladó, Xavier; Rovira, Miquel; de Pablo, Joan; Casas, Ignasi; Giménez, Javier

2010-09-15

Strontium-90 is considered the most important radioactive isotope in the environment and one of the most frequently occurring radionuclides in groundwaters at nuclear facilities. The uranyl peroxide studtite (UO2O2 . 4H2O) has been observed to be formed in spent nuclear fuel leaching experiments and seems to have a relatively high sorption capacity for some radionuclides. In this work, the sorption of strontium onto studtite is studied as a function of time, strontium concentration in solution and pH. The main results obtained are (a) sorption is relatively fast although slower than for cesium; (b) strontium seems to be sorbed via a monolayer coverage of the studtite surface, (c) sorption has a strong dependence on ionic strength, is negligible at acidic pH, and increases at neutral to alkaline pH (almost 100% of the strontium in solution is sorbed above pH 10). These results point to uranium secondary solid phase formation on the spent nuclear fuel as an important mechanism for strontium retention in a high-level nuclear waste repository (HLNW). Copyright 2010 Elsevier B.V. All rights reserved.

Strontium-90 and cesium-137 in sea sediments from July, 1981, to January, 1982

International Nuclear Information System (INIS)

1981-01-01

Sediment was collected in the same area as that of sea water sampling, taking the following criteria into account: the depth of water exceeds 1 m at low tide, no significant sedimental movement is observed in the vicinity of concern, mud, silt and fine sand are preferable. A conventional sediment sampling device was used for collecting a top few cm of surface sediment. Approximately 4 kg of the sample in wet weight was spread on a large porcelain dish and dried in an electric oven to a constant weight. After removal of pebbles, shells and other foreign matters, the sediment sample was dried in a hot air oven, and ground finely with a mortar. The sample was passed through a 20 mesh sieve, and heated in the presence of strontium and cesium carriers with sodium hydroxide. Then it was heated with hydrochloric acid, and the radiochemical separation of strontium-90 and cesium-137 was performed. The mounted precipitates were counted for activity, and after the correction of net counting rates, concentrations of these nuclides were calculated. The maximum values obtained were 22 pCi/kg of Sr-90 and 220 pCi/kg of Sc-137 in Mutsu-bay in August, 1981. (Kako, I.)

Decontamination of cesium, strontium, and cobalt from aqueous solutions by bentonite

Energy Technology Data Exchange (ETDEWEB)

Khan, M.A. [Univ. of the Punjab, Lahore (Pakistan); Khan, S.A. [Government F.C. College, Lahore (Pakistan)

1996-12-31

Sorption studies of cesium, strontium, and cobalt (Cs, Sr, and Co) on bentonite under various experimental conditions, such as contact time, pH, sorbent and sorbate concentration, and temperature, have been performed. The sorption data for all these metals have been interpreted in terms of Freundlich, Langmuir, and Dubinin-Radushkevich equations. Thermodynamics parameters, such as heat of sorption {Delta}H{degrees}, free energy change {Delta}G{degrees}, and entropy change {Delta}S{degrees}, for the sorption of these metals on bentonite have been calculated. The value of {Delta}H{degrees} shows that the sorption of Cs was exothermic, while the sorption of Sr and Co on bentonite were endothermic in nature. The value of {Delta}G{degrees} for their sorption was negative, showing the spontaneity of the process. The maximum loading capacity of Cs, Sr, and Co were 75.5, 22, and 27.5 meq, respectively, for 100 g of bentonite. The mean free energy E of Cs, Sr, and Co sorption on bentonite was 14.5, 9, and 7.7 kJ/mol, respectively. The value of E indicates that ion exchange may be the predominant mode of sorption for these radionuclides. The desorption studies with 0.01 M CaCl{sub 2} and groundwater at low-metal loading on bentonite showed that about 95% of Cs, 85-90% of Sr, and 97% of Co were irreversibly sorbed. Bentonite could be effectively used for the decontamination of wastewater effluent containing low concentrations of radioactive nuclides of Cs, Sr, and Co. 16 refs., 7 figs., 3 tabs.

Trade study for the disposition of cesium and strontium capsules

International Nuclear Information System (INIS)

Claghorn, R.D.

1996-03-01

This trade study analyzes alternatives for the eventual disposal of cesium and strontium capsules currently stored at the Waste Encapsulation and Storage Facility as by-product. However, for purposes of this study, it is assumed that at some time in the future, the capsules will be declared high-level waste and therefore will require disposal at an offsite geologic repository. The study considered numerous alternatives and selected three for detailed analysis: (1) overpack and storage at high-level waste canister storage building, (2) overpack at the high-level waste vitrification facility followed by storage at a high-level waste canister storage building, and (3) blend capsule contents with other high-level waste feed streams and vitrify at the high-level waste vitrification facility

Transport of fallout and reactor radionuclides in the drainage basin of the Hudson River estuary

International Nuclear Information System (INIS)

Simpson, H.J.; Linsalata, P.; Olsen, C.R.

1982-01-01

The transport and fate of Strontium 90, Cesium 137 and Plutonium 239, 240 in the Hudson River Estuary is discussed. Rates of radionuclide deposition and accumulation over time and space are calculated for the Hudson River watershed, estuary, and continental shelf offshore. 37 references, 7 figures, 15 tables

Vertical transfer of radionuclides in soils of different genesis after Chernobyl NPP accident

International Nuclear Information System (INIS)

Bakarykava, Zh.; Shagalova, E.; Zhukova, O.

2003-01-01

In this paper a vertical transfer of radionuclides in soils of different genesis after Chernobyl NPP accident was studied. Analysis of obtained data revealed that the main content of cesium-137 is located in 0-5 cm layer of turf-podsolic, sandy-loam and loamy soil provided the lack of their humidification, and of light un-bogged (automorphous) soil as well. Cesium-137 penetration into light un-bogged soils with that sings of surplus humidification is approximately 10 cm deep. Strontium-90 as global birth so Chernobyl origin migrates more rapidly than cesium-137 because of less strong bond with soil absorbing complex. Cesium-137 migration coefficients amounted (0.03-0.46)·10 -7 cm 2 /s for a slow component, and for the fast one (0.39-0.67)·10 -7 cm 2 /s. Strontium-90 migration coefficients in the experimented sites, amounted (0.07-0.58)·10 -7 cm 2 /s for a slow component, and for the fast one (0.64-1.28)·10 -7 cm 2 /s. (authors)

Absorption of radionuclides from the Fukushima nuclear accident by a novel algal strain.

Directory of Open Access Journals (Sweden)

Hiroki Shimura

Full Text Available Large quantities of radionuclides have leaked from the Fukushima Daiichi Nuclear Power Plant into the surrounding environment. Effective prevention of health hazards resulting from radiation exposure will require the development of efficient and economical methods for decontaminating radioactive wastewater and aquatic ecosystems. Here we describe the accumulation of water-soluble radionuclides released by nuclear reactors by a novel strain of alga. The newly discovered green microalgae, Parachlorella sp. binos (Binos has a thick alginate-containing extracellular matrix and abundant chloroplasts. When this strain was cultured with radioiodine, a light-dependent uptake of radioiodine was observed. In dark conditions, radioiodine uptake was induced by addition of hydrogen superoxide. High-resolution secondary ion mass spectrometry (SIMS showed a localization of accumulated iodine in the cytosol. This alga also exhibited highly efficient incorporation of the radioactive isotopes strontium and cesium in a light-independent manner. SIMS analysis showed that strontium was distributed in the extracellular matrix of Binos. Finally we also showed the ability of this strain to accumulate radioactive nuclides from water and soil samples collected from a heavily contaminated area in Fukushima. Our results demonstrate that Binos could be applied to the decontamination of iodine, strontium and cesium radioisotopes, which are most commonly encountered after nuclear reactor accidents.

Investigations into the transfer of cesium 137 and strontium 90 in selected exposure pathways

International Nuclear Information System (INIS)

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

1991-12-01

This research project investigates the behaviour of radiocesium and strontium 90 in natural conifer forest sites and derives corresponding transfer factors for radioecological calculations. As a point of particular interest the question was investigated in how far the requirements of the different mushroom species and the properties of the forest soil bear on the dynamics and transfer rate of radiocesium and strontium 90. To complement the investigations, autotrophic plants were included. The results of these studies are compared with the behaviour of the same radionuclides on farmland. The differences are discussed. (orig./HP) [de

A new simulation model for calculating the internal exposure of some radionuclides

Directory of Open Access Journals (Sweden)

Mahrous Ayman

2009-01-01

Full Text Available A new model based on a series of mathematical functions for estimating excretion rates following the intake of nine different radionuclides is presented in this work. The radionuclides under investigation are: cobalt, iodine, cesium, strontium, ruthenium, radium, thorium, plutonium, and uranium. The committed effective dose has been calculated by our model so as to obtain the urinary and faecal excretion rates for each radionuclide. The said model is further validated by a comparison with the widely spread Mondal software and a simulation program. The results obtained show a harmony between the Mondal package and the model we have constructed.

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

Energy Technology Data Exchange (ETDEWEB)

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

1975-01-01

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

Metabolism of radionuclides in domestic animals

International Nuclear Information System (INIS)

Wirth, E.; Leising, C.

1986-01-01

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

Health and Safety Laboratory environmental quarterly, March 1, 1977--June 1, 1977. [Air pollution in environs of Cu smelter and fallout radionuclides in food chains

Energy Technology Data Exchange (ETDEWEB)

Hardy, E.P. Jr.

1977-07-01

This report presents current information from the HASL environmental programs, The Technical University of Wroclaw, Poland, and the Radiological and Environmental Research Division of Argonne National Laboratory. The initial section consists of interpretive reports and notes on environmental levels of lead and mercury in the area of a copper smelter, radionuclide uptake by cultivated dusts in crops, and fallout strontium-90 in diet through 1976. Subsequent sections include tabulations of radionuclide concentrations in stratospheric air, radionuclide and stable lead concentrations in surface air, strontium-90 in deposition, milk, diet, and tapwater and cesium-137 in diet and tapwater. A bibliography of recent publications related to environmental studies is also presented.

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

Science.gov (United States)

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

2017-01-05

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

Immobilization of strontium and cesium in intermediate-level liquid wastes by solidification in cements

International Nuclear Information System (INIS)

Rudolph, G.; Koester, R.

1979-01-01

An accelerated leach test at elevated temperature has been developed which gives intercomparable results within one day. It is very useful for product quality control at large throughputs. Using this test, it has been shown that cesium leachabilities from cement products containing a simulated waste typical of fuel reprocessing plants can be reduced by addition of a bentonite. Addition of barium silicate hydrate retards strontium leaching in these cements. Leach rates in tap water and in salt brine are lower than in distilled water and sodium chloride solution

Column studies of strontium and cesium migration in a granular geologic material

International Nuclear Information System (INIS)

Reynolds, W.D.; Gilham, R.W.; Cherry, J.A.

1981-06-01

Infinite-pulse, miscible-displacement experiments were conducted to investigate the applicability of batch Ksub(d) values in the prediction of reactive solute transport during dynamic flow through porous media. Non-reactive tracers (chloride, tritium and oxygen-18), and the reactive tracers (strontium-85 and cesium-137) were passed through a column 5.0 cm long and 6.5 cm in diameter packed with a medium to fine sand. The effluent concentrations of the nonreactive solutes were accurately predicted using the advection-dispersion equation; however, there were large discrepancies between the measured and predicted effluent concentrations for both reactive species. Good agreement was obtained between the measured and computed results by incorporating an empirical isotherm into the advection-dispersion model

Engineered Materials for Cesium and Strontium Storage Final Technical Report

Energy Technology Data Exchange (ETDEWEB)

Sean M. McDeavitt

2010-04-14

Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at

Engineered Materials for Cesium and Strontium Storage. Final Technical Report

International Nuclear Information System (INIS)

McDeavitt, Sean M.

2010-01-01

Closing the nuclear fuel cycle requires reprocessing spent fuel to recover the long-lived components that still have useful energy content while immobilizing the remnant waste fission products in stable forms. At the genesis of this project, next generation spent fuel reprocessing methods were being developed as part of the U.S. Department of Energy's Advanced Fuel Cycle Initiative. One of these processes was focused on solvent extraction schemes to isolate cesium (Cs) and strontium (Sr) from spent nuclear fuel. Isolating these isotopes for short-term decay storage eases the design requirements for long-term repository disposal; a significant amount of the radiation and decay heat in fission product waste comes from Cs-137 and Sr-90. For the purposes of this project, the Fission Product Extraction (FPEX) process is being considered to be the baseline extraction method. The objective of this project was to evaluate the nature and behavior of candidate materials for cesium and strontium immobilization; this will include assessments with minor additions of yttrium, barium, and rubidium in these materials. More specifically, the proposed research achieved the following objectives (as stated in the original proposal): (1) Synthesize simulated storage ceramics for Cs and Sr using an existing labscale steam reformer at Purdue University. The simulated storage materials will include aluminosilicates, zirconates and other stable ceramics with the potential for high Cs and Sr loading. (2) Characterize the immobilization performance, phase structure, thermal properties and stability of the simulated storage ceramics. The ceramic products will be stable oxide powders and will be characterized to quantify their leach resistance, phase structure, and thermophysical properties. The research progressed in two stages. First, a steam reforming process was used to generate candidate Cs/Sr storage materials for characterization. This portion of the research was carried out at Purdue

Adsorption behavior of radionuclide in water containing sea salts

International Nuclear Information System (INIS)

Kani, Yuko; Kamoshida, Mamoru; Asano, Takashi; Tamata, Shin

2012-01-01

Waste water caused by the Fukushima Dai-ichi Nuclear Reactor accident contains high level radioactive material with impurities of sea water origin, such as chloride, sodium and magnesium. These impurities have the potential to inhibit the adsorption reaction of radioactive cesium and strontium to adsorbents. We have studied adsorption behavior of radioactive cesium and strontium to adsorbents to measure distribution coefficients (Kd) in the condition of different sea water concentrations. For cesium adsorption, the dependence of Kd on the sea water concentration was affected by the adsorption mechanism of adsorbent; the adsorbents which adsorbed cesium by intercalation showed less dependence of Kd on the sea water concentration, while those adsorbed cesium by ion exchange had smaller Kd with increasing the sea water concentration. For strontium adsorption, Kd decreased as the sea water concentration increased for both adsorbents which adsorbed strontium by intercalation and by ion exchange. The inhibition of intercalation and ion exchange reaction of strontium by calcium ion, that exists high concentration in sea water (400 ppm) and similar hydrated ionic radius with strontium, will cause the decrease of Kd for strontium in the sea water with higher concentration. (author)

On the role of water and forage in penetration of some radionuclides into the Limnaea organism

International Nuclear Information System (INIS)

Marchyulenene, D.P.; Polikarpov, G.G.; AN Ukrainskoj SSR, Sevastopol. Inst. Biologii Yuzhnykh Morej)

1976-01-01

The objective of this work was to study under laboratory conditions the significance of elodea (Elodea canadensis Rich.) and aqueous medium in accumulation of strontium-90, cesium-137, cerium-144 and ruthenium-106 by limnetic gastropods (Limnaea Stagnalis L.). The study revealed that only 2 and 5% of strontium-90 and cerium-144 respectively were accumulated in molluscs shell from radioactive food, and 4 and 26% - in the body. The authors believed that higher accumulation levels of cerium-144 and ruthenium-106 in mollusca body when the molluscs are fed with radioactive elodea were caused by high accumulation coefficients (AC) of radionuclides in food, i.e. elodea, and their accumulation in the gastrointestinal tracts of molluscs. To appreciates the significance of elodea and water as sources of radionuclide accumulation by mollusca, strontium-90 and cerium-144 AC in molluscs were estimated in relation to water and elodea. The results obtained indicated that AC of these radionuclides in mollusca was much lower in relation to food than to water

Application of crown-ethers to caesium and strontium removal from Marcoule reprocessing concentrate

International Nuclear Information System (INIS)

Dozol, J.F.; Garcia, J.C.i; Sastre, A.M.

1991-01-01

The liquid wastes arising from reprocessing plants are treated by evaporation, the distillate is discharged into environment and the concentrate containing all the active and inactive salts must be stored in geological formation, after embedding, due to the activity of long life radionuclides (actinides, Cs, Sr). The object of the work is to remove actinides and cesium/strontium from high sodium content acidic concentrated in order to sharply decrease the volume of wastes to be stored in geological formation. (author)

Model for prognostication of population irradiation dose at the soil way of long-living radionuclides including in food chains

International Nuclear Information System (INIS)

Prister, B.S.; Vinogradskaya, V.D.

2009-01-01

On the basis of modern pictures of cesium and strontium ion absorption mechanisms a soil taking complex was build the kinetic model of radionuclide migration from soil to plants. Model parameter association with the agricultural chemistry properties of soil, represented by complex estimation of soil properties S e f. The example of model application for prognostication of population internal irradiation dose due to consumption of milk at the soil way of long-living radionuclides including in food chains

Dynamic modeling of the cesium, strontium, and ruthenium transfer to grass and vegetables

International Nuclear Information System (INIS)

Renaud, P.; Real, J.; Maubert, H.; Roussel-Debet, S.

1999-01-01

From 1988 to 1993, the Nuclear Safety and Protection Institute (Institut de Protection et de Surete Nucleaire -- IPSN) conducted experimental programs focused on transfers to vegetation following accidental localized deposits of radioactive aerosols. In relation to vegetable crops (fruit, leaves, and root vegetables) and meadow grass these experiments have enabled a determination of the factors involved in the transfer of cesium, strontium, and ruthenium at successive harvests, or cuttings, in respect of various time lags after contamination. The dynamic modeling given by these results allows an evaluation of changes in the mass activity of vegetables and grass during the months following deposit. It constitutes part of the ASTRAL post-accident radioecology model

Distribution of radionuclides in leaf-stem biomass of lupine and clover under production of protein concentrates

International Nuclear Information System (INIS)

Novikov, Yu.F.; Lobach, G.A.; Buzenko, T.A.; Zaretskaya, T.P.

1993-01-01

The basic regularities of radionuclide distribution between the obtained products have been studied using the fractionation of lupine and clover phytomass as an example. The content of radionuclides in protein concentrates has been shown to be strongly related to the crop species. A scheme and a regime of the fractionation of leaf-stem lupine biomass contaminated with cesium radioisotopes and strontium-90 which ensured the minimizing of their residual content in protein-vitaminic and protein concentrates have been selected with due accout of experimental data

LOW CONTENT OF RADIONUCLIDES IN NATURAL ENVIRONMENT AND PRODUCTION AS A RATIONALE FOR DEVELOPMENT OF RECREATIONAL POTENTIAL OF NORTHERN BUKOVINA

Directory of Open Access Journals (Sweden)

Natalia OMEL’CHENKO

2017-06-01

Full Text Available Investigation on food products contamination by Cesium-137 and Strontium-90, detection of content of natural radionuclides (Radium-226, Thorium-232, Potassium-40 in raw materials and finished products of building industry, monitoring of some radionuclides content in soils of mountainous area of Northern Bukovina was carried out. All the results were analyzed and discussed in view of the life safety position. Data on radionuclides content in surrounding natural environment as well as in building and food industry production confirm Northern Bukovina territory’s attractiveness and safety for recreation areas development.

Report on intercomparison A-14 of the determination of some mineral components and radionuclides in milk powder

International Nuclear Information System (INIS)

Pszonicki, L.; Hanna, A.N.; Suschny, O.

1984-01-01

To enable those laboratories to control their analytical performance the IAEA's Analytical Quality Control Service organizes periodic international comparisons of the determination of radionuclides or of inorganic components in liquid or in powdered milk. The comparison reported here is one in this series. The analytical results, provided by the laboratories which have participated in the intercomparison, allow the certification of concentration values for three mineral components, viz. calcium, potassium, and sodium and for two radionuclides, viz. cesium-137 and strontium-90, in Milk Powder IAEA/A-14

Effect of Temperature on the Removal of Cesium and Strontium Ions from Aqueous Solutions Using Zeolite A

International Nuclear Information System (INIS)

El-Kamash, A.M.; El-Naggar, M.R.; El-Dessouky, M.I.

2008-01-01

Ion exchange experiments between synthetic zeolite A and aqueous solutions of cesium and strontium ions were conducted at constant total ion concentrations of 0.1 N and at different temperatures in the range from 25 to 60 degree C. Thermodynamic equilibrium constants, calculated from the corresponding Kielland's plots, were used for the calculation of . δG degree δH degree and δS degree. The obtained data indicated that zeolite A exhibits higher affinity for Cs + and Sr +2 ions from solution than host Na + ions

Cesium-134 and strontium-85 turnover rates in the centipede Scolopocryptops nigridia McNeill

International Nuclear Information System (INIS)

Yates, L.R.; Crossley, D.A. Jr.

1979-07-01

Radioactive tracers are providing significant information about the ecology of food chains, including such phenomena as accumulation of radioactive fission products, movement of materials along food chains, assimilation and ingestion rates, and nutrient accumulation and turnover. In this study the ingestion, assimilation and turnover to two radioactive tracers were investigated for Scolopocryptops nigridia, an abundant species in forests of the southeastern United States. The two tracers utilized, cesium-134 and strontium-85, are metabolic analogs of potassium and calcium, respectively. The research was performed as part of a larger investigation on the population ecology of the centipede species, emphasizing its relations to nutrient cycling and energy flow in a forest floor system

Radionuclide transport and retardation in tuff

International Nuclear Information System (INIS)

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

1980-01-01

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

Metabolic behaviour of some radionuclides in mammals

International Nuclear Information System (INIS)

Behr, B.

1978-01-01

The author has taken up the difficult task of reviewing the literature on the metabolic behaviour of some radioactive substances in different animal species, especially in domestic animals. Scope and amount of the material available on this subject field very soon induced the author to restrict herself to the more 'classical' radionuclides of iodine, cesium and strontium, as well as to a rather topical group of radioactive substances, the transuranium elements. With a total of about 800 titles cited from the literature, and by means of numerous examples of experiments, skilfully selected and analyzed, various essential differences in the metabolic behaviour of the radionuclides in the different animal species are shown. The extraordinary difficulties arising in comparing the different relevant results and possible methods for a unified approach are presented. (orig./MG) [de

Behavior of radionuclides in sanitary landfills.

Science.gov (United States)

Chang, K C; Chian, E S; Pohland, F G; Cross, W H; Roland, L; Kahn, B

1984-01-01

his study was undertaken to evaluate the possibility of disposing low-level radioactive waste in sanitary landfills with leachate containment to prevent environmental releases. To meet this objective, two simulated landfills, each 200 l. in volume and containing 55 kg of municipal refuse, were operated in the laboratory with simulated rainfall additions for a 9-month period to observe the extent to which radio-cobalt, -cesium, -strontium and tritium were leached into the liquid phase. One of the units was operated with leachate recycle, the other as a single pass control. Liquid samples were analyzed weekly for 3H, 58Co, 85Sr and 134Cs tracers. Weekly analyses were also performed for approximately 30 parameters to define the degree of stabilization of the waste. Major parameters included BOD, COD, pH and concentrations of specific organics, metals and gases. Concentrations of stable cobalt, strontium and cesium were also measured periodically. Soluble radioactivity levels in both systems were reduced by factors of 50 for 58Co, 5 for 85Sr and 7 for 134Cs, taking radioactive decay and dilution into account. Some radionuclide removal from the liquid phase was associated with major chemical changes in the landfills that occurred within 80 days for the control system and within 130 days for the recycle unit. Observed acid, sulfide, and CO2 concentrations suggested mechanisms for removing some of the radionuclides from leachate. Detection of 3H in the off-gas indicated that less than 1% of tritiated waste became airborne. The waste in the leachate recycle unit was more completely stabilized than in the control unit.

Research of decreasing of the cesium radionuclides discharge in the course pouring of the liquid glass from furnace EhP-500/1

International Nuclear Information System (INIS)

Sadovskij, B.F.; Borisov, N.B.; Dzekun, E.G.; Skobtsov, A.S.

1996-01-01

Cesium radionuclides discharge from the furnace liquid-glass discharge unit are studied and estimates of cesium emission from the glass melt by the stream flow-out and filling the waste storage capacity are performed. The ways for decreasing cesium discharges are indicated and new additional aerosol protection system for high-active glass discharge, providing for high protection efficiency is proposed. 10 refs., 1 fig., 1 tab

Clean-up of liquid radiation wastes with elevated mineralization from cesium and cobalt radionuclides by the modified clinoptilolite of the Chankanaj deposit

International Nuclear Information System (INIS)

Plotnikov, V.I.; Tuleushev, A.Zh.; Zhabykbaev, G.T.; Kostsov, S.V.; Medvedeva, Z.V.; Plotnikova, O.M.; Chakrova, E.T.; Idrisova, U.R.; Idrisova, D.Zh.

2003-01-01

On the base of laboratory studies and semi-industrial testing the possibility of liquid radioactive wastes clean-up from cesium and cobalt radionuclides in elevated mineralization conditions with help of modified clinoptilolite is shown. In the work the synthesized thin-layer inorganic sorbent (TIS) with conventional name MC-2 (modified clinoptilolite) was used. The Chankanaj deposit's zeolite in the crushed form was base for the TIS production. The copper ferrocyanides serves as the modifier. This sorbent is selective one in relationship to cesium and cobalt radionuclides

Speciation of radionuclides in natural poly-electrolytes of milk and soils. Author-review of dissertation submitted for fulfillment of the scientific degree 'Philosophiae doctor' (Ph.D.)

International Nuclear Information System (INIS)

Gerhart, P.

1999-01-01

The object of this research was to follow the chemical speciation of added radionuclides Sr-85 or Sr-90, Tc-99, Cs-137, Eu-152, and native cations in cow milk, as well as Pb-212 as a radioactive indicator of lead. The possibility of decontamination of milk from the contaminants was investigated. Speciation of Sr-90 and Cs-137 in the humic acids (HA) was studied as well. Skimmed milk pectin was prepared, which was used to follow the speciation of added radionuclides in the milk. The process of membrane-less dialysis from milk to the pectin phase was rapid and associated with the 3.5 to 4.7 times preconcentration of the non-diffusible in the milk phase in 15 minutes. From the fresh skim bovine milk spiked with respective radionuclides dissolved in the Jenness-Koops buffer (simulating milk serum) and agitated with 4% w/w water solution of apple pectin, about 80% of cesium, 22% of strontium and less than 1.5% of europium was recovered with the pectin. The results indicated that pectin and milk behave according poly-electrolytes. Thus, distribution does not depend on the degree of esterification pectin within the uncertainty of the results. The kinetics of radionuclide distribution was sufficiently rapid even though the viscosity of milk strongly increased during the contact. The recovery of radionuclides into the pectin phase using the milk-pectin membrane-less dialysis allowed the determination of the fractions of diffusible species of radionuclides, depending upon the model of evaluation employed. The sorption of strontium with the simulated milk serum was 31% and that of cesium and europium 58% and 40% respectively. The behaviour of Pb-212 recalls that of trivalent elements. Speciation of fission products Sr-90, Tc-99, Cs-137 and Eu-152 in raw cow milk was studied using the high-performance size exclusion radio-chromatography. The technique of HP-SEC and HP-RSEC by Micro-aqua-gel column was used for identification of radiocesium and radiostrontium interaction with

Selected radionuclides important to low-level radioactive waste management

International Nuclear Information System (INIS)

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237

Selected radionuclides important to low-level radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-11-01

The purpose of this document is to provide information to state representatives and developers of low level radioactive waste (LLW) management facilities about the radiological, chemical, and physical characteristics of selected radionuclides and their behavior in the environment. Extensive surveys of available literature provided information for this report. Certain radionuclides may contribute significantly to the dose estimated during a radiological performance assessment analysis of an LLW disposal facility. Among these are the radionuclides listed in Title 10 of the Code of Federal Regulations Part 61.55, Tables 1 and 2 (including alpha emitting transuranics with half-lives greater than 5 years). This report discusses these radionuclides and other radionuclides that may be significant during a radiological performance assessment analysis of an LLW disposal facility. This report not only includes essential information on each radionuclide, but also incorporates waste and disposal information on the radionuclide, and behavior of the radionuclide in the environment and in the human body. Radionuclides addressed in this document include technetium-99, carbon-14, iodine-129, tritium, cesium-137, strontium-90, nickel-59, plutonium-241, nickel-63, niobium-94, cobalt-60, curium -42, americium-241, uranium-238, and neptunium-237.

Decreasing of transfer of caesium and strontium radionuclides from soil to vegetation - Use of modified aluminosilicates for decreasing of transfer of caesium and strontium radionuclides from soil to vegetation

Energy Technology Data Exchange (ETDEWEB)

Voronina, Anna V.; Blinova, Marina O.; Semenischev, Vladimir S.; Kutergin, Andrey S. [Ural federal university, 620002 Ekaterinburg (Russian Federation)

2014-07-01

The method of addition of sorbents to soils is seemed to be the most efficient for decreasing of transfer of radionuclides from soil to vegetation. Using sorbents should possess affinity to natural systems, high specificity and selectivity and also irreversibility of sorption of radionuclides for effective retention of radionuclides as well as to prevent their migration into vegetation and further movement through food chains. Specificity, selectivity and reversibility of sorption of caesium and strontium radionuclides by natural aluminosilicates (glauconite, clinoptilolite) and modified ferrocyanide sorbents based on them was studied in this work. It was shown that the natural glauconite sorbs caesium from tap water with distribution coefficient K{sub d} = 10{sup (3.5±0.1)} mL/g, static exchange capacity of Cs is 11.0 mg/g; it shows lower specificity to strontium: K{sub d} = 10(2.5±0.1) mL/g, static exchange capacity = 9 mg/g. For clinoptilolite these parameters are for caesium K{sub d} = 10(4.4±0.5) mL/g, static exchange capacity 210 mg/g; for strontium K{sub d} = 10(3.5±0.1) mL/g, capacity = 12 mg/g. Ferrocyanide sorbents concentrate caesium radionuclides more effectively: distribution coefficient of Cs from tap water by mixed nickel-potassium ferrocyanide based on glauconite is 10(5.9±1.6) mL/g, static exchange capacity of Cs is (63.0±2.0) mg/g; for mixed nickel-potassium ferrocyanide based on clinoptilolite these characteristics are respectively 10(7.4±1.3) mL/g, 500 mg/g. In case of modified sorbents specificity to strontium remains the same as for natural aluminosilicates. Reversibility of sorption of caesium by natural glauconite and ferrocyanide sorbent was determined as caesium leaching degree from saturated samples. High caesium leaching rates and degrees are typical for natural glauconite irrespective of leachant salinity: total degree of leaching after 35 days of leaching was: mineral water = 63.4%, tap water = 41.6% and rain water = 28.8%. For

Selective removal of cesium and strontium using porous frameworks from high level nuclear waste.

Science.gov (United States)

Aguila, Briana; Banerjee, Debasis; Nie, Zimin; Shin, Yongsoon; Ma, Shengqian; Thallapally, Praveen K

2016-05-01

Efficient and cost-effective removal of radioactive (137)Cs and (90)Sr found in spent fuel is an important step for safe, long-term storage of nuclear waste. Solid-state materials such as resins and titanosilicate zeolites have been assessed for the removal of Cs and Sr from aqueous solutions, but there is room for improvement in terms of capacity and selectivity. Herein, we report the Cs(+) and Sr(2+) exchange potential of an ultra stable MOF, namely, MIL-101-SO3H, as a function of different contact times, concentrations, pH levels, and in the presence of competing ions. Our preliminary results suggest that MOFs with suitable ion exchange groups can be promising alternate materials for cesium and strontium removal.

A preliminary investigation of radiation level and some radionuclides in imported food and food products

International Nuclear Information System (INIS)

Sinakhom, F.; Mongkolphantha, S.

1980-04-01

A preliminary study of gross beta activity and content of some long-lived radionuclides associated with fission products in various types of imported food and food-products was carried out. Food samples were purchased monthly during 1976-1977 from general well-known supermarkets and local grocery stores up to a total of 89 samples. The gamma spectrum of long-lived radionuclides was searched using a 128 channel analyzer coupled with 3'' x 3'' NaI (T1) crystal detector. Two radionuclides were frequently found to be present in these food samples, viz. potassium-40 and cesium-137 and their concentrations were subsequently determined. The limits of detection under the conditions used for potassium-40 and cesium-137 were 0.04 and 0.03 pCi/g-wet weight, respectively. Samples were dry-ashed and counted for gross beta activity utilizing a low background anti-coincidence G.M. counter. The content of strontium-90 was also investigated concurrently by solvent extraction technique employing tri-n-butyl phosphate as an extractant. Results of the study are tabulated. (author)

Characteristics of radionuclide accumulation in benthic organisms and fish of the Barents and Kara Seas

International Nuclear Information System (INIS)

Matishov, G.G.; Matishov, D.G.; Rissanen, C.

1995-01-01

Artificial radionuclides play a specific role in the hydrochemical, geochemical, and hydrobiological processes that are currently occurring in the western Arctic. The existing data on radioactive contamination of different plant and animal species inhabiting the sea shelf are fragmentary. Hence, it was difficult to follow the transformation of radionuclides during their transmission along food chains, from phyto- and zoo-plankton to benthos, fish, birds, and marine mammals. In 1990-1994, the Murmansk Institute of Marine Biology organized expeditions to collect samples of residues on the sea floor and also of benthos, benthic fish, macrophytes, and other organisms inhabiting the shelf of the Barents and Kara Seas. These samples were tested for cesium-137, cesium-134, strontium-90, plutonium-239, plutonium-240, americium-241, and cobalt-60 in Rovaniemi (Finland) by the regional radiation administration of the Finnish Centre for Radiation and Nuclear Safety. Over 1000 tests were made. Their results provided new data on the content and distribution of these radionuclides among different components of marine ecosystems. 7 refs

Estimating the transfer of radionuclides from foodstuff into animals (meat)

International Nuclear Information System (INIS)

Franke, B.; Hopfner, U.

1978-10-01

Eating contaminated animal food represents a considerable contribution to human irradiation loading from radioactive emission. When estimating the irradiation loading, a precondition is a knowledge of the radio-nuclide transfer from the feedstuff into the meat of the domestic animal. The radio-ecology importance of this exposure path requires a precise examination of the origin of the values given by SSK with the data in the international literature. The transfer of radio-cesium, radio-strontium, radio-iodine and plutonium from feedstuff into meat/milk are especially considered. (DG) [de

Decontamination of radionuclides in food

Energy Technology Data Exchange (ETDEWEB)

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

1994-03-01

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

Decontamination of radionuclides in food

International Nuclear Information System (INIS)

Ohmomo, Yoichiro

1994-01-01

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

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

International Nuclear Information System (INIS)

El- Masry, E.H.

2012-01-01

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Retention of Radionuclides in Halite and Anhydrite

DEFF Research Database (Denmark)

Carlsen, Lars; Platz, O.

1986-01-01

The interaction between a series of radionuclides, comprising **1**3**4Cs** plus , **8**5Sr**2** plus , **6**0Co**2** plus , **1**5**4Eu**3** plus , **2**4**1Am**3** plus , and **9**9Tc (as TcO//4** minus ) and halite (NaCl) and anhydrite (CaSO//4), respectively, has been investigated. It appears...... for europium and americium, respectively. Impuritites in the halite, such as hematite or anhydrite strongly increase the sorption efficiency. In these cases also cobalt, and to a minor extent cesium and strontium, was found to be sorbed. Anhydrite was found to sorb all metal cations studied. The sorption...

Guidance on offsite emergency radiation measurement systems. Phase 2: The milk pathway

International Nuclear Information System (INIS)

1984-04-01

This document provides guidance to State and local governments and to Federal agencies on offsite emergency measurement of radionuclides after an accident involving a light-water nuclear power plant; in particular, this document provides guidance on determining the dose commitment from the milk pathway. Protective action levels proposed by the Food and Drug Administration (FDA) for milk are used as the basis for monitoring requirements. Measurement of radionuclides in milk should be made at the earliest practical point in the production chain: dairy farms, receiving and transfer stations, processing plants or marketing facilities. Early monitoring will provide data to keep significantly contaminated milk out of distribution and will provide the basis for the most timely emergency response action. Radioiodine plus four other radionuclides, cesium-134, cesium-137, strontium-89, and strontium-90, contribute significantly to dose via the milk pathway; of the most severe potential accident, the short-term dose via the milk pathway from radioiodine is significantly greater than that of cesium or strontium. There is no emergency field monitoring instrumentation available for accurately monitoring cesium and strontium, particularly in the presence of radioiodine. Radioiodine can be a potential contamination problem in liquid milk, whereas radiocesium and radiostrontium can be a contamination problem in processed milk products. Monitoring for the long half-life nuclides such as cesium and strontium requires sophisticated equipment or chemistry procedures which are only available in a laboratory. 2 references, 21 figures, 21 tables

Elimination of man-made radionuclides from natural waters by applying a standard coagulation-flocculation process

International Nuclear Information System (INIS)

Baeza, A.; Miro, C.; Salas, A.; Fernandez, M.; Herranz, M.; Legarda, F.

2004-01-01

Effectiveness of potable water treatment processes that consist of the stages of coagulation-flocculation-decantation, using iron-based coagulants, in eliminating gamma-emitting man-made radioisotopes of cesium, strontium, and americium from two natural waters with different degrees of mineralization was studied. The resulting decontamination was found to depend on the chemical behavior of each of the radionuclides considered, on the pH at which the process of coagulation is carried out, and on the concentration of the other stable cations present. (author)

A dosing method in the same time of the radiocesium and the radiostrontium in natural waters; Dosage simultane du cesium 137 et des strontium 89 et 90 dans les eaux naturelles

Energy Technology Data Exchange (ETDEWEB)

Scheidhauer, J; Messainguiral, L [Commissariat a l' Energie Atomique, Marcoule (France).Centre d' Etudes Nucleaires

1960-07-01

Prior a concentration and an unselective elution are effected by the way of an exchange resin. The cesium is absorbed on ammonium molybdophosphate precipitated with hydrofluoric acid after radium elimination. The strontium is stripped in concentrated nitric acid, precipitated in the form of strontium carbonate and then counted near the radioactive balance. At last the yttrium is separated by the thenoyltrifluoroacetone and counted on a counting device. From the outset of this paper, an analysis of the method is explained. (author) [French] On opere d'abord une concentration sur resine et une elution non selective. Le cesium est absorbe sur un precipite de phosphomolybdate d'ammonium en presence d'acide fluorhydrique, apres separation du radium. Le strontium est traite a l'acide nitrique concentre, precipite sous forme de carbonate et compte au voisinage de l'equilibre radioactif ({sup 90}Sr {sup 9O}y ). L'yttrium 90 est ensuite separe a la thenoyltrifluoracetone et compte. Une etude de la methode est presentee au debut de ce memoire. (auteur)

New composite fibres for natural and waste waters decontamination from cesium radionuclides

Directory of Open Access Journals (Sweden)

Yu. V. Bondar

2017-08-01

Full Text Available New composite adsorbent based on modified polyacrylonitrile fibers is synthesized by in situ deposition of potassium-nickel ferrocyanide layer on the fibers’ surface. It is shown that the ferrocyanide phase forms a compact homogeneous layer on the fibers’ surface consisted of rounded nanoaggregates (∼ 40 - 50 nm. Composite fibers are chemically stable in both acidic and alkaline solutions. Sorption experiments have demonstrated that synthesized fibers are high-selective adsorbents and can be used for the purification of natural waters and high-salt solutions from cesium radionuclides.

Foliar uptake of cesium, iodine and strontium and their transfer to the edible parts of beans, potatoes and radishes

International Nuclear Information System (INIS)

Kopp, P.; Oestling, O.; Burkart, W.

1988-01-01

In the case of a nuclear fall-out the uptake of radionuclides via the leaves and the transfer to the edible parts is an important pathway in food contamination. After the Chernobyl accident cesium-activity was measured in fruits and nuts in Wuerenlingen. Considering the short time between fall-out and harvest, the activity which was found in some of these could hardly be explained by root-uptake in the amounts that they were present. Neither could the high content be explained by direct contamination since the fall-out occurred before development of the edible parts. Therefore it was concluded that the cesium has been taken up through the leaves

Special foodstuffs rich in anticarcinogens and antioxidants as means of protecting the population at territories polluted by radionuclides

International Nuclear Information System (INIS)

Knizhnikov, V.A.; Shandala, N.K.; Komleva, V.A.; Rudintseva, T.A.

1996-01-01

The purpose of this work was to assess the effect of diets including foodstuffs rich in special additives on the metabolism of ecologically important radionuclides strontium-90 and cesium-137 and to assess the resistance of exposed and intact animals from changes in body weight and hemopoietic status. Three types of special meat products containing additives made of sea alga laminaria. Normalization of the ration for mineral and protein composition owing to the above foodstuffs has a favorable impact on the time course of body weight and peripheral hemopoietic system. Radiometry of bone tissue showed that accumulation of strontium 90 was reduced by half in animals fed nutritive additives of meat preserves with routine diet. Refs. 6, tabs. 5

Population dose commitment associated with various radionuclides in foods

International Nuclear Information System (INIS)

Simpson, Robert E.; Baratta, Edmond J.; Tanner, James T.

1978-01-01

The radionuclides in foods monitoring program initiated by the Food and Drug Administration in 1973 was expanded in 1975 to include the analysis for hydrogen-3 in selected foods originating from the vicinity of nuclear power stations. Also, in 1975 the analysis for radium-226 was initiated in food samples from areas adjacent to the phosphate mines in Florida. In October 1976 a special survey of milk was performed to determine the levels of fission product contamination from the fallout produced by the detonation of a nuclear device by the People's Republic of China. Results from the analysis of strontium-90 and cesium-137 in the general foods survey for the years 1973 through 1977 indicated intake levels well within range I of the Radiation Protection Guides (RPG) [FRC 1: Range I at 0.1xRPG dose, periodic surveillance; Range II at the RPG dose, quantitative surveillance and routine control; Range III 10xRPG dose, evaluation and additional controls]. The levels of hydrogen-3 in foods from nuclear power station areas were slightly above the tritium background. The radium-226 levels in foods from Florida phosphate mining areas were about double that of the controls. In both cases, however, the radium-226 intake from the total diet was in range II of the RPGs. The iodine-131 levels in the special milk survey in HEW regions I and III were in range III of the RPGs. The levels of barium-lanthanum-140, cesium-137 and strontium-89-90 were all within range I. The clearance half-time from milk for these radionuclides was about 5, 7 and 9 days respectively. (author)

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)

Distribution and migration of cesium and strontium radionuclides in Estonian scots pine stands

International Nuclear Information System (INIS)

Martin, L.; Tekko, S.; Aaspollu, J.; Martin, J.; Vilde, R.; Nifontova, M.

1994-01-01

Radioactive pollution from the Chernobyl NPS reactor accident in 1986 has wide scale impact through radionuclides fallout over large areas. We used mushrooms, macrolichenes, mosses and pine needles, forest litter and soil for the investigaton of 137 Cs and 90 Sr accumulation and migration in pine ecosystems. Systematic collections were made on 63 field sites, total amount of samples analyzed is 350. Highest concentrations of radiocaesium were determined in mushrooms (41.8 kBq/kg) in north-east of Estonia, in macrolichens at the Lahemaa National Park (6.2 kBq/kg). At the Rumpo Botanical Reserve the level of radiocaesium exceeded background concentration (1985) 1.3-1.8 times and at the Koljaku 4.0-4.4 times. During five years of observations (1986-1991) decrease of radionuclides pollution revealed 15 times the Rumpo and Koljaku. Radiostrontium concentrations in different ecosystem compartments all over the territory did not exeed harmful levels. (author). 2 tabs

Removal of dissolved heavy metals and radionuclides by microbial spores

International Nuclear Information System (INIS)

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

1997-01-01

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

Effects of experimental parameters on the sorption of cesium, strontium, and uranium from saline groundwaters onto shales: Progress report

International Nuclear Information System (INIS)

Meyer, R.E.; Arnold, W.D.; Case, F.I.; O'Kelley, G.D.

1988-11-01

This report concerns an extension of the first series of experiments on the sorption properties of shales and their clay mineral components reported earlier. Studies on the sorption of cesium and strontium were carried out on samples of Chattanooga (Upper Dowelltown), Pierre, Green River Formation, Nolichucky, and Pumpkin Valley Shales that had been heated to 120/degree/C in a 0.1-mol/L NaCl solution for periods up to several months and on samples of the same shales which had been heated to 250/degree/C in air for six months, to simulate limiting scenarios in a HLW repository. To investigate the kinetics of the sorption process in shale/groundwater systems, strontium sorption experiments were done on unheated Pierre, Green River Formation, Nolichucky, and Pumpkin Valley Shales in a diluted, saline groundwater and in 0.03-mol/L NaHCO 3 , for periods of 0.25 to 28 days. Cesium sorption kinetics tests were performed on the same shales in a concentrated brine for the same time periods. The effect of the water/rock (W/R) ratio on sorption for the same combinations of unheated shales, nuclides, and groundwaters used in the kinetics experiments was investigated for a range of W/R ratios of 3 to 20 mL/g. Because of the complexity of the shale/groundwater interaction, a series of tests was conducted on the effects of contact time and W/R ratio on the pH of a 0.03-mol/L NaHCO 3 simulated groundwater in contact with shales. 8 refs., 12 figs., 15 tabs

Strontium-82/rubidium-82 generator

International Nuclear Information System (INIS)

Gennaro, G.P.; Haney, P.S.

1986-01-01

Hydroxylapatite, a compound having the formula: M 10 (PO 4 ) 6 (OH) 2 wherein M is calcium, strontium, barium, lead, iron, sodium, potassium, zinc, cadmium, magnesium, aluminium or a rare earth metal, is provided as a support medium for strontium-82 in a strontium-82/rubidium-82 parent-daughter radionuclide generator

Ecological processes in the cycling of radionuclides within arctic ecosystems

International Nuclear Information System (INIS)

Hanson, W.C.

1986-01-01

Worldwide fallout radionuclides in arctic ecosystems was investigated ecologically by circumpolar nations during 1959-80. Several of the radionuclides are isotopes of elements which currently contribute to arctic haze; they thus serve as effective tracers of biogeochemical processes. Investigations demonstrated the effective concentration of several radionuclides, particularly strontium-90 (an alkaline earth metal) and cesium-137 (a light alkali metal) which are chemical analogs of calcium and potassium, two very important stable elements in biotic systems. Transfer of 137 Cs through the lichen-cariboureindeer-man food chain characteristic of circumpolar nations, resulted in body burdens in Inuit that were 20 to 200 times greater than those in human populations of temperature latitudes. Radiation exposures from 90 Sr, 137 Cs and other natural and worldwide fallout radionuclides, were two to three times greater than for most other world populations. These results demonstrate the concentration capabilities of arctic ecosystems for several groups of chemical elements that have counterparts in arctic haze. These elements, therefore, provide the basis for considering the ecological implications of current situations

Determination of cesium and selenium in cultivated mushrooms using radionuclide X-ray fluorescence technique

International Nuclear Information System (INIS)

Racz, L.; Bumbalova, A.; Harangozo, M.; Toelgyessy, J.; Tomecek, O.

2000-01-01

Cesium and selenium intake of cultivated mushrooms (Agaricus bisporus), with these elements previously added to culture medium, has been examined from the viewpoint of health- and environmental protection. The process of measuring has been carried out by the radionuclide X-ray fluorescence technique. Treatments of the elementary substance with Se salt appears to influence the Se content of the mushrooms to a significant extent. Cs intake is of considerable importance, as this element is accumulated by mushrooms. (author)

Comparison of radionuclide levels in soil, sagebrush, plant litter, cryptogams, and small mammals

International Nuclear Information System (INIS)

Landeen, D.S.

1994-09-01

Soil, sagebrush, plant litter, cryptogam, and small mammal samples were collected and analyzed for cesium-137, strontium-90, plutonium-238, plutonium 239/240, technetium-99, and iodine-129 from 1981 to 1986 at the US Department of Energy Hanford Site in southeastern Washington State as part of site characterization and environmental monitoring activities. Samples were collected on the 200 Areas Plateau, downwind from ongoing waste management activities. Plant litter, cryptogams, and small mammals are media that are not routinely utilized in monitoring or characterization efforts for determination of radionuclide concentrations. Studies at Hanford, other US Department of Energy sites, and in eastern Europe have indicated that plant litter and cryptogams may serve as effective ''natural'' monitors of air quality. Plant litter in this study consists of fallen leaves from sagebrush and ''cryptogams'' describes that portion of the soil crust composed of mosses, lichens, algae, and fungi. Comparisons of cesium-137 and strontium-90 concentrations in the soil, sagebrush, litter, and cryptogams revealed significantly higher (p<0.05) levels in plant litter and cryptogams. Technetium-99 values were the highest in sagebrush and litter. Plutonium-238 and 239/40 and iodine-129 concentrations never exceeded 0.8 pCi/gm in all media. No evidence of any significant amounts of any radionuclides being incorporated into the small mammal community was discovered. The data indicate that plant litter and cryptogams may be better, indicators of environmental quality than soil or vegetation samples. Augmenting a monitoring program with samples of litter and cryptogams may provide a more accurate representation of radionuclide environmental uptake and/or contamination levels in surrounding ecosystems. The results of this study may be applied directly to other radioecological monitoring conducted at other nuclear sites and to the monitoring of other pollutants

Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet

International Nuclear Information System (INIS)

Abotsi, G.M.K.; Bostick, D.T.; Beck, D.E.

1996-05-01

The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere

Sorption of radionuclides from spent fuel in crystalline rocks

International Nuclear Information System (INIS)

Nikula, A.

1982-10-01

The safe disposal of spent nuclear fuel or reprocessed waste is an essential element in the expansion of the nuclear power industry. Stable rock formations e.g. granite are considered to be potential sites for disposal. A major factor in evaluating the degree of safety of the disposal is the sorption of radionuclides in rock, which affects their retardation. The report considers the chemical forms of the hazardous radionuclides of spent nuclear fuel in groundwater and the effects of the water's properties on them. In the groundwater near the Olkiluoto power plant site cesium, strontium and radium are in cationic form, iodine as I - . Technetium would occur as TcO +2 , but the pertechnetate form is also possible. Uranium most probably would be as U(VI) plutonium and neptunium as Np(IV) or Np(V). The valences for thorium, americium and curium are not changed in this groundwater and would be +4, +3 and +3, respectively. The actinides in groundwater are all in hydrated or complex form. An increase on the ionic stregth of the groundwater in most instances causes a decrease in the sorption of nuclides since the ion exchange capacity of the rock is limited. Anionic ligands also decrease sorption of cations by complex formation. In some case, on the other hand, high salt concentrations may cause formation of radiocolloids of lanthanides and neptunium and thus increase sorption. In all cases the degree of sorption described by the distribution ratio Ksub(d) was influenced by the pH of the groundwater. Sorption of cesium and strontium increased with growing pH. The sorption behaviour of actinides was in positive correlation with formation of hydroxide complexes at different pH values. The Ksub(d) values of Cs, Sr, Co, Ni and Am for Olkiluoto granites were found to agree with Swedish values, also determined at ambient atmospheric conditions

The contamination of the oceans by anthropogenic radionuclides

International Nuclear Information System (INIS)

Figueira, Rubens C.L.; Cunha, Ieda I.L.

1998-01-01

Several hundreds of artificial of artificial radionuclides are produced as the result of human activities, such as the applications of nuclear reactors and particle accelerators, testing of nuclear weapons and nuclear accidents. Many of these radionuclides are short-lived and decay quickly after their production, but some of them are longer-lived and are released into the environment. From the radiological point of view the most important radionuclides are cesium-137, strontium-90 and plutonium-239, due to their chemical and nuclear characteristics. The two first radioisotopes present long half life (30 and 28 years), high fission yields and chemical behaviour similar to potassium and calcium, respectively. No stable element exists for plutonium-239, that presents high radiotoxity, longh half-life (24000 years) and some marine organisms accumulate plutonium at high levels. The radionuclides introduced into marine environment undergo various physical, chemical and biological processes taking place in the sea. These processes may be due to physical, dispersion or complicated chemical and biological interactions of the radionuclides with inorganic and organic suspend matter, variety of living organism, bottom sediments, etc. The behaviour of radionuclides in the sea depends primarily on their chemical properties, but it may also be influenced by properties of interacting matrices and other environmental factors. The major route of radiation exposure of man to artificial radionuclides occuring in the marine environment is through ingestion of radiologically contamined marine organisms. This paper summarizes the main sources of contamination in the marine environment and presents an overview covering the oceanic distribution of anthropogenic radionuclides in the FAO regions. A great number of measurements of artificial radioclides have been carried out on various marine environmental samples in different oceans over the world, being cesium-137 the most widely measured

Bioaccumulation factors for radionuclides in freshwater biota

International Nuclear Information System (INIS)

Vanderploeg, H.A.; Parzyck, D.C.; Wilcox, W.H.; Kercher, J.R.; Kaye, S.V.

1975-11-01

This report analyzes over 200 carefully selected papers to provide concise data sets and methodology for estimation of bioaccumulation factors for tritium and isotopes of strontium, cesium, iodine, manganese, and cobalt in major biotic components of freshwater environments. Bioaccumulation factors of different tissues are distinguished where significant differences occur. Since conditions in the laboratory are often unnatural in terms of chemical and ecological relationships, this review was restricted as far as possible to bioaccumulation factors determined for natural systems. Because bioaccumulation factors were not available for some shorter-lived radionuclides, a methodology for converting bioaccumulation factors of stable isotopes to those of shorter-lived radionuclides was derived and utilized. The bioaccumulation factor for a radionuclide in a given organism or tissue may exhibit wide variations among bodies of water that are related to differences in ambient concentrations of stable-element and carrier-element analogues. To account for these variations, simple models are presented that relate bioaccumulation factors to stable-element and carrier-element concentrations in water. The effects of physicochemical form and other factors in causing deviations from these models are discussed. Bioaccumulation factor data are examined in the context of these models, and bioaccumulation factor relations for the selected radionuclides are presented

Comparison of organic and inorganic ion exchangers for removal of cesium and strontium from simulated and actual Hanford 241-AW-101 DSSF tank waste

International Nuclear Information System (INIS)

Brown, G.N.; Bray, L.A.; Carlson, C.D.

1996-04-01

A number of organic and inorganic exchangers are being developed and evaluated for cesium removal from Hanford tank wastes. The exchangers of interest that are investigated in this work include powdered (IONSIV reg-sign IE-910; referred to as IE-910) and engineered (IONSIV reg-sign IE-911; referred to as IE-911) forms of the crystalline silico-titanate (CST) inorganic sorbent developed by Sandia National Laboratories (SNL)/Texas A and M and prepared by UOP; a phenol-formaldehyde (CS-100) resin developed by Rohm and Haas; a resorcinol-formaldehyde (R-F) polymer developed at the Westinghouse Savannah River Company (WSRC) and produced by Boulder Scientific; an inorganic zeolite exchanger produced by UOP (IONSIV reg-sign TIE-96; referred to as TIE-96); an inorganic sodium titanate produced by Allied Signal/Texas A and M (NaTi); and a macrocyclic organic resin developed and produced by IBC Advanced Technologies (SuperLig reg-sign 644; referred to as SL-644). Several of these materials are still under development and may not be in the optimal form. The work described in this report involves the direct comparison of the ion exchange materials for the pretreatment of actual and simulated Hanford tank waste. Data on the performance of all of the exchangers with simulated and actual double shell slurry feed (DSSF) is included. The DSSF waste is a mixture of the supernate from tanks 101-AW (70%), 106-AP (20%) and 102-AP (10%). The comparative parameters include radionuclide removal efficiency under a variety of conditions and material properties (e.g., bed density and percent removable water). Cesium and strontium distribution (K d ), lambda (λ = K d x ρ b ), and decontamination factors (DF) are compared as a function of exchanger contact duration, solution composition (Na and Cs concentration), exchanger/waste phase ratio, and multiple sequential contacts

Analytical procedures for the determination of strontium radionuclides in environmental materials

International Nuclear Information System (INIS)

Harvey, B.R.; Ibbett, R.D.; Lovett, M.B.; Williams, K.J.

1989-01-01

As part of its statutory role in the authorisation, monitoring and research relating to radioactive wastes discharged into the aquatic environment, the Aquatic Environment Protection Division of the Directorate of Fisheries Research (DFR), Lowestoft routinely carries out analyses for a substantial number of radionuclides in a wide range of environmental materials. The Ministry of a Agriculture, Fisheries and Food has for many years required information about the concentrations of strontium radionuclides in waters, sediments and biological materials. There are not absolute standard methods for such radiochemical analysis; indeed none are required because methodology is continually developing. A very considerable amount of expertise has been developed in the analysis of radiostrontium at the Laboratory since the late 1950s, when detailed analysis first commenced, and the procedures described in this report have been developed and tested over a long period of time with a view to achieving the highest analytical quality. Full details of the practical, analytical and computational procedures, as currently used, are given in the Appendix. (author)

Exchange of certain radionuclides between environment and freshwater algae

International Nuclear Information System (INIS)

Marchyulenene, E. D.P.

1978-01-01

Data on the dynamics and levels of accumulation of strontium, cesium, cerium and ruthenium radionuclides by Charophyta and Cladophora fresh-water algae are presented. An attempt has been made to investigate some processes that accompany the accumulation of radionuclides by plants. Under experimental conditions, the intensity and levels of radionuclide accumulation can be presented in the following order: 144 Ce> 106 Ru> 90 Sr> 137 Cs. The dynamics of radionuclide accumulation varied greatly with the radionuclide and the algae species studied. The 144 Ce accumulation coefficients (AC) in the course of experiment (from 3 hours to 16 days) increased 8-, 9-, 23.4-, 27-, 14.3- and 20.4-fold for Cladophora glomerata, Nitella syncarpa, Nitellopsis obtusa, Chara vulgaris, Ch. rudis, and Ch. aspera, respectively. In the case of 106 Ru, AC for C.glomerata, N. syncarapa, Ch. vulgaris and Ch. rudis increased 34-, 18-,24- and 23-fold, respectively. In all algae species studied the equilibrium of radionuclide accumulation was attained after 2-4 days of experiment. Levels of accumulated 90 Sr and 137 Cs in most species depended on the season while that of 144 Cs and 106 Ru remained constant throughout the vegetation period. The levels of radionuclide elimination, like the accumulation levels, are shown to depend on both isotopes and algae species

Simulating the Transfer of Strontium-90 from Soil to Leafy Vegetables by Using Strontium-88

OpenAIRE

Kuke, Ding; Shujuan, Liu; Yingxue, He; Dong, Yan; Fengshou, Zhang; Shuifeng, Wang; Jinghua, Guo; Wei, Zhang; Xin, Wang; Xiaoyan, Jiang

2016-01-01

The transfer, from soil to Chinese cabbage and spinach, of radioactive strontium-90 released as a result of accidents in nuclear power stations was studied using a stable isotope of strontium, namely nuclide strontium-88 (88Sr). The study led to an experimental model for assessing the hazard of radionuclide strontium-90 (90Sr) entering the food chain and for predicting the risk to food safety. Chinese cabbage and spinach were grown in pots in a greenhouse and irrigated with deionized water co...

Laboratory studies of radionuclide transport in fractured Climax granite

International Nuclear Information System (INIS)

Failor, R.; Isherwood, D.; Raber, E.; Vandergraaf, T.

1982-06-01

This report documents our laboratory studies of radionuclide transport in fractured granite cores. To simulate natural conditions, our laboratory studies used naturally fractured cores and natural ground water from the Climax Granite Stock at the Nevada Test Site. For comparison, additional tests used artificially fractured granite cores or distilled water. Relative to the flow of tritiated water, 85 Sr and /sup 95m/Tc showed little or no retardation, whereas 137 Cs was retarded. After the transport runs the cores retained varying amounts of the injected radionuclides along the fracture. Autoradiography revealed some correlation between sorption and the fracture fill material. Strontium and cesium retention increased when the change was made from natural ground water to distilled water. Artificial fractures retained less 137 Cs than most natural fractures. Estimated fracture apertures from 18 to 60 μm and hydraulic conductivities from 1.7 to 26 x 10 -3 m/s were calculated from the core measurements

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

Importance of biota in radionuclide transport at the SL-1 radioactive waste disposal area

International Nuclear Information System (INIS)

Arthur, W.J.; Grant, J.C.; Markham, O.D.

1983-01-01

During summer 1981 and 1982, radioecological research was conducted at the Stationary Low Power Reactor-1 radioactive waste disposal area to: (1) identify vegetation, wildlife, and invertebrate species occurring at or using the area; (2) determine radionuclide concentrations in these various ecosystem components; and (3) to evaluate their respective roles in radionuclide uptake and transport through the surrounding environment. Cesium-137 concentrations detected in surface soils, small mammal excavated soils and small mammal tissues collected at the waste disposal site were significantly (P less than or equal to 0.05) greater than control area samples. Strontium-90 and 235 U analyses of SL-1 and control area samples and projections of total mass of ecosystem components in SL-1 area will be completed in summer of 1983 at which time estimates will be made on the total quantity of fission and activation radionuclides occurring in ecological media at the SL-1 waste disposal area

Radionuclide transfer from soil to plants

International Nuclear Information System (INIS)

Teufel, D.; Steinhilber-Schwab, B.; Hoepfner, U.; Ratka, R.; Sand, H. van de; Franke, B.

1979-01-01

The planned nuclear reprocessing plant (NEZ) Gorleben will fundamentally differ from actually operating nuclear power plants with regard to its radioactive emissions because relatively long-life isotopes will play a greater role in the emissions. The longevity of the radionuclides emitted in the planned NEZ implies that there will be an accumulation of radionuclides in the surroundings of the plant and long-term effects of the plant on the environment will get higher significance. As radionuclides mainly reach milk and meat via the food of farm animals the transfer of cesium and strontium from the ground into plants was amply investigated. The results show that the correlation calculations are suitable to describe the effect of different parameters on the transfer factor. They are not suited for a forecast of the transfer conditions on a certain location for the reasons explained before. Location-specific measurements seem to be indispensable for these purposes. Besides the greenhouse tests open air measurements of fall-out nuclides with and without elimination of external contamination seem to represent a realistic possibility for the determination of transfer factors. Great attention has to be paid in this kind of tests to the growth conditions (especially fertilization) which have to be accurately registered. (orig./MG) [de

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

International Nuclear Information System (INIS)

Freire, Carolina Braccini

2007-01-01

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

Leachability and thermal properties of ceramic solid forms immobilizing cesium and/or strontium

International Nuclear Information System (INIS)

Mimura, H.; Hirabayashi, T.; Ozawa, M.

2003-01-01

Solid forms immobilizing nuclides were prepared from Cs-mordenite and Sr-A zeolite by calcination at 1.200 deg C for 1 h. Cesium and strontium were fixed in the crystal phases of pollucite (CsAlSi 2 O 6 ) and Sr-feldspar (SrAl 2 Si 2 O 8 ), respectively. The leachability of Cs andSr was rather high in 0.1 M HNO 3 leachant, while the leached percentage was lowered in 0.1 M NaOH, 0.1 M NaCl and deionized water. The recrystallized phases formed on the surface after leaching in 0.1 M NaOH resulted in the lowering of the leachability of Cs and Sr. The thermal conductivities (κ) of solid forms of Cs-MOR, Sr-A, (Cs,Sr)-A and Al-matrix (calcined Cs-mordenite dispersed in Al metal matrix) were determined to be 0.83-1.00, 0.55-0.64, 0.83-1.01 and 47 W/(m·K), respectively. The central temperature of solid forms with the same diameter was in the order of Sr-A > Cs-MOR > Al-matrix. (author)

Radionuclide sorption behavior in particulate matter in near coastal marine environments

International Nuclear Information System (INIS)

Hansen, A.M.; Ortega-Lara, V.; Leckie, J.O.

1997-01-01

Full text: In order to evaluate the migration behavior of radioactive cesium and strontium while transported from continental aquatic systems to marine environments, the sorption behaviors for these metals were evaluated in several different environments. Laboratory experiments using radioactive tracers, and equilibrium as well as time dependent modeling were used to evaluate and quantify the distribution of the two elements as a function of element chemistry, solid substrate characteristics and solution composition. The experimental conditions reflected salinities ranging from those found in rivers and lakes through estuaries to the ocean. Adsorption constants were obtained for strontium in natural sediments from these aquatic environments. The strontium specification was evaluated in solution as well as in the adsorbed state. Sorption of strontium occurred mainly as outer sphere complexes. Major cations, ligands (soluble and particulate), ionic strength, and pH were among parameters that affected the distribution of cesium and strontium between adsorbed and dissolved forms. Time-dependent sorption behaviors were observed under study dissolved salt and suspended sediment conditions. Desorption occurred to some degree for all sediment types. Cesium was exchanged with potassium and sodium in clay minerals and was therefore less desorbed than would be expected. The results allowed the description of migration behaviors of two important pollutants from the atomic energy industry

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)

Simulating the Transfer of Strontium-90 from Soil to Leafy Vegetables by Using Strontium-88.

Science.gov (United States)

Kuke, Ding; Shujuan, Liu; Yingxue, He; Dong, Yan; Fengshou, Zhang; Shuifeng, Wang; Jinghua, Guo; Wei, Zhang; Xin, Wang; Xiaoyan, Jiang

The transfer, from soil to Chinese cabbage and spinach, of radioactive strontium-90 released as a result of accidents in nuclear power stations was studied using a stable isotope of strontium, namely nuclide strontium-88 ( 88 Sr). The study led to an experimental model for assessing the hazard of radionuclide strontium-90 ( 90 Sr) entering the food chain and for predicting the risk to food safety. Chinese cabbage and spinach were grown in pots in a greenhouse and irrigated with deionized water containing known quantities of strontium. Based on the strontium content of that water, the plants were divided into five groups (treatments) and strontium content of the soil, and 30-day-old plants were determined by inductively coupled plasma atomic emission spectroscopy instrument (ICP-AES). Data on the strontium content of soil and plants enabled the development of a model using MATLAB, a mathematical software package, which included curve fitting and problem solving using regression equations and differential equations. Although strontium curves for leaves, stems, and roots of Chinese cabbage were not exactly the same, all showed a non-linear increase when compared with the increase in the content of strontium in soil. Strontium curves for leaves, stems, and roots of spinach were very similar and showed an initial increase followed by a decrease. Strontium concentrations in both Chinese cabbage and spinach were initially related to the concentrations of sodium and sulfur, the next two relevant nuclides being calcium and magnesium. The relationship between calcium and strontium in Chinese cabbage was different from that in spinach. By using 88 Sr to simulate the transfer of radionuclide 90 Sr from soil to a crop, the relevant data required to deal with accidental release of strontium can be obtained using a fitting curve and regression equations, thereby providing some experimental basis for evaluating the potential hazards posed by such accidents to the food chain.

Decorporation of cesium-137; Decorporation du cesium-137

Energy Technology Data Exchange (ETDEWEB)

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

1998-12-31

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

Decorporation of cesium-137; Decorporation du cesium-137

Energy Technology Data Exchange (ETDEWEB)

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

1997-12-31

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

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

International Nuclear Information System (INIS)

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

1995-01-01

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

Crystalline silicotitanates -- novel commercial cesium ion exchangers

International Nuclear Information System (INIS)

Braun, R.; Dangieri, T.J.; Fennelly, D.J.

1996-01-01

A new class of inorganic ion exchangers called crystalline silicotitanates (CST), invented by researchers at Sandia National Laboratories and Texas A ampersand M University, has been commercialized in a joint Sandia-UOP effort. The original developmental materials exhibited high selectivity for the ion exchange of cesium, strontium, and several other radionuclides from highly alkaline solutions containing molar concentrations of Na + . The materials also showed excellent chemical and radiation stability. These CST properties made them excellent candidates for treatment of solutions such as the Hanford tank supernates and other DOE radwastes. Sandia and UOP, under a Cooperative Research and Development Agreement (CRADA), developed CSTs in the powdered form and in an engineered form suitable for column ion exchange use. A continuous-flow, column ion exchange process is expected to be used to remove Cs and other radionuclides from the Hanford supernatant. The powder material invented by Sandia and Texas A ampersand M consists of submicron-size particles. It is not designed for column ion exchange but may be used in other applications such as batch waste processing. Data are also presented confirming the excellent stability of the commercial CSTs over a broad pH range and the high radiation stability of the exchangers. In addition, data are provided that demonstrate the high physical strength and attrition resistance of IONSIV reg-sign IE-911, critical properties for column ion exchange applications

Conceptual and Numerical Modeling of Radionuclide Transport and Retention in Near-Surface Systems

International Nuclear Information System (INIS)

Pique, Angels; Arcos, David; Grandia, Fidel; Molinero, Jorge; Duro, Lara; Berglund, Sten

2013-01-01

Scenarios of barrier failure and radionuclide release to the near-surface environment are important to consider within performance and safety assessments of repositories for nuclear waste. A geological repository for spent nuclear fuel is planned at Forsmark, Sweden. Conceptual and numerical reactive transport models were developed in order to assess the retention capacity of the Quaternary till and clay deposits for selected radionuclides, in the event of an activity release from the repository. The elements considered were carbon (C), chlorine (Cl), cesium (Cs), iodine (I), molybdenum (Mo), niobium (Nb), nickel (Ni), radium (Ra), selenium (Se), strontium (Sr), technetium (Tc), thorium (Th), and uranium (U). According to the numerical predictions, the repository-derived nuclides that would be most significantly retained are Th, Ni, and Cs, mainly through sorption onto clays, followed by U, C, Sr, and Ra, trapped by sorption and/or incorporation into mineral phases

Ion exchange flowsheet for recovery of cesium from purex sludge supernatant at B Plant

International Nuclear Information System (INIS)

Carlstrom, R.F.

1977-01-01

Purex Sludge Supernatant (PSS) contains significant amounts of 137 Cs left after removal of strontium from fission product bearing Purex wastes. To remove cesium from PSS, an Ion Exchange Recovery system has been set up in Cells 17-21 at B Plant. The cesium that is recovered is stored within B Plant for eventual purification through the Cesium Purification process in Cell 38 and eventual encapsulation and storage in a powdered form at the Waste Encapsulation Storage Facility. Cesium depleted waste streams from the Ion Exchange processes are transferred to underground storage

Interaction of radionuclides in severe accident conditions

International Nuclear Information System (INIS)

Nagrale, Dhanesh B.; Bera, Subrata; Deo, Anuj Kumar; Paul, U.K.; Prasad, M.; Gaikwad, A.J.

2015-01-01

Nuclear power plants are designed with inherent engineering safety systems and associated operational procedures that provide an in-depth defence against accidents. Radionuclides such as Iodine, Cesium, Tellurium, Barium, Strontium, Rubidium, Molybdenum and many others may get released during a severe accident. Among these, Iodine, one of the fission products, behaviour is significant for the analysis of severe accident consequences because iodine is a chemically more active to the potential components released to the environment. During severe accident, Iodine is released and transported in aqueous, organic and inorganic forms. Iodine release from fuel, iodine transport in primary coolant system, containment, and reaction with control rods are some of the important phases in a severe accident scenario. The behaviour of iodine is governed by aerosol physics, depletion mechanisms gravitational settling, diffusiophoresis and thermophoresis. The presence of gaseous organic compounds and oxidizing compounds on iodine, reactions of aerosol iodine with boron and formation of cesium iodide which results in more volatile iodine release in containment play significant roles. Water radiolysis products due to presence of dissolved impurities, chloride ions, organic impurities should be considered while calculating iodine release. Containment filtered venting system (CFVS) consists of venturi scrubber and a scrubber tank which is dosed with NaOH and NaS_2O_3 in water where iodine will react with the chemicals and convert into NaI and Na_2SO_4. This paper elaborates the issues with respect to interaction of radionuclides and its consideration in modeling of severe accident. (author)

Hydrogeochemical processes affecting the migration of radionuclides in a fluvial sand aquifer at the Chalk River Nuclear Laboratories

International Nuclear Information System (INIS)

Jackson, R.E.; Inch, K.J.

1980-01-01

In the mid-1950's two experimental disposals of liquid radioactive waste containing about 700 curries of strontium-90 and cesium-137 were made into pits in sandy ground at one of the disposal areas at Chalk River Nuclear Laboratories. Since then, the wastes have migrated into two nearby aquifers and have chromatographically separated into strontium-90 and cesium-137 plumes moving at velocities less than that of the transporting groundwater. Analysis of radioactively contaminated aquifer sediments showed that most of the strontium-90 is exchangeably adsorbed, primarily to feldspars and layer silicates (mainly biotite); the rest is either specifically adsorbed to iron (III) and perhaps manganese (IV) oxhydroxides or fixed to unknown sinks. Less than one half of adsorbed cesium-137 is exchangeable with 0.5 m calcium chloride; the high levels of cesium-137 adsorption and fixation are probably due to its reaction with micaceous minerals. Complexation of strontium-90 and cesium-137 does not appear to be an important factor affecting their transport or adsorption. In studies of groundwater quality or pollution, dissolved oxygen and sulfide should be measured in addition to the redox potential since it allows independent assessment of the redox levels. The latter were found to affect the mobility of multivalent transition metals and nonmetals. (DN)

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

International Nuclear Information System (INIS)

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

2015-01-01

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

''Crown molecules'' for separating cesium

International Nuclear Information System (INIS)

Dozol, J.F.; Lamare, V.

2002-01-01

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

Radionuclides in forest biogeocenose elements

International Nuclear Information System (INIS)

Bulavik, I.M.; Zhuchenko, T.A.

1992-01-01

In 1991 year investigations are made on a studying of the radionuclide distribution (CS-137 and Sr-90) through the main forest biogeocenose elements (a litter a mineral soil layer, overground trees parts) on 5 experimental objects of Gomel' region with a various contamination. Radiation characters of the objects are done. As compared with 1989 year cesium and strontium migration from tress into the litter and from the litter to the soil is shown. In the litter and upper soil layer (5 m) contents of Cs-137 and Sr-90 are 95 and 80% accordingly. The Sr-90 concentration in the wood and the isotope concentration change through yearly layers (1986-1991 years) are studied. Wood layers formed to the accident have a lesser cesium concentration, especially in the oax-tree. The highest Cs and Se translocation, into the wood is noted in the pine the lesse one in the oax-tree. Among all elements of the biogeocenose the highest Cs-137 concentration the litter has and then one-year-old shoots, needles, lives, the bark and the wood go on. Even on the sixth year after the accident Cs concentration in the wood was 20-30 times less, than the one in needes and one-year-old shoot of this year. 4 refs.; 5 tabs

Transport and accumulation of radionuclides in soil

International Nuclear Information System (INIS)

Frissel, M.J.; Jakubick, A.T.; Kernforschungszentrum Karlsruhe G.m.b.H.

1979-01-01

The movement of radioactive isotopes through the water phase of soils is by far the most important. Most of the water-transported radioactive isotopes (radionuclides) occur via their dissolved salts, while the rest is carried by small soil particles to which the radionuclides are adsorbed. In the case of many chemicals, it is possible to calculate the movement or migration through soil from adsorption measurements made in the laboratory and from knowledge of the flow pattern of soil water. With increasing complexity of the chemical-soil-water system predictions become more uncertain. In the case of radionuclides the amounts expressed in units of weight are extremely small. This renders terms such as 'soluble' or 'insoluble' inapplicable. In these cases transport of 'radiocolloids' and adsorbed particles as 'insoluble' compounds may be more significant. For fallout strontium and cesium reliable predictive models have been developed. For fallout plutonium such models are under development. For calculations or predictions of the migration of radioactive material from deep soil layers to the soil surface fewer mathematical models are available. Many laboratory studies cannot yet be made due to lack of suitable soil samples from the sites under study. Nevertheless safety studies already carried out in a preliminary way are reliable, since factos such as adsorption of radionuclides on soils are neglected; consequently most safety studies overestimate possible risks. Further studies are required to ascertain how 'pessimistic' are the present safety criteriy. (orig./MG) [de

Comparative placental transfer, localization, and effects of radionuclides in experimental animal and human pregnancies

International Nuclear Information System (INIS)

Sikov, M.R.; Traub, R.J.; Meznarich, H.K.

1992-01-01

Estimating radiation doses to the human embryo/fetus from radionuclides and predicting effects requires extrapolation of data from studies of laboratory species with scaling for species-specific developmental stage and gestational time relationships and maturities at birth. Combinations of fetal-to-maternal ratios of concentrations, patterns of deposition, transfer kinetics, and compartmental and physiologic models are used to predict radioactivity levels and radiation doses to the conceptus. There is agreement between values expressing fractional transfer across the placenta with values for fractional absorption from gastrointestinal tract or lung for most substances. Information about three elements - cesium, strontium, and iodine - serve to present comparative approaches to predicting radiation dose and effect. 25 refs., 11 figs., tab

Diffusion mechanisms of strontium, cesium and cobalt in compacted sodium bentonite

International Nuclear Information System (INIS)

Muurinen, A.; Rantanen, J.; Penttilae-Hiltunen, P.

1986-01-01

For a porous water-saturated material where diffusion in the porewater, sorption on the solid material and diffusion of the sorbed ions (surface diffusion) occur, a diffusion equation can be derived where the apparent diffusivity includes two terms. One represents diffusion in the pore-water, the other surface diffusion. In this research diffusion mechanisms were studied. The apparent diffusivities of strontium, cesium and cobalt in compacted sodium bentonite were measured by a non-steady state method. The sorption factors were adjusted using different sodium chloride solutions, groundwater and addition of EDTA for saturation of the bentonite samples. The corresponding sorption factors were measured by a batch method. The results suggest that cations diffuse also while being sorbed. A combined pore diffusion-surface diffusion model has been used to explain the transport and the corresponding diffusivities have been evaluated. The surface diffusivities (D/sub s/) of Sr and Cs were 8-9 x 10 -12 m 2 /s and 4-7 x 10 -13 m 2 /s respectively. The pore diffusivity epsilon D/sub p/ of Cs was 3.5 x 10 -11 m 2 /s which has been used also for Sr. The sorption mechanisms of Co seems to be different from that of Sr or Cs and the results allow no specific conclusions of the diffusion mechanisms of Co. The apparent diffusivity of Co ranged from 2 x 10 -14 to 7 x 10 -14 m 2 /s. The anionic Co-EDTA seems to follow some other diffusion mechanism than the cations

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

Science.gov (United States)

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

2001-01-01

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

Investigations of Baltic See radioactivity within 1976-1980

International Nuclear Information System (INIS)

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

1983-01-01

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

Alginate enhances excretion and reduces absorption of strontium and cesium in rats

International Nuclear Information System (INIS)

Idota, Yoko; Harada, Hitomi; Tomono, Takumi; Morimoto, Kaori; Kakinuma, Chihaya; Ogihara, Takuo; Kobayashi, Shoko; Miyajima, Chihiro; Kasahara, Fumiyoshi

2013-01-01

Alginate (ALA), which is an intercellular polysaccharide associated with brown algae, is used as a food additive, a health food and a medicine. Here, we first examined the adsorption of strontium (Sr) and cesium (Cs) by ALA in vitro, and then evaluated the effects of ALA on absorption and excretion of Sr and Cs in rats, in order to evaluate its potential usefulness for minimizing radiation damage from materials released after a nuclear accident. Both Sr and Cs were concentration-dependently adsorbed by sodium alginate (ALA-Na) in vitro. In rats given diet containing either ALA-Na or calcium alginate (ALA-Ca) for two weeks, the plasma concentration of Sr gradually decreased compared with the controls (normal diet); however, in the case of Cs, the plasma concentration was decreased only in the ALA-Ca group, but not the ALA-Na group. Moreover, we examined the effect of preadministration of diet containing either ALA-Na or ALA-Ca on absorption of Sr and Cs administered orally as the chloride salts to rats. Absorption of both Sr and Cs was reduced in the ALA-Ca group, while absorption of only Sr was reduced in the ALA-Na group. Safety assessments indicated that ALA-Ca is safer than ALA-Na. These results indicate that ALA-Ca reduces absorption and promotes excretion of both Sr and Cs, while ALA-Na does so only for Sr. (author)

Use to titanium-treated zeolite for plutonium, strontium, and cesium removal from West Valley alkaline wastes and sludge wash wastes

International Nuclear Information System (INIS)

Bray, L.A.; Hara, F.T.

1993-01-01

Zeolite (IONSIV IE-96) treated with a titanium (Ti) solution will extract traces of plutonium (Pu), strontium (Sr), and cesium (Cs) found in the West Valley Nuclear Services Co., Inc. (WVNS) alkaline supernatant and alkaline sludge water washes. Small ion exchange columns containing Ti-treated zeolite have been successfully tested at WVNS and Pacific Northwest Laboratory (PNL) for the removal of Pu. Full-scale ion exchange processing of sludge wash solution is now being developed at WVNS for use in FY 1992. Commercial manufacturing options for the production of the Ti-treated zeolite were investigated. The Ti-treated zeolite may have application at Hanford and at other U.S. Department of Energy (DOE) sites for the removal of low-level concentrations of Cs, Sr, and Pu from alkaline waste streams

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

International Nuclear Information System (INIS)

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

1997-01-01

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

Extension of Studies with 3M Empore TM and Selentec MAG *SEP SM Technologies for Improved Radionuclide Field Sampling

International Nuclear Information System (INIS)

Beals, D.M.; Bibler, J.P.; Brooks, D.A.

1996-01-01

The Savannah River Technology Center is evaluating new field sampling methodologies to more easily determine concentrations of radionuclides in aqueous systems. One methodology studied makes use of 3M EmporeTM disks. The disks are composed of selective resins embedded in a Teflon support. The disks remove the ion of interest from aqueous solutions when the solution is passed through the disk. The disk can then be counted directly to quantify the isotope of interest. Four types of disks were studied during this work: for the extraction of technetium (two types), cesium, plutonium, and strontium. A sampler has been developed for automated, unattended, in situ use of the EmporeTM disks

Extension of Studies with 3M Empore TM and Selentec MAG *SEP SM Technologies for Improved Radionuclide Field Sampling

Energy Technology Data Exchange (ETDEWEB)

Beals, D.M. [Westinghouse Savannah River Company, AIKEN, SC (United States); Bibler, J.P.; Brooks, D.A.

1996-07-10

The Savannah River Technology Center is evaluating new field sampling methodologies to more easily determine concentrations of radionuclides in aqueous systems. One methodology studied makes use of 3M EmporeTM disks. The disks are composed of selective resins embedded in a Teflon support. The disks remove the ion of interest from aqueous solutions when the solution is passed through the disk. The disk can then be counted directly to quantify the isotope of interest. Four types of disks were studied during this work: for the extraction of technetium (two types), cesium, plutonium, and strontium. A sampler has been developed for automated, unattended, in situ use of the EmporeTM disks.

Radionuclides in ground-level air

International Nuclear Information System (INIS)

Sinkko, K.

1987-01-01

In the air surveillance programme the concentrations of artificial radionuclides are monitored in the air close to the ground to obtain the necessary basic data for estimating the exposure of the Finnish population to fall-out radionuclides and also to detect atmospheric traces of radioactive materials caused by their use or production. Airborne dust is collected on filters with high-volume air samplers and the concentrations of gamma-emitting radionuclides in the air are evaluated. In the first quarter of 1986 only long-lived cesium, caused by earlier atmospheric nuclear explosions was detected. The concentrations of cesium were very low. In January and March a small amount of short-lived, fresh fission and activation products were also observed

Leaching properties and chemical compositions of calcines produced at the Idaho Chemical Processing Plant

International Nuclear Information System (INIS)

Staples, B.A.; Paige, B.E.; Rhodes, D.W.; Wilding, M.W.

1980-01-01

No significant chemical differences were determined between retrieved and fresh calcine based on chemical and spectrochemical analyses. Little can be derived from the amounts of the radioisotopes present in the retrieved calcine samples other than the ratios of strontium-90 to cesium-137 are typical of aged fission product. The variations in concentrations of radionuclides within the composite samples of each bin also reflect the differences in compositions of waste solutions calcined. In general the leaching characteristics of both calcines by distilled water are similar. In both materials the radionuclides of cesium and strontium were selectively leached at significant rates, although cesium leached much more completely from the alumina calcine than from the zirconia calcine. Cesium and strontium are probably contained in both calcines as nitrate salts and also as fluoride salts in zirconia calcine, all of which are at least slightly soluble in water. Radionuclides of cerium, ruthenium, and plutonium in both calcines were highly resistant to leaching and leached at rates similar to or less than those of the matrix elements. These elements exist as polyvalent metal ions in the waste solutions before calcination and they probably form insoluble oxides and fluorides in the calcine. The relatively slow leaching of nitrate ion from zirconia calcine and radiocesium from both calcines suggests that the calcine matrix in some manner prevents complete or immediate contact of the soluble ions with water. Whether radiostrontium forms slightly fluoride salts or forms nitrate salts which are protected in the same manner as radiocesium is unknown. Nevertheless, selective leaching of cesium and strontim is retarded in some manner by the calcine matrix

Present and potential contamination of the river system at Mayak PA

International Nuclear Information System (INIS)

Amundsen, I.; Strand, P.; Malyshev, S.V.

1999-01-01

Studies of mobility of radionuclides in environmental samples at Mayak show that strontium-90 is the most mobile of the relevant radionuclides and hence can be transported by river water. Cesium-137, although less mobile, can also be transported over large distances. The main source of river contamination today is the remobilization of strontium-90 from the boggy area at the upper reaches of Techa River (Asanov Swamp). Regular Russian monitoring programmes show that levels of strontium-90 leaving the swamp are three times higher than levels entering the swamp. The net outflow from the Swamp is now estimated to 2-3% of the 37 TBq of strontium-90 located in the swamp, 1992 levels

Radionuclides at the Hudson Canyon disposal site

International Nuclear Information System (INIS)

Schell, W.R.; Nevissi, A.E.

1983-01-01

A sampling and analytical program was initiated in June 1978 to measure radionuclides in water, sediments, and biota collected at the deepwater (4000 m) radioactive waste disposal site at the mouth of the Hudson Canyon 350km off New York Harbor in the western Atlantic Ocean. Plutonium, americium, cesium, strontium, and uranium series isotopes were measured in selected samples; the /sup 210/Pb data were used to give sedimentation and mixing rates in the upper sediment layers. The results showed that /sup 137/Cs, /sup 239,240/Pu, and /sup 238/Pu were found at low concentrations in the skin, viscera, and stomach contents for some of the fish collected. Significant concentrations of /sup 241/Am were found in tissues of the common rattail Coryphaenoides (Macrouridae) collected at the disposal site, suggesting a local source for this radionuclide and biological accumulation. The edible muscle of this fish contained less than 2.6 x 10/sup -5/ Bq g/sup -1/ (dry wt) of /sup 239,240/Pu. Radionuclides measured in sediment-core profiles showed that mixing occurred to depths of 16 cm and that variable sedimentation or mixing rates, or both, exist at 4000 m deep. Radionuclide deposition near the canisters was not found to be significantly higher than the expected fallout levels at 4000 m deep. At the mouth of the Hudson Canyon variable sedimentation and mixing rates were found using the natural unsupported /sup 210/Pb tracer values; these variable rates were attributed to sediment transport by the currents and to bioturbation

Radionuclide kinetics and biological effects from strontium-89 and cerium-144 at combined inocculation with the phosphorganic pesticide ''Agria-1060'' (Fazolon) in experimental animals

International Nuclear Information System (INIS)

Peyankov, I.Ya.

1985-01-01

Kinetics of 89 strontium and 144 cerium in the rat were studied for the case of single intake of either radionuclide combined with an organophosphorus pesticide, Agria-1060, and for chronic intake of 89 strontium with the same pesticide. After treatments involving minimal effective activities and concentrations, some hematological parameters were monitored, as well as biochemical (SGOT, SGPT, serum cholinesterase) and phagocytic activity of neutrophils. Unfavorable changes in RBC counts were attributable to the chemical factor, while those in WBC counts resulted from radiation exposure. Serum cholinesterase activity underwent shifts distinctly showing a phasic pattern and related in the main to the chemical agent. SGOT and SGPT activities were more markedly affected by 144 cerium combined with pesticide than by sole agent treatments. Phagocytic index response was observed to change according to radionuclide organotropism. As for chronic treatments, neutrophil phagocytic activity proved most susceptible, suggesting occurrence of changes in the immune system under such exposure conditions

A thermoelectric-conversion power supply system using a strontium heat source of high-level radioactive nuclear waste

International Nuclear Information System (INIS)

Chikazawa, Yoshitaka

2011-01-01

A thermoelectric-conversion power supply system with radioactive strontium in high-level radioactive waste has been proposed. A combination of Alkali Metal Thermo-Electric Conversion (AMTEC) and a strontium fluoride heat source can provide a compact and long-lived power supply system. A heat source design with strontium fluoride pin bundles with Hastelloy cladding and intermediate copper has been proposed. This design has taken heat transportation into consideration, and, in this regard, the feasibility has been confirmed by a three-dimensional thermal analysis using Star-CD code. This power supply system with an electric output of 1 MW can be arranged in a space of 50 m 2 and approximately 1.1 m height and can be operated for 15 years without refueling. This compact and long-lived power supply is suitable for powering sources for remote places and middle-sized ships. From the viewpoint of geological disposal of high-level waste, the proposed power supply system provides a financial base for strontium-cesium partitioning. That is, a combination of minor-actinide recycling and strontium-cesium partitioning can eliminate a large part of decay heat in high-level waste and thus can save much space for geological disposal. (author)

Decorporation of cesium-137

International Nuclear Information System (INIS)

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

1997-01-01

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

Variability of the strontium-90 and caesium-137 burden of native plants and animals

Energy Technology Data Exchange (ETDEWEB)

Eberhardt, L L

1946-10-17

Cesium-137 and /sup 90/Sr body burdens were determined in plants and animals at selected sites in Alaska, Idaho, Nevada, Utah, California, and Maryland, and coefficients of variations were derived. Coefficients of variation for burdens of /sup 90/Sr and /sup 137/Cs were suprisingly consistent over a wide range of plants and animals. Values for /sup 90/Sr ranged from about 0.30 to 0.45 while those for /sup 137/Cs appeared somewhat lower, ranging roughly from 0.25 to 0.35. Various factors possibly affecting individual sets of data were indicated. With one exception (Maryland white-tailed deer), the bone-strontium-90 values were calculated in terms of picocuries (10/sup -12/c) per g calcium (strontium units). Analysis of the Alaskan caribou data in terms of picocuries per g standard dry weight yields virtually the same coefficient of variation. The plant data were calculated on the standard dry weight basis, while soil-levels were on a unit area basis. All /sup 137/Cs values were expressed in units per g dry weight. Results reported here should not be interpreted as meaning that the coefficient of variation for levels of these two radionuclides is everywhere roughly constant.

Chernobyl: one year after; radiological measurements in Chile

International Nuclear Information System (INIS)

Pinones O, O.

1987-01-01

The results of environmental radionuclides activity measurements in 694 samples obtained from National Sampling Network and 152 samples from foods imported during april 1986 - april 1987 in order to evaluate the possible influence, in Chile, of the Chernobyl accident, is presented. The results showed that only long life radionuclides like strontium 90 and Cesium 137 were detected. However, Cesium 134 in some imported food was found in lowlevels. The higher value was 36.0% of Maximum Permissible level referring to radiocesium (370 Bq/Kg). (author)

Applicability of sodium alginate in decorporation therapy of strontium radioisotopes in human being

International Nuclear Information System (INIS)

Ferreira, Aloisio Cordilha

1999-10-01

The increasing release of fission products from nuclear weapon tests in the environment has been rising the levels of radioactive contamination of food chains caused by the fall-out of these elements. In cases of accidental exposure, human subjects could be submitted to an internal contamination, which is likely to include several radionuclides. Special concern must be given, however, to the radioactive isotopes of strontium, cesium and iodine, along with the highly radio toxic transuranium elements like cerium. It was found that sodium alginate, a polyelectrolyte commonly used in food industry and obtained from brown algae (Phaeophyceae), provides the selective suppression of absorption of radioactive strontium presented in the ingested food material with no disturbance of the electrolyte balance nor undesirable side effects, even for a long term treatment. Moreover, these patterns were maintained when alginate was associated to other decontamination additives, specially those related to the other radioisotopes mentioned above, as, in this case, losses in the effectiveness, mutual interference or adverse health effects were not detected. These conclusions ground the discussion about the present trend in the usual choice of EDTA/DTPA complex therapy rather than of alginate therapy for medical assistance of radiocontaminated patients, although they corroborate the efficiency and usefulness of alginate salts in situations related to extensive intakes of strontium radioisotopes alone or associated to other fission products. The purpose of the present work is to make a general review of the alginate therapy as well as to discuss its present and future therapeutic importance from the scientific and institutional points of view. (author)

Method for synthesizing pollucite from chabazite and cesium chloride

International Nuclear Information System (INIS)

Pereira, C.

1999-01-01

A method is described for immobilizing waste chlorides salts containing radionuclides and hazardous nuclear material for permanent disposal, and in particular, a method is described for immobilizing waste chloride salts containing cesium, in a synthetic form of pollucite. The method for synthesizing pollucite from chabazite and cesium chloride includes mixing dry, non-aqueous cesium chloride with chabazite and heating the mixture to a temperature greater than the melting temperature of the cesium chloride, or above about 700 C. The method further comprises significantly improving the rate of retention of cesium in ceramic products comprised of a salt-loaded zeolite by adding about 10% chabazite by weight to the salt-loaded zeolite prior to conversion at elevated temperatures and pressures to the ceramic composite. 3 figs

Influence of selected factors on strontium sorption on bentonites

International Nuclear Information System (INIS)

Galambos, M.; Kufcakova, J.; Rajec, P.

2007-01-01

Sorption on bentonite will play an important role in retarding the migration of radionuclides from a waste repository. Bentonite is a natural clay and one of the most promising candidates for use as a buffer material in the geological disposal systems for high-level nuclear waste. It is intended to isolate metal canisters with highly radioactive waste products from the surrounding rocks because of its ability to retard the movement of radionuclides by sorption. Bentonite is characterized by low permeability, water swelling capability and excellent sorption potential for cationic radionuclides. To correctly assess the sorption potential of radionuclides on bentonite is essential for the development of predictive migration models. The sorption of strontium on bentonite from different Slovak deposits - Jelsovy potok, Kopernica and Lieskovec has been investigated under various experimental conditions, such as contact time, sorbate concentrations, presence of complementary cation. Sorption was studied using the batch technique. The uptake of Sr was rapid and equilibrium was reached almost instantaneously. The instantaneous uptake may be due to adsorption and/or exchange of the metal with some ions on the surface of the adsorbent. The best sorption characteristics distinguish bentonite Kopernica, sorption capacity for Sr of the fraction under 45 mm is 0,48 mmol·g -1 for Sr. The highest values of distribution coefficient were reached for the bentonite Jelsovy potok. Radiation stability has been investigated, the higher sorption parameters were observed for the irradiated bentonites, which can be explained by the increase of specific surface of the bentonite samples. The presence of complementary cations depresses the sorption of Sr on bentonite. Cations Ca 2+ exhibit higher effect on cesium sorption than the Na 2+ ions. Results indicate that the sorption of Sr 2+ on bentonite will be affected by the presence of high concentrations of various salts in the waste water

Sorption of iodine, chlorine, technetium and cesium in soil

International Nuclear Information System (INIS)

Soederlund, M.; Lusa, M.; Lehto, J.; Hakanen, M.; Vaaramaa, K.

2011-01-01

The safety assessment of final disposal of spent nuclear fuel will include an estimate for the behavior of waste nuclides in the biosphere. As a part of this estimate also the sorption of radioactive iodine, chlorine, technetium and cesium in soil is to be considered. The chemistry and the sorption of these radionuclides in soils are described in this literature survey. Behavior of I-129, Cl-36 and Tc-99 in the environment is of great interest because of their long half-lives and relatively high mobilities. The importance of Cs-135 arises from its high content in spent nuclear fuel and long physical half-life, even though it is considered relatively immobile in soil. Factors affecting the migration and sorption of radionuclides in soils can be divided into elemental and soil specific parameters. The most important elemental factor is the speciation of the element, which is influenced by the soil redox potential, pH and complex forming ligands. Soil micro-organisms can either serve as sorbents for radionuclides or affect their speciation by altering the prevailing soil redox conditions. Soil organic matter content and mineral properties have a marked influence on the retention of radionuclides. The sorption of anionic radionuclides such as I-, Cl- and TcO 4 - is pronounced in the presence of organic matter. Clay minerals are known to bound cesium effectively. The effect of speciation of radioactive iodine, chlorine, technetium and cesium in soil is considered in this study, as well as the effect of soil micro-organisms, organic matter and mineral properties. (orig.)

Adsorption of Some Hazardous Radionuclides on Cerium(IV) Antimonate

International Nuclear Information System (INIS)

Aly, H.F.; Zakaria, E.S.; Shady, S.A.; El-Naggar, I.M.

1999-01-01

Cerium(IV) antimonate had been prepared by the dropwise addition of 0.6 M antimony pentachloride and 0.6 M cerium ammonium nitrate solutions by a molar radio of Ce/Sb 0.75. Exchange isotherms for H +/ Co 2+ , H +/ Cs +, H +/ Zn 2+ , H +/ Sr 2+ and H +/ Eu 3+ have been determined at 25, 40 and 60 degree. Besides it was proved that europium is physically adsorbed while zinc, strontium, cobalt and cesium are chemically adsorbed. Moreover, the heat of adsorption of zinc, strontium, cobalt and cesium on cerium(IV) antimonate had been calculated and indicated that cerium(IV) antimonate is of endothermic behaviour towards these ions. Also the distribution coefficients of these ions were determined and it was found that the selectivity in the order: Eu 3+ >Sr 2+ > Cs +> Na +

Radionuclide toxicity

International Nuclear Information System (INIS)

Galle, P.

1982-01-01

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

Deposition of caesium and strontium substances on growing crops: Effects and countermeasures

International Nuclear Information System (INIS)

Bengtsson, S.

2010-01-01

Full text: To investigate how the two radionuclides caesium ( 134 Cs) and strontium ( 85 Sr) are taken up and transported to the harvested parts (the seeds) by fallout in a growing crop. Further on how this is related to the size and time of the fallout. From the information collected recommendation of suitable countermeasures at different scenarios to prevent further spreading to food stuff can be suggested. In the project a number of field trials where artificial deposited by the two radionuclides 134 Cs and 85 Sr in a contaminated rainfall, on the two agricultural crops Brassica napus L. (spring rape) and Triticum aestivum L. (spring wheat). The trial contained different treatments where the radionuclides where deposited by a rainfall simulator at different growing stages of the crops. The field trial continues for two more years and the reason for that is due to the variation of the climate for the different years. The radionuclides were applied in the form of a wet deposition and the rainfall was about 1 mm m -1 with a concentration of 20 kBq m -1 for each radionuclide. Samples were taken from the plots at the day(s) after the treatment of contaminated rainfall, both from the latest treated plots and from the earlier treated plots. The hypotheses are: 1. That the size of the deposition and the time in relation to the development stages of the crop will steer how much caesium and strontium that are coughed, detained and transferred to the harvested parts. 2. That the levels of caesium and strontium in the harvested parts of the crops are related to the insensitivity of the rainfall after a deposition and also how long time the first intensive rain will occur. 3. That the size of caesium and strontium in harvested plant parts are related to the size of uptake throw the leaves. 4. If the deposition of caesium and strontium will be the same, the levels of caesium will be much higher than strontium in the harvested parts. (author)

Evaluation of radionuclide migration in forest ecosystems in TEMAS project

International Nuclear Information System (INIS)

Claver, F.; Vazquez, C.

1998-01-01

The applicability study of the best countermeasures for the restoration of environments contaminated by the accidental liberation of radionuclides, requires the assessment of the space and the temporal flow of radionuclides. The objective of the multinational project TEMAS (Techniques and Management Strategies for environmental restoration and their ecological consequences), that is carried out under EU-CIEMAT contract n. TI4-CT95-0021, is the development of management tool that provides the necessary support in the selection of the best strategies of environmental restoration after a nuclear accident, considering all the possible affected environments (urban, agricultural, semi natural and forest). In the forest environment,CIEMAT is working with the University of Lund (Sweden) and the Physical Science Faculty of the University of Seville in the prognosis of the distribution of Cesium and Strontium in forest ecosystems and through the associated production systems. This paper summarizes the study of the response of two different models, FORM and FORESTPATH to predict the radionuclides flow in the event of an accidental contamination of a forest. The comparison of results has been carried out over a period of 100 years after deposition on a coniferous forest. Although the approaches are different, the results obtained (using generic parameters) indicate that either model could to be selected for the analysis of the intervention in TEMAS. (Author) 14 refs

Sorption of radionuclides on inorganic sorbents

International Nuclear Information System (INIS)

Rajec, P.; Matel, L.

1995-01-01

The sorption of cesium, strontium, plutonium and americium from water solution on natural zeolite, clay minerals, synthetic zeolites and ferrocyanides in silica gel matrix was studied. The same experiments but with synthetic zeolites irradiated by the dose 100 kGy proved no change in sorption properties. 1 tab., 4 refs

Final report on a field study of soil-to-plant transfer radioactive caesium, strontium and zinc in Tropical Northern Australia

International Nuclear Information System (INIS)

Twining, J.; Payne, T.; Russell, R.; Wilde, K; McOrist, G.; Wong, H.; Shotton, P.; Tagami, K.; Itakura, T.

2003-01-01

Soil-to-plant radionuclide transfer factors for cesium ( 134 Cs), strontium ( 85 Sr) and zinc ( 65 Zn) into sorghum and mung plants grown in tropical Australia have been determined over a four-year study period. The crops were grown on two types of red earth soils. Transfer factors for Cs and Sr are not substantially different from the expected values based on previous studies, reported in the general literature and compiled in the IUR database, mainly performed within temperate climates. In contrast, the values for zinc (Zn) are more than an order of magnitude greater than anticipated. Most of the radioactivity added to the soils has been retained in the top 5 cm of both soils. There has been a general decline in soil-to-plant transfer of Cs and Zn as time has increased

Equilibrium concentration of radionuclides in cement/groundwater/carbon steel system

International Nuclear Information System (INIS)

Keum, D. K.; Cho, W. J.; Hahn, P. S.

1997-01-01

Equilibrium concentration of major elements in an underground repository with a capacity of 100,000 drums have been simulated using the geochemical computer code (EQMOD). The simulation has been carried out at the conditions of pH 12 to 13.5, and Eh 520 and -520 mV. Solubilities of magnesium and calcium decrease with the increase of pH. The solubility of iron increases with pH at Eh -520 mV of reducing environment, while it almost entirely exists as the precipitate of Fe(OH) 3 (s) at Eh 520 mV of oxidizing environment. All of cobalt and nickel are predicted to be dissolved in the liquid phase regardless of pH since the solubility limit is greater than the total concentration. In the case of cesium and strontium, all forms of both ions are present in the liquid phase because they have negligible sorption capacity on cement and large solubility under disposal atmosphere. And thus the total concentration determines the equilibrium concentration. Adsorbed amounts of iodide and carbonate are dependent on adsorption capacity and adsorption equilibrium constant. Especially, the calcite turns out to be a solubility-limiting phase on the carbonate system. In order to validate the model, the equilibrium concentrations measured for a number of systems which consist of iron, cement, synthetic groundwater and radionuclides are compared with those predicted by the model. The concentrations between the model and the experiment of nonadsorptive elements - cesium, strontium, cobalt, nickel and iron, are well agreed. It indicates that the assumptions and the thermodynamic data in this work are valid. Using the adsorption equilibrium constant as a free parameter, the experimental data of iodide and carbonate have been fitted to the model. The model is in a good agreement with the experimental data of the iodide system. (author)

Removal of cesium from red deer meat

International Nuclear Information System (INIS)

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

1989-01-01

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

Strontium, cessium, and cerium radioisotope concentration in water of superficial reservoirs as determined by their accumulation in alga Cladophora glomerata

International Nuclear Information System (INIS)

Piskunov, L.I.; Gushchin, V.M.

1979-01-01

An indirect method of measuring concentrations of strontium-90,cesium-137 and cerium-144 in water is considered. The method is bsed on the accumulation of the nuclides in Cladophora glomerata Kutz, a fresh-water alga. During 10 days in the end of July, 1975, water samples (20 l) and alga samples (about 1 kg) were taken at 14 locations more or less evenly distributed along the bank of reservoir. Some locations were in coves or issues of small rivers so that almost all morphometric features of the reservoir were taken into account. The samples were processed and radiochemically analyzed, including the radiometry of standard techniques. The counting time was so selected that the statistical error did not exceed 10 %. The radionuclide concentration was calculated per unit weight of sample (pCi/l or pCi/kg of natural alga biomass). The method may be of particular importance for those radionuclides that are rapidly absorbed by bottom sediments and at the same time intensively accumulated by the hydrobios (radioisotopes of iron, cobalt, zinc, yttrium, zirconium and some others)

Fast determination of strontium radionuclides in milk with the aid of the cryptand 2.2.2

International Nuclear Information System (INIS)

Tait, D.; Haase, G.; Hartmann, R.

2004-01-01

A rapid method for separating strontium (Sr) radionuclides from liquid milk has been improved and tested for the determination of Sr-90 in milk. The method is based on the specific extraction of Sr from the milk with cryptand 2.2.2 on a cation exchange resin (Dowex Marathon C). Decontamination from other radionuclides such as those of caesium and from chemically similar elements such as calcium and barium is efficient. At least 6 samples can be treated in one day by one person. Tests were carried out on series of six 1.0 and 0.10 litre milk samples representing respectively routine milk samples and samples for fast analysis i.e milk contaminated with fresh fallout, including Ba-140, and requiring barium separation. For the 1.0 litre samples Sr recoveries ranged from 75-85% while for 0.10 liter samples the range was 65-80%. Conditions for the use of Sr-85 as yield tracer to correct for the losses were established. The method minimizes the handling of hazardous reagents. (orig.)

Total deposition of cesium-137 measured in Finland during the exercise 'RESUME 95' in August 1995

International Nuclear Information System (INIS)

Geer, L.E. De; Vintersved, I.; Arntsing, R.

1997-01-01

In the exercise called 'RESUME 95' the Nuclear Detection Group from the National Defence Research Establishment in Stockholm participated with field gamma ray measurements combined with soil sampling and profile measurements. The results are presented in this report for the measurements of cesium-137. We considered the measurements of cesium-137 at the airfield the most important part of the in-situ exercise. Data was of course collected also for cesium-134 and natural radionuclides but time has not permitted a full analysis of these radionuclides. The methodology would, however, be the same as applied for cesium-137. Less attention was paid for area II and due to limited personnel resources the search exercise was not fully carried out. (au)

Total deposition of cesium-137 measured in Finland during the exercise `RESUME 95` in August 1995

Energy Technology Data Exchange (ETDEWEB)

Geer, L.E. De; Vintersved, I.; Arntsing, R. [National Defence Research Establisment, Nuclear Detection Group, Stockholm (Sweden)

1997-12-31

In the exercise called `RESUME 95` the Nuclear Detection Group from the National Defence Research Establishment in Stockholm participated with field gamma ray measurements combined with soil sampling and profile measurements. The results are presented in this report for the measurements of cesium-137. We considered the measurements of cesium-137 at the airfield the most important part of the in-situ exercise. Data was of course collected also for cesium-134 and natural radionuclides but time has not permitted a full analysis of these radionuclides. The methodology would, however, be the same as applied for cesium-137. Less attention was paid for area II and due to limited personnel resources the search exercise was not fully carried out. (au).

Total deposition of cesium-137 measured in Finland during the exercise `RESUME 95` in August 1995

Energy Technology Data Exchange (ETDEWEB)

Geer, L.E. De; Vintersved, I; Arntsing, R [National Defence Research Establisment, Nuclear Detection Group, Stockholm (Sweden)

1998-12-31

In the exercise called `RESUME 95` the Nuclear Detection Group from the National Defence Research Establishment in Stockholm participated with field gamma ray measurements combined with soil sampling and profile measurements. The results are presented in this report for the measurements of cesium-137. We considered the measurements of cesium-137 at the airfield the most important part of the in-situ exercise. Data was of course collected also for cesium-134 and natural radionuclides but time has not permitted a full analysis of these radionuclides. The methodology would, however, be the same as applied for cesium-137. Less attention was paid for area II and due to limited personnel resources the search exercise was not fully carried out. (au).

Advanced separations at Savannah River Site

International Nuclear Information System (INIS)

Thompson, M.; McCabe, D.

1996-01-01

The Savannah River Site (SRS) has many waste streams that are contaminated with radionuclides and/or hazardous materials that must be treated to remove the radioactivity (cesium, strontium, tritium, actinides) and hazardous components (polychlorinated biphenyls (PCBs), cyanide, metal ions)

Estimating the transfer of radionuclides from foodstuff into animals (meat). Contribution to the partial study 26 of the model study 'Radioecology Biblis'. Zur Abschaetzung des Transfers von Radionukliden aus dem Futter in tierische Nahrungsmittel (Fleisch). Beitrag zur Teilstudie 26 der Modellstudie 'Radiooekologie Biblis'

Energy Technology Data Exchange (ETDEWEB)

Franke, B; Hopfner, U

1978-01-01

Eating contaminated animal food represents a considerable contribution to human irradiation loading from radioactive emission. When estimating the irradiation loading, a precondition is a knowledge of the radio-nuclide transfer from the feedstuff into the meat of the domestic animal. The radio-ecology importance of this exposure path requires a precise examination of the origin of the values given by SSK with the data in the international literature. The transfer of radio-cesium, radio-strontium, radio-iodine and plutonium from feedstuff into meat/milk are especially considered.

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

International Nuclear Information System (INIS)

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

2014-01-01

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

Determination of stable cesium and strontium in rice samples by inductively coupled plasma mass spectrometry

Science.gov (United States)

Srinuttrakul, W.; Yoshida, S.

2017-06-01

For long-term radiation dose assessment models, food ingestion is one of the major exposure pathways to human. In general, the stable isotopes can serve as analogues of radioisotopes. In this study, rice samples were collected from 30 paddy fields in Si Sa Ket, Yasothon and Roi Et in the northeast of Thailand in November 2014. The concentrations of stable cesium (Cs-133) and strontium (Sr-88) in polished rice were determined by inductively coupled plasma mass spectrometry (ICP-MS). The standard reference material of rice flour (NIST 1568a) with spiked Cs and Sr was used to validate the analytical method. The concentration of Cs in polished rice from Si Sa Ket, Yasothon and Roi Et was 0.158 ± 0.167 mg kg-1, 0.090 ± 0.117 mg kg-1 and 0.054 ± 0.031 mg kg-1, respectively. The concentration of Sr in polished rice from Si Sa Ket, Yasothon and Roi Et was 0.351 ± 0.108 mg kg-1, 0.364 ± 0.215 mg kg-1 and 0.287 ± 0.102 mg kg-1, respectively. Comparison of the results with Japanese data before the Fukushima Di-ichi nuclear power plant accident showed that the concentrations of both Cs and Sr for Thai rice were higher than those for Japanese rice.

Determination of stable cesium and strontium in rice samples by inductively coupled plasma mass spectrometry

International Nuclear Information System (INIS)

Srinuttrakul, W; Yoshida, S

2017-01-01

For long-term radiation dose assessment models, food ingestion is one of the major exposure pathways to human. In general, the stable isotopes can serve as analogues of radioisotopes. In this study, rice samples were collected from 30 paddy fields in Si Sa Ket, Yasothon and Roi Et in the northeast of Thailand in November 2014. The concentrations of stable cesium (Cs-133) and strontium (Sr-88) in polished rice were determined by inductively coupled plasma mass spectrometry (ICP-MS). The standard reference material of rice flour (NIST 1568a) with spiked Cs and Sr was used to validate the analytical method. The concentration of Cs in polished rice from Si Sa Ket, Yasothon and Roi Et was 0.158 ± 0.167 mg kg -1 , 0.090 ± 0.117 mg kg -1 and 0.054 ± 0.031 mg kg -1 , respectively. The concentration of Sr in polished rice from Si Sa Ket, Yasothon and Roi Et was 0.351 ± 0.108 mg kg -1 , 0.364 ± 0.215 mg kg -1 and 0.287 ± 0.102 mg kg -1 , respectively. Comparison of the results with Japanese data before the Fukushima Di-ichi nuclear power plant accident showed that the concentrations of both Cs and Sr for Thai rice were higher than those for Japanese rice. (paper)

Determination of distribution coefficient (Kd's) of some artificial and naturally occurring radionuclide in fresh and marine coastal water sediment

International Nuclear Information System (INIS)

Al-Masri, M. S.; Mamish, S; Haleem, M. A.

2004-12-01

Distribution coefficients of artificial and natural radionuclides in fresh and marine water sediment are used in modeling radionuclide dispersion in water system, and the radiation risk and environmental investigating of impact of radioactive emissions, due to routine operations of nuclear plants or disposal and burial of radioactive waste in the environment. In the present work, distribution coefficient of uranium, lead, polonium, radium (naturally occurring radionuclides that may be emitted into the Syrian environment by the phosphate and oil industry with relatively high concentrations) and caesium 137 and strontium 85, in fresh water sediment (Euphrates River, Orantos River and Mzzerib Lake) and marine coastal water (Lattakia, Tartous and Banias). Distribution coefficients were found to vary between (5.8-17.18)*10 3 , (2.2-8.11)*10 3 , (0.22-2.08)*10 3 , (0.16-0.19)*10 3 , (0.38-0.69)*10 3 and 49-312 for polonium, lead, uranium, radium, cesium and strontium respectively. Results have indicated that most measurement distribution coefficients in the present study were lower than those values reported in IAEA documents for marine coastal sediment. In addition, variations of Kd's with aqueous phase composition and sediment elemental and mineralogical composition and its total organic materials content have been studied, where liner correlation coefficients for each isotope with different parameters have been determined. The obtained data reported in this study can be used for radioactive contaminants dispersion and transfer in Syrian river, lake and coast to assess risks to public due to discharges of the phosphate and oil industry into the Syrian environment. (Authors)

Have we to harvest the contaminated wheats?

International Nuclear Information System (INIS)

Tannenberg, P. de

1997-01-01

The institute of nuclear protection and safety (IPSN) has just developed a calculation method allowing to evaluate the radioactive contamination of harvesting. This tool would allow, in case of nuclear accident, to determine if the contaminated lands under cultivation are eatable or not. Two radionuclides have been chosen: cesium 137 and strontium 90. The experiments are conclusive: the experimental releases of cesium and strontium were comparable to these ones of the Chernobyl forbidden zone (between 10 and 40 millions of becquerels/m 2 ): the foliar contamination is proportional to the plants development. Wheats ready to be harvested capture more than 80% of the radioactivity that contaminates them. Leaves of young plants keep only 20 to 40 %. Second result: cesium is more easily washable than strontium. Third results: more late is the contamination more the plant will be irradiated; then,the wheats contaminated when they are just out of ground are nine times less contaminated than cereals contaminated just before the harvest. (N.C.)

Distribution of radionuclides in soils in surroundings of Bratislava, capital of the Slovak Republic

International Nuclear Information System (INIS)

Matel, L.; Rosskopfova, O.; Svec, V.

2000-01-01

The actual distribution of the concentration natural and man-made radionuclides in the soil from the area of Podunajske Biskupice, locality from outer part of Bratislava, Capital of Slovakia is presented. Documentation is based on the collection of soil and analysed for cesium-137, strontium-90, plutonium-239,240, and americium-241. Occurrence of natural potassium-40 as well as radionuclides from decay series of uranium and thorium in chosen soil profile are in accordance with the average concentration of those radionuclides in dominant type of soils in the monitored area. The soils were analysed using gamma spectrometry (HPGe detector with relative efficiencies 28 %, Cs-137, Ortec). Analytical procedure involve total dissolution of the samples, followed by radiochemical separation and purification using solvent extraction (Aliquat-336 - Pu-239,240; TBP - Sr-90), calcium oxalate precipitation and extraction chromatography an Eichrom TRU Resin - Am-241, UTEVA Resin - uranium and thorium.The intervals of specific activities of Cs-137, Sr-90, Pu-239,240 and Am-241 are 14.1-83.8; 3.8-29.2; 0.130-2.904, and 0.804-0.580 Bq/kg. The average values of specific activity of potassium, uranium and thorium are 481 ± 159; 270.3 ± 4.5, and 29.2 ± 4.6 Bq/kg. (authors)

Trace Metals in Groundwater and the Vadose Zone Calcite: In Situ Containment and Stabilization of Strontium-90 and Other Divalent Metals and Radionuclides at Arid West DOE

International Nuclear Information System (INIS)

Smith, Robert W.

2004-01-01

Radionuclide and metal contaminants such as strontium-90 are present beneath U.S. Department of Energy (DOE) lands in both the groundwater (e.g., 100-N area at Hanford, WA) and vadose zone (e.g., Idaho Nuclear Technology and Engineering Center at the Idaho National Engineering and Environmental Laboratory). In situ containment and stabilization of these contaminants is a cost-effective treatment strategy. However, implementing in situ containment and stabilization approaches requires definition of the mechanisms that control contaminant sequestration. We are investigating the in situ immobilization of radionuclides or contaminant metals (e.g., strontium-90) by their facilitated co-precipitation with calcium carbonate in groundwater and vadose zone systems. Our facilitated approach, shown schematically in Figure 1, relies upon the hydrolysis of introduced urea to cause the acceleration of calcium carbonate precipitation (and trace metal co-precipitation) by increasing pH and alkalinity. Subsurface urea hydrolysis is catalyzed by the urease enzyme, which may be either introduced with the urea or produced in situ by ubiquitous subsurface urea hydrolyzing microorganisms. Because the precipitation process tends to be irreversible and many western aquifers are saturated with respect to calcite, the co-precipitated metals and radionuclides will be effectively removed from the aqueous phase over the long-term. Another advantage of the ureolysis approach is that the ammonium ions produced by the reaction can exchange with radionuclides sorbed to subsurface minerals, thereby enhancing the availability of the radionuclides for re-capture in a more stable solid phase (co-precipitation rather than adsorption)

Placental transfer of calcium and strontium and of their radionuclides

International Nuclear Information System (INIS)

Griessl, I.; Stieve, F.E.

1987-11-01

The first part of the report deals with the occurrence and the chemistry of strontium and its radioisotopes, and the second part discusses the calcium and the strontium metabolism in man. General information on the biology and physiology of the human skeleton is given in part 3, whereas part 4 again discusses the calcium and strontium metabolism in man, however with particular emphasis on the conditions during pregnancy and lactation. Part 5 presents an evaluation of the literature in this subject field, concentrating on results obtained with experimental animals such as cows, swine, dogs, guinea pigs, rats, and mice, and discusses the applicability of these findings to the conditions in man. An annex presents data on the yttrium metabolism in man and animal. (MG) [de

Cesium-137 inventories in undisturbed areas in different regions of Brazil

Energy Technology Data Exchange (ETDEWEB)

Andrello, Avacir C.; Appoloni, Carlos R., E-mail: acandrello@uel.b [Universidade Estadual de Londrina, PR (Brazil). Dept. de Fisica; Araujo, Ednaldo S. [EMBRAPA Agrobiologia, Seropedica, RJ (Brazil); Thomaz, Edivaldo L. [Universidade Estadual do Centro-Oeste - UNICENTRO, Guarapuava, PR (Brazil). Dept. de Geografia; Medeiros, Pedro Henrique Augusto [Universidade Federal do Ceara (UFC), Fortaleza, CE (Brazil). Dept. de Engenharia Agricola; Macedo, Iris L. [Universidade de Brasilia (UnB), DF (Brazil). Faculdade de Tecnologia. Dept. de Engenharia Civil e Ambiental

2009-07-01

Cesium-137 is an anthropogenic radionuclide introduced in the environment in the early of 1960s to the end of 1970s. The Cesium-137 has very used to assess soil redistribution in the landscape because this is very tight in the fine soil particles and its movement in the landscape is due to soil redistribution. To use Cesium-137 to assess soil redistribution is need to known the Cesium-137 inventory in an area that not has experimented soil erosion neither soil deposition. So, this work present Cesium-137 inventories in undisturbed areas in different regions of Brazil, from South to Northeast of Brazil. The inventories in these areas represent the variational deposition of Cesium-137 in the whole national territory of Brazil. The inventories of Cesium-137 varied from 200 +- 15 Bq.m{sup -2} for South region to 15 +- 2 Bq.m{sup -2} for Northeast region. Moreover, was verified that the Cesium- 137 inventories depend on latitude and altitude of the area. (author)

Cesium-137 inventories in undisturbed areas in different regions of Brazil

International Nuclear Information System (INIS)

Andrello, Avacir C.; Appoloni, Carlos R.; Thomaz, Edivaldo L.; Medeiros, Pedro Henrique Augusto; Macedo, Iris L.

2009-01-01

Cesium-137 is an anthropogenic radionuclide introduced in the environment in the early of 1960s to the end of 1970s. The Cesium-137 has very used to assess soil redistribution in the landscape because this is very tight in the fine soil particles and its movement in the landscape is due to soil redistribution. To use Cesium-137 to assess soil redistribution is need to known the Cesium-137 inventory in an area that not has experimented soil erosion neither soil deposition. So, this work present Cesium-137 inventories in undisturbed areas in different regions of Brazil, from South to Northeast of Brazil. The inventories in these areas represent the variational deposition of Cesium-137 in the whole national territory of Brazil. The inventories of Cesium-137 varied from 200 ± 15 Bq.m -2 for South region to 15 ± 2 Bq.m -2 for Northeast region. Moreover, was verified that the Cesium- 137 inventories depend on latitude and altitude of the area. (author)

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

International Nuclear Information System (INIS)

Saleh, H.M.

2012-01-01

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

Studies on the synthesis and characterization of cesium-containing iron phosphate glasses

Science.gov (United States)

Joseph, Kitheri; Govindan Kutty, K. V.; Chandramohan, P.; Vasudeva Rao, P. R.

2009-02-01

Isotopes of cesium and strontium can be utilized as radiation source for various industrial and medical applications after their separation from high level nuclear waste. However, these elements need to be immobilized in a suitable matrix. In the present work, a systematic approach has been made to immobilize inactive cesium into iron phosphate glass. Up to 36 mol% of Cs 2O has been loaded successfully without crystallization. The glass transition temperature of the cesium loaded glass was found to increase initially and then decrease as a function of Cs 2O content. Mössbauer studies show that the concentration of Fe 3+ ions in the cesium loaded glasses is >95%. Volatilization experiments at 1263 K show that the weight loss is >0.5% for a period of 4 h. The 36 mol% of Cs 2O loaded iron phosphate glass with high Fe 3+ content described in this paper is reported for the first time.

Sorption and chromatographic techniques for processing liquid waste of nuclear fuel cycle

International Nuclear Information System (INIS)

Gelis, V.M.; Milyutin, V.V.; Chuveleva, E.A.; Maslova, G.B.; Kudryavtseva, S.P.; Firsova, L.A.; Kozlitin, E.A.

2000-01-01

In the spent nuclear fuel processing procedures the significant quantity of high level liquid waste containing long-lived high toxic radionuclides of cesium, strontium, promethium, americium, curium, etc. is generated. Separation of those radionuclides from the waste not merely simplifies the further safe waste handling but also reduces the waste processing operation costs due to the market value of certain individual radionuclide preparations. Recovery and separation of high grade pure long-lived radionuclide preparations is frequently performed by means of chromatographic techniques. (authors)

Methodology for the U.S. Food and Drug Administration's radionuclides in foods program

International Nuclear Information System (INIS)

Baratta, E.J.

1998-01-01

The U.S. Food and Drug Administration (FDA) is responsible for the wholesomeness of the nation's food supply. The FDA modified its food monitoring program in January, 1973, to include radioactive isotopes. The methodology used to perform analyses on these food products are taken from the standard setting societies such as the AOAC International, American Society for Testing Materials and American Public Health Association Standard Methods. In addition, methods not tested by these societies are taken from the literature or from Department of Energy manuals such as the Health and Safety Laboratory and also from Environmental Protection Agency, Public Health Service, and Food and Agricultural Organization manuals. These include the methods for long-lived radionuclides such as tritium, strontium-90, cesium-137 and plutonium. Also, the short-lived radionuclides such as iodine-131, radiocesium, radiocerium and radioruthenium. In addition, they include the natural occurring radionuclides such as radium and uranium isotopes. The activity concentrations of gamma-emitters such as radiocesium, iodine-131 and radioruthenium are determined by gamma-ray spectrometry. This is done using intrinsic germanium detectors with the appropriate hardware and software. The alpha and 'pure' beta-emitters are determined by various radiochemical methods and techniques. The radiochemical methodology and equipment used in analyzing these radionuclides are described and discussed. Also, the methodology and equipment for the gamma-emitters are described in more detail in this paper. In addition, the limits of detection for the methods used will be discussed. (author)

Health and Safety Laboratory environmental quarterly, March 1--June 1, 1976. [Fallout, natural radioactivity, and lead in environmental samples from USA, India, and Taiwan during 1976

Energy Technology Data Exchange (ETDEWEB)

Hardy, E.P. Jr.

1976-07-01

This report presents current data from the HASL environmental programs, the Air Monitoring Section of the Bhabha Atomic Research Center in India, the Health Physics Section of the Institute of Nuclear Science in Taiwan and the Radiological and Environmental Research Division at Argonne National Laboratory. The initial section consists of interpretive reports and notes on the history of long-range fallout, cesium-137 in Bombay milk, natural and fallout radioactivity in Indian diet, reporting results of radioactivity measurements at near zero levels of sample activity and background, plutonium in soil northeast of the Nevada Test Site, radon levels at the Lloyd, NY regional station, strontium-90 in New York and San Francisco diets through 1975, plutonium-239, 240 in 1974 diet, up-dating stratospheric radionuclide inventories to July 1975 and a revised table of radionuclides. Subsequent sections include tabulations of radionuclide levels in stratospheric air; lead and radionuclides in surface air; strontium-90 in deposition, milk, diet, tap water, and human bone; cesium-137 in Chicago foods in April 1976; and environmental radioactivity surveys for nuclear power plants in North Taiwan. A bibliography of recent publications related to environmental studies is also presented.

Crystalline silicotitanates--new ion exchanger for selective removal of cesium and strontium from radwastes

International Nuclear Information System (INIS)

Dosch, R.G.; Klavetter, E.A.; Stephens, H.P.; Brown, N.E.; Anthony, R.G.

1996-08-01

A new class of inorganic ion exchange material called crystalline silicotitanates (CST) has been developed for radioactive waste treatment in a collaborative effort between Sandia National Laboratories and Texas A ampersand M University. The Sandia National Laboratories Laboratory Directed Research and Development program provided the initial funding for this effort and this report summarizes the rapid progress that was achieved. A wide range of compositions were synthesized, evaluated for cesium (Cs) removal efficiency, and a composition called TAM-5 was developed that exhibits high selectivity and affinity for Cs and strontium (Sr). Tests show it can remove parts per million concentrations of Cs + from highly alkaline, high-sodium, simulated radioactive waste solutions modeled after those at Hanford, Oak Ridge, and Savannah River. In experiments with solutions that simulate highly alkaline Hanford defense wastes, the crystalline silicotitanates exhibit distribution coefficients for Cs + of greater than 2,000 ml/g, and distribution coefficients greater than 10,000 ml/g for solutions adjusted to a pH between 1 and 10. In addition, the CSTs were found to exhibit distribution coefficients for Sr + greater than 100,000 ml/g and for plutonium of 2,000 ml/g from simulated Hanford waste. The CST crystal structure was determined and positions of individual atoms identified using x-ray and neutron diffraction. The structural information has permitted identification of the ion exchange sites and provided insights into the strong effect of pH on Cs ion exchange. Information on the synthesis, composition, and structure of CST is considered proprietary and is not discussed in this report

Cesium and strontium fractionation from HLW for thermal-stress reduction in a geologic repository

International Nuclear Information System (INIS)

McKee, R.W.

1983-02-01

Results are described for a study to assess the benefits and costs of fractionating the cesium and strontium components in commercial high-level waste (HLW) to a separate waste stream for the purpose of reducing geologic repository thermal stresses. System costs are developed for a broad range of conditions comparing the Cs/Sr fractionation concept with disposal of 10-year old vitrified HLW and vitrified HLW aged to achieve (through decay) the same heat output as the fractionated high-level waste (FHLW). All comparisons are based on a 50,000 metric ton equivalent (MTE) system. The FHLW and the Cs/Sr waste are both disposed of a vitrified waste but emplaced in separate areas of a basalt repository. The FHLW is emplaced in high-integrity packages at relatively high waste loading but low heat loading, while the Cs/Sr waste is emplaced in minimum integrity packages at relatively high heat loading. System cost comparisons are based on minimum cost combinations of canister diameter, waste concentration, and canister spacing in a basalt repository for each waste type. The effects on both long- and near-term safety considerations are also addressed. The major conclusion is that the Cs/Sr fractionation concept offers, potentially, a substantial total system cost advantage for HLW disposal if reduced HLW package temperatures in a basalt repository are desired. However, there is no cost advantage if currently designated maximum design temperatures are acceptable. Aging the HLW for 50 to 100 years can accomplish similar results at equivalent or loser costs

Factors affecting the leachability of caesium and strontium from cemented simulant evaporator wastes

International Nuclear Information System (INIS)

Lee, D.J.; Brown, D.J.

1981-08-01

Leach rates of stable cesium and strontium from a range of simulated evaporator waste/cement formulations have been determined. Important factors in plant operation are assessed for their effect on leach rates. Increasing the curing time and lowering the water/cement ratio has been shown to reduce leach rates by up to a factor of four. Incorporation of additives such as clays and supplementary cementatious materials can reduce leach rates by up to three orders magnitude, and coating the surface of the waste form with a neat cement grout can reduce the cesium leach rate by up to four orders of magnitude. The effects of permeability of the matrix and its cesium absorption capacity on the leach rates have been analysed qualitatively. (U.K.)

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

Energy Technology Data Exchange (ETDEWEB)

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

1988-01-01

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

The study of selective accumulation of radionuclides cesium 137, strontium 90 and cerium 144 in the cellular compartments of charophyta algae

International Nuclear Information System (INIS)

Marchyulenene, D.P.; Moteyunene, E.B.; Gudavichene, N.A.; Polikarpov, G.G.

1976-01-01

The study of the accumulation of 137 Cs, 90 Sr and 144 Ce in separate compartments of Chara algae (cellular wall, protoplasm, vacuoles), testifies to the fact that the entrance and accumulation level of the radionuclides depend upon the selective permeability of the cellular wall and plasmalemma, which is regulated both by the ratio of the chemical analogues of the radionuclides in the medium, and by the level of cellular metabolism [fr

The Usage of Natural Zeolites for the Adsorption of Radionuclides, particularly in emergency situations

International Nuclear Information System (INIS)

Reitbauer, Franz

2012-09-01

Specific natural zeolites have proven their capability to bind nuclear radiation During the last decades, numerous research work has proven the potential of natural zeolites to adsorb nuclear radiation through their cation exchange properties. Zeolites have been used successfully in Chernobyl, and are used in Fukushima and in nuclear waste repositories today. Within the various kinds of zeolites the special type clinoptilolite particularly binds 137-cesium as well as 90- strontium ions. Therefore zeolites with high contents of clinoptilolite are the first choice for this purpose. High contents of clinoptilolite can be defined as being above 90 %. Such zeolites are typically capable of binding some 2,50 meq/g of cesium ions and some 1,40 meq/g of strontium ions. (authors)

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

International Nuclear Information System (INIS)

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

1988-01-01

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

Radionuclide distributions and migration mechanisms at shallow land burial sites. Annual report of research investigations on the distribution, migration and containment of radionuclides at Maxey Flats, Kentucky

International Nuclear Information System (INIS)

Kirby, L.J.

1982-07-01

Subsurface waters at Maxey Flats are anoxic systems with high alkalinity and high concentrations of dissolved ferrous ion. Americium and cobalt in these trench waters are made more soluble by the presence of EDTA, while strontium and cesium are unaffected under the same conditions. EDTA is the major organic complexing component in waste trench 27 leachate, but other polar, water-soluble organics are also present. Evidence points to the migration of plutonium between waste trench 27 and inert atmosphere wells as an EDTA complex. Polar organic compounds may influence the migration of 90 Sr and 137 Cs. The primary pathway of water entry into the waste burial trenches is through the trench caps, but major increases in water level have occurred in an experimental trench by subsurface flow. The areal distribution of radionuclides at Maxey Flats has been influenced by surface runoff, deposition from the evaporator plume, subsurface flow and the actions of burrowing animals or deep-rooted trees. Vegetal and surface contamination on site and near site are quite low, and only 60 Co exceeds commonly observed fallout levels. Radionuclide concentrations in surface soil at Maxey Flats are comparable to concentrations resulting from normal fallout in other areas of high rainfall

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%

Environmental Measurements Laboratory. Environmental report, September 1, 1981-March 1, 1982

International Nuclear Information System (INIS)

Hardy, E.P. Jr.; Toonkel, L.E.

1982-01-01

This report presents current information from the EML environmental programs, the Radiological and Environmental Research Division at Argonne National Laboratory and the Los Alamos National Laboratory. Two reports on radionuclide data quality assurance are presented in the initial section: one dealing with fallout and biological samples and the other with filtered air samples. These are followed by a report on stratospheric tritium injection by the October 1980 Chinese test. The second section presents recent data from EML progams strontium-90 fallout, radionuclides and trace metals in surface air, radioactivity and trace gases sampled in the stratosphere by aircraft and balloons, strontium-90 in San Francisco and New York diet, milk, and tap water, and cesium-137 in tap water. The third section presents data from Argonne National Laboratory on cesium-137 in Chicago food and from Los Alamos National Laboratory on tritium in the stratosphere. A bibliography of recent publications related to environmental studies is presented. Each section has been abstracted and indexed individually for ERA/EDB

Speciation of native cations and added radionuclides in raw bovine milk. I. membraneless dialysis in aqueous biphasic systems

International Nuclear Information System (INIS)

Macasek, F.; Gerhart, P.; Malovikova, A.; Celkova, A.

1996-01-01

Partition of native sodium, potassium, magnesium, calcium and radioisotopes of cesium, strontium and europium was investigated in the aqueous liquid-liquid systems formed after agitation of fresh pasteurized skim bovine milk with 4% w/w water solution of pectin of various degree of esterification (60-93%). The partition of the ions in the 'membraneless dialysis' was described by Donnan equilibria and ion-exchange in the macro-and microheterogenous systems and, within uncertainty of results, does not depend on the degree of esterification. Strong negative non-ideality of Sr and Eu in milk phase is attributed to binding with proteins, casein particles in particular, and complexation with low molecular ligands. Separation factor α = D(Sr)/D(Ca) is 0.70 ±0.06, in favor of strontium concentration in pectin phase. While>96% of cesium is diffusible to pectin phase, only 43-56% (depending on physico-chemical model of dialysis) of strontium behaves in that way, and in original milk phase the percent of strontium cationic from may be as low as 13%. (author). 24 refs., 8 figs., 4 tabs

Uranium and Cesium sorption to bentonite colloids in high salinity and carbonate-rich environments: Implications for radionuclide transport

Science.gov (United States)

Tran, E. L.; Teutsch, N.; Klein-BenDavid, O.; Weisbrod, N.

2017-12-01

When radionuclides are leaked into the subsurface due to engineered waste disposal container failure, the ultimate barrier to migration of radionuclides into local aquifers is sorption to the surrounding rock matrix and sediments, which often includes a bentonite backfill. The extent of this sorption is dependent on pH, ionic strength, surface area availability, radionuclide concentration, surface mineral composition, and solution chemistry. Colloidal-sized bentonite particles eroded from the backfill have been shown to facilitate the transport of radionuclides sorbed to them away from their source. Thus, sorption of radionuclides such as uranium and cesium to bentonite surfaces can be both a mobilization or retardation factor. Though numerous studies have been conducted to-date on sorption of radionuclides under low ionic strength and carbonate-poor conditions, there has been little research conducted on the behavior of radionuclides in high salinities and carbonate rich conditions typical of aquifers in the vicinity of some potential nuclear repositories. This study attempts to characterize the sorption properties of U(VI) and Cs to bentonite colloids under these conditions using controlled batch experiments. Results indicated that U(VI) undergoes little to no sorption to bentonite colloids in a high-salinity (TDS= 9000 mg/L) artificial groundwater. This lack of sorption was attributed to the formation of CaUO2(CO3)22- and Ca2UO2(CO3)3 aqueous ions which stabilize the UO22+ ions in solution. In contrast, Cs exhibited greater sorption, the extent to which was influenced greatly by the matrix water's ionic strength and the colloid concentration used. Surprisingly, when both U and Cs were together, the presence of U(VI) in solution decreased Cs sorption, possibly due to the formation of stabilizing CaUO2(CO3)22- anions. The implications of this research are that rather than undergoing colloid-facilitated transport, U(VI) is expected to migrate similarly to a

Dynamics of cesium and strontium radionuclides in macrolichens

International Nuclear Information System (INIS)

Martin, J.; Martin, L.; Nifontova, M.

1994-04-01

To investigate 137C s and 90S r fallout and migration in the system plant-soil macrolichens belonging to the Cetraria and Cladina genera were used. Systematic field collections were made in the Rumpo Botanical Sanctuary on Vormsi Island (West-Estonia n Archipelago Biosphere Reserve, WEABR) and in the Koljaku Reserve (Lahemaa National Park, LNP) during 1986-90. (author). 2 figs

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

Energy Technology Data Exchange (ETDEWEB)

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

2012-01-15

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

Willow wood production on radionuclide polluted areas

Directory of Open Access Journals (Sweden)

Rodkin Oleg I.

2010-01-01

Full Text Available ABSTRACT: One of the key environmental problems in Belarus is effective use of agricultural lands contaminated by radionuclide due to the Chernobyl disaster. The alternative method to traditional agricultural crops is fast growing willow cultivation. It is possible to use biomass of willow as renewable energy source. The goal of our investigation was the estimation of environmental aspects of willow wood production on polluted areas. The field study experiments (2007-2010 were conducted at Krichev district of Mogilev region in eastern Belarus. This region characterized by high level of Cs-137 contamination as well as high level of heavy metals pollution. In the first stage of experiments, the concentration of cesium-137 in different parts of willow biomass had been measured and transfer factor calculated. The measuring had been done for leaves, roots, and wood. To control cesium-137 accumulation in willow biomass we apply different types (nitrogen N, phosphorus P and potassium K and dose of fertilizer. The experiments show that potassium mineral fertilizer is the key factor for radionuclide accumulation control. The optimal dose of potassium is 90 kg per hectare. On the base of experimental results the model of cesium-137 accumulation in the wood for a 21 year has been developed. In accordance with calculation to the end of willow cultivation (21 year concentration of cesium-137 in wood will not be higher than permitted even with the level of cesium-137 contamination in the soil 1480 kBq/m2 (maximum 140 kqB/m2 with permitted level for firewood is 740 Bq/kg.. The concentration of cesium-137 in the roots increases gradually and get maximum in 21 year (3000 kqB/m2. Our results confirm that in the sum about 0.8 million hectares of radionuclide polluted arable lands partly excluded from agricultural practice in Belarus could be used for willow biomass production.

separation of strontium and cesium from ternary and quaternary lithium chloride-potassium chloride salts via melt crystallization

Directory of Open Access Journals (Sweden)

Ammon N. Williams

2015-12-01

Full Text Available Separation of cesium chloride (CsCl and strontium chloride (SrCl2 from the lithium chloride-potassium chloride (LiCl-KCl salt was studied using a melt crystallization process similar to the reverse vertical Bridgeman growth technique. A ternary SrCl2-LiCl-KCl salt was explored at similar growth rates (1.8–5 mm/h and compared with CsCl ternary results to identify similarities. Quaternary experiments were also conducted and compared with the ternary cases to identify trends and possible limitations to the separations process. In the ternary case, as much as 68% of the total salt could be recycled per batch process. In the quaternary experiments, separation of Cs and Sr was nearly identical at the slower rates; however, as the growth rate increased, SrCl2 separated more easily than CsCl. The quaternary results show less separation and rate dependence than in both ternary cases. As an estimated result, only 51% of the total salt could be recycled per batch. Furthermore, two models have been explored to further understand the growth process and separation. A comparison of the experimental and modeling results reveals that the nonmixed model fits reasonably well with the ternary and quaternary data sets. A dimensional analysis was performed and a correlation was identified to semipredict the segregation coefficient.

Separation of strontium and cesium from ternary and quaternary lithium chloride-potassium chloride salts via melt crystallization

Energy Technology Data Exchange (ETDEWEB)

Williams, Ammon n.; Pack, Michael [Dept. of Mechanical and Nuclear Engineering, Virginia Commonwealth University, Richmond (United States); Phongikaroon, Spathorn [Dept. of Chemical and Materials Engineering and Nuclear Engineering Program, University of Idaho, Idaho Falls (United States)

2015-12-15

Separation of cesium chloride (CsCl) and strontium chloride (SrCl{sub 2}) from the lithium chloride-potassium chloride (LiCl-KCl) salt was studied using a melt crystallization process similar to the reverse vertical Bridgeman growth technique. A ternary SrCl2-LiCl-KCl salt was explored at similar growth rates (1.8-5 mm/h) and compared with CsCl ternary results to identify similarities. Quaternary experiments were also conducted and compared with the ternary cases to identify trends and possible limitations to the separations process. In the ternary case, as much as 68% of the total salt could be recycled per batch process. In the quaternary experiments, separation of Cs and Sr was nearly identical at the slower rates; however, as the growth rate increased, SrCl{sub 2} separated more easily than CsCl. The quaternary results show less separation and rate dependence than in both ternary cases. As an estimated result, only 51% of the total salt could be recycled per batch. Furthermore, two models have been explored to further understand the growth process and separation. A comparison of the experimental and modeling results reveals that the nonmixed model fits reasonably well with the ternary and quaternary data sets. A dimensional analysis was performed and a correlation was identified to semipredict the segregation coefficient.

Spatial distribution of radionuclides in soil around a coal-fired power plant: lead 210, polonium 210, radium 226, thorium 232, kalium 40 emitted with the fly ash and cesium 137 from the worldwide weapon testing fallout

Energy Technology Data Exchange (ETDEWEB)

Bunzl, K.; Hoetzl, H.; Rosner, G.; Winkler, R.

1984-09-01

To determine the effect of airborne emissions of radionuclides from coal-fired power plants on the environment, the concentrations of the most important radionuclides were measured in soil samples from the local environments (0.4-5.2 km) as well as in fly ash. The spatial distribution of the radionuclides in the soil did not indicate any significantly increased concentrations in the area downwind of the plant compared to other areas; the ratios lead 210/radium 226 and polonium 210/radium 226 were within the range observed for unaffected soils. The emissions from the plant, though present, are obviously too small to significantly change the natural local distribution pattern of the radionuclides in the soil. A highly significant correlation between potassium 40 and thorium 232 was observed which was independent of the different types of soils found in this area. The concentration of cesium 137 in topsoil, which is the result of worldwide fallout from nuclear weapons testing, varied at some places even within a small distance (approx. 2 km) by up to one order of magnitude. Furthermore, it was observed that the concentration of cesium 137 in soils from cropland was on average a factor of 2 less than in those from grassland. This variability has to be considered in planning monitoring programs around nuclear power plants, which may also release this radionuclide. (A.V.)

Radionuclide transfer from forage plants into milk

Energy Technology Data Exchange (ETDEWEB)

Heeschen, W

1987-06-09

There is a lot of information regarding the transfer of radionuclides (iodine, caesium, strontium) which allows the transfer factor being calculated with high certainty. The transfer coefficients (forage-)plant/milk laid down in Paragraph 45 of the Radiation Protection Ordinance (Strahlenschutzverordnung) amount to 1.0x10/sup -2/ for iodine-131, 1.2x10/sup -2/ for caesium-137 and 2.0x10/sup -3/ for strontium-90. More recent calculated factors are markedly lower at the average. During milk processing, the greatest amount of radionuclides gets access to the whey or into the permeate after ultrafiltration of whey. In butter and cheese only minute amounts of caesium can be expected.

Solvent extraction of radionuclides from aqueous tank waste

International Nuclear Information System (INIS)

Bonnesen, P.; Sachleben, R.; Moyer, B.

1996-01-01

The purpose of this task is to develop an efficient solvent-extraction and stripping process to remove the fission products 99 Tc, 90 Sr, and 137 Cs from alkaline tank waste, such as those stored at Hanford and Oak Ridge. As such, this task expands on FY 1995's successful development of a solvent-extraction and stripping process for technetium separation from alkaline tank-waste solutions. This process now includes the capability of removing both technetium and strontium simultaneously. In this form, the process has been named SRTALK and will be developed further in this program as a prelude to developing a system capable of removing technetium, strontium, and cesium

Study of radionuclide mobilization and drag mechanisms during hydric erosion

International Nuclear Information System (INIS)

Claval, D.

2000-11-01

Water erosion is responsible for the spread of radioactive contaminant through the agricultural catchment area, its redistribution, possible concentration and export towards the aquatic environment, and also for the post-accident contamination of plants through splash of water. The aim of this work is to offer or improve values for the proper functioning of codes of calculation destined for operational use. These codes of calculation do not take into account the spread of contamination after its release. Modelling these transfers requires initially the acquisition of the capacity for spread of the contamination at decimetric scale. To this end, we have reproduced deposits of dry and wet radioactive aerosols of cesium and strontium at various stages in the hydric and structural history of the soil in function of a range of degrees of slope of the terrain. The exchanges of cesium and strontium at the water-soil interface have been quantified by means of millimetric experimentation in batches, during which the various phases of the mobilization of soil particles have been reproduced on calibrated blocks of aggregates. At the end of this study, it was apparent that the cesium migrates horizontally at an appreciably faster rate and in greater proportions than the strontium that fixes little on the particles and infiltrates into the first centimeter of the soil. The key parameter to take into account for the model would appear to be the initial humidity of the soil. In addition, the migration of the cesium appears to be particularly sensitive to the development of sedimentary crusts. Where the soil is dry or slaking crusted at the time of contamination, the first run-off are very efficient carriers of contamination. The sedimentary crust favours the exportation of cesium and strontium by preventing its infiltration, while at the same time trapping part of the contamination on its immobile particles. On steep slopes, the structure of the sedimentary crusts is less

Background concentrations of selected radionuclides, organic compounds, and chemical constituents in ground water in the vicinity of the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Orr, B.R.; Cecil, L.D.; Knobel, L.L.

1991-01-01

Background concentrations of radionuclides, organic compounds, and other chemical constituents in water in the Snake River Plain aquifer in Idaho were estimated from groundwater sample analyses. Detectable concentrations of transuranic elements should not be present in water from the Snake River Plain aquifer. Background concentrations of tritium generally range from 75 to 150 pCi/L. Strontium-90 and iodine-129 concentrations generally are 0 and from 0.05 pCi/L, respectively. At the INEL, comparison of the mean and median concentrations of tritium, strontium-90, and iodine-129 indicates that operations locally have affected concentrations in groundwater. Gross alpha-particle and beta-particle radioactivity in water from the Snake River Plain aquifer ranges from 0 to 5 pCi/L and 0 to 8 pCi/L, respectively. Background gamma radiation in groundwater is attributed to cesium-137, cobalt-60, and potassium-40. Cesium-137 and cobalt-60 concentrations generally are zero in groundwater at the INEL. Naturally occurring concentrations of potassium-40 probably are about 300 pCi/L. Background concentrations of organic compounds in water from the Snake River Plain aquifer generally are less than 0.2 microg/L. Background arsenic and chromium concentrations both are about 2 to 3 microg/L. Barium concentrations are from about 50 to about 70 microg/L. Lead and mercury concentrations generally are less than 5 microg/L and 0.1 microg/L, respectively. Cadmium, selenium, and silver concentrations generally are less than 1 microg/L. Nitrate concentrations range from 0 to about 1.4 mg/L

Development of zirconium/magnesium phosphate composites for immobilization of fission products

International Nuclear Information System (INIS)

Singh, D.; Tlustochowicz, M.; Wagh, A.S.

1999-01-01

Novel chemically bonded phosphate ceramics have been investigated for the capture and stabilization of volatile fission-product radionuclides. The authors have used low-temperature processing to fabricate zirconium phosphate and zirconium/magnesium phosphate composites. A zirconium/magnesium phosphate composite has been developed and shown to stabilize ash waste that has been contaminated with a radioactive surrogate of the 137 Cs and 90 Sr species. Excellent retention of cesium in the phosphate matrix system was observed in both short- and long-term leaching tests. The retention factor determined by the USEPA Toxicity Characteristic Leaching Procedure was one order of magnitude better for cesium that for strontium. The effective diffusivity, at room temperature, for cesium and strontium in the waste forms was estimated to be as low as 2.4 x 10 -13 and 1.2 x 10 -11 m 2 /s, respectively. This behavior was attributed to the capture of cesium in the layered zirconium phosphate structure via an intercalation ion-exchange reaction, followed by microencapsulation. However, strontium is believed to be precipitated out in its phosphate form and subsequently microencapsulated in the phosphate ceramic. The performance of these final waste forms, as indicated by the compression strength and the durability in aqueous environments, satisfies the regulatory criteria

Main investigation results on the forest radioecology in the Kyshtym and Chernobyl accident zones

International Nuclear Information System (INIS)

Tikhomirov, F.A.; Shcheglov, A.I.

1994-01-01

As a result of the long-term studies of radionuclide migration in forest ecosystems in zones of radioactive contamination after the Kyshtym and Chernobyl accidents, the following trends were revealed: (1) High retention capacity of stand canopy with respect to radioactive fallout. This leads to high doses absorbed by apical and leaf meristems, β-radiation giving the main part of the dose; (2) Fast self-decontamination of crowns during the growth period and relatively slow decontamination in the phase of physiological rest, regardless of amount of atmospheric precipitation. The rate of crown decontamination determines the value and duration of radiation stress on woody plants; (3) Accumulation not less than 95% of the total radionuclide amount in the forest litter 1-2 years after the cessation of radioactive fallout; (4) Relatively slow migration of strontium and cesium radionuclides along the forest soil profile; (5) High capacity of the forest when serving as a biogeochemical barrier to the routes of horizontal and vertical radionuclide migration and export out of the zone of initial contamination, including migration into the river water; (6) Considerable difference between strontium and cesium when migrating in forest soils and in the soil-plant system; (7) Broad variations in transfer factors for uptake of cesium-137 from soil into forest plants depending on the plant species and soil type. The primary radiobiological effects connected with irradiation of organisms are considered and secondary disturbances due to changes of ecological bonds between the components of irradiated forest ecosystem are discussed

Distribution of plutonium and cesium in alluvial soils of the Los Alamos environs

International Nuclear Information System (INIS)

Nyhan, J.W.; Miera, F.R. Jr.; Peters, R.J.

1976-01-01

The alluvial soils of three liquid waste disposal areas at Los Alamos were sampled to determine plutonium and cesium distributional relationships and correlations with soil physical-chemical properties. Radionuclide concentrations were determined for soil samples as a function of soil depth and distance from the waste outfall. The cesium-plutonium data were correlated with levels of organic carbon, carbonates, exchangeable and water-soluble cations, pH, cation exchange capacity, bulk density, surface area and geometric particle size of these soils. The distribution patterns of soil plutonium and cesium were also compared to the waste use history of the three study areas

Biological effects of cesium-137 injected in beagle dogs of different ages

International Nuclear Information System (INIS)

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

1995-01-01

The toxicity of cesium-137 ( 137 Cs) in the Beagle dog was investigated at the Argonne National Laboratory (ANL) as part of a program to evaluate the biological effects of internally deposited radionuclides. The toxicity and health effects of 137 Cs are important to understand because 137 Cs is produced in large amounts in light-water nuclear reactors. Large quantities of cesium radioisotopes have entered the human food chain as a result of atmospheric nuclear weapons test, and additional cesium radioisotopes were released during the Chernobyl accident. Although the final analyses are not complete, three findings are significant: older dogs dies significantly earlier than juvenile and young adult dogs; greater occurrence of sarcomas in the cesium-137 injected dogs; the major nonneoplastic effect in dogs surviving beyond 52 d appears to be testicular atrophy

The uptake of radionuclides by plants

International Nuclear Information System (INIS)

Cawse, P.A.; Turner, G.S.

1982-02-01

A review of the literature, since 1970, on the research into the uptake of radionuclides by plants, with references to earlier soil and plant studies on the fate of nuclear weapons fallout. Experimental data on the uptake of plutonium isotopes, americium 241, cesium 137, radium 226, curium 244 and neptunium 237 and details of the chemical form of the radionuclide, soil type and plant growth period are tabulated. (U.K.)

Cesium 137 in oils and plants from Guatemala

International Nuclear Information System (INIS)

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

1993-01-01

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

Radionuclide concentrations in vegetation at radioactive-waste disposal Area G during the 1994 growing season

International Nuclear Information System (INIS)

Fresquez, P.R.; Biggs, J.B.; Bennett, K.D.

1995-01-01

Overstory (pinon pine) and understory (grass and forb) vegetation samples were collected within and around selected points at Area G-a low-level radioactive solid-waste disposal facility at Los Alamos National Laboratory-for the analysis of tritium ( 3 H), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), cesium ( 137 Cs), americium ( 241 Am), and total uranium. In general, most vegetation samples collected within and around Area G contained radionuclide levels in higher concentrations than vegetation collected from background areas. Tritium, in particular, was detected as high as 5,800 pCi/mL in overstory vegetation collected outside the fence just west of the tritium shafts; this suggests that tritium is migrating from this waste repository through subsurface pathways. Also, understory vegetation collected north of the transuranic (TRU) pads (outside the fence of Area G) contained the highest values of 90 Sr, 238 Pu, 239 Pu, 137 Cs, and 241 Am, and may be a result of surface holding, storage, or disposal activities

Assessment of hydrologic transport of radionuclides from the Rulison Underground Nuclear Test Site, Colorado

International Nuclear Information System (INIS)

Earman, S.; Chapman, J.; Andricevic, R.

1996-09-01

The U.S. Department of Energy (DOE) is operating an environmental restoration program to characterize, remediate, and close non-Nevada Test Site locations that were used for nuclear testing. Evaluation of radionuclide transport by groundwater from these sites is an important part of the preliminary risk analysis. These evaluations are undertaken to allow prioritization of the test areas in terms of risk, provide a quantitative basis for discussions with regulators and the public about future work at the sites, and provide a framework for assessing data needs to be filled by site characterization. The Rulison site in west-central Colorado was the location of an underground detonation of a 40-kiloton nuclear device in 1969. The test took place 2,568 m below ground surface in the Mesaverde Formation. Though located below the regional water table, none of the bedrock formations at the site yielded water during hydraulic tests, indicating extremely low permeability conditions. The scenario evaluated was the migration of radionuclides from the blast-created cavity through the Mesaverde Formation. Transport calculations were performed using the solute flux method, with input based on the limited data available for the site. Model results suggest that radionuclides from the test are contained entirely within the area currently administered by DOE. The transport calculations are most sensitive to changes in the mean groundwater velocity and the correlation scale of hydraulic conductivity, with transport of strontium and cesium also sensitive to the sorption coefficient

Migration of strontium, cesium, and europium from poly(butyl acrylate)/phosphate/composites prepared using gamma radiation

Energy Technology Data Exchange (ETDEWEB)

Alhassanieh, O., E-mail: cscientific@aec.org.s [Nuclear and Radiochemistry Division, Chemistry Department, Atomic Energy Commission of Syria, Damascus, P.O. Box 6091 (Syrian Arab Republic); Ajji, Z. [Polymer Technology Division, Radiation Technology Department, Atomic Energy Commission of Syria, Damascus, P.O. Box 6091 (Syrian Arab Republic); Alkourdi, H.; Haloum, D. [Nuclear and Radiochemistry Division, Chemistry Department, Atomic Energy Commission of Syria, Damascus, P.O. Box 6091 (Syrian Arab Republic)

2011-02-15

Composites based on natural phosphate powder and the monomer N-butyl acrylate have been prepared by means of gamma irradiation. The conversion of polymerization was followed up with respect to the irradiation dose using thermogravimetric analyzer (TGA). A total polymerization conversion was achieved by exposure of the samples to a dose of 10 kGy. A thermomechanical analyzer (TMA) was used to locate the region of the glass transition temperatures (T{sub g}) using the mode with alternative variable force; the mode with constant force was used to determine the T{sub g} of the pure polymer and the composite prepared at the same irradiation dose. The T{sub g} of the pure poly(butyl acrylate) is -51.41 {sup o}C, and the T{sub g} of poly(butyl acrylate)/phosphate/composites is -46.54 {sup o}C. The distribution of {sup 137}Cs, {sup 152}Eu, and {sup 85}Sr in a solid-aqueous system, a composite of phosphate-polybutyl acrylate in contact with groundwater, was investigated using {gamma}-spectrometry. The effect of contact time, pH, and the concentration of concurrent elements (Na, Ca, and La) were studied. The results were compared with earlier results with phosphate alone in the solid phase. The ability of the produced composites to keep the studied radioisotopes in the solid phase is much higher than mineral phosphate. This improvement is more remarkable by strontium and cesium than europium, due to its high element ratio in the solid phase in phosphate experiments.

Identification of efficient chelating acids responsible for Cesium, Strontium and Barium complexes solubilization in mixed wastes

International Nuclear Information System (INIS)

Borai, E.H.

2007-01-01

The present paper is focused to characterize the available multi dentate ligand species and their metal ion complexes of cesium (Cs), strontium (Sr) and barium (Ba) formed with the parent chelators, complexing agents and its fragment products in mixed waste filtrate. The developed separation programs of different ligands by different mobile phases were based on the decrease of the effective charge of the anionic species in a differentiated way hence, the retention times on the stationary phases (AS-4A and AS-12A) are changed. Ion chromatographic (IC) analysis of the metal complexes showed that the carboxylic acids that are responsible for solubilizing Cs, Sr and Ba in the waste filtrate are NTA, Citrate and PDCA, respectively. Therefore, the predominant metal complexes in the filtrate at high ph are Cs (I)-NTA, Sr (IT)-Citrate and Ba (IT)-PDCA. Identification of the metal ion complexes responsible for solubilizing Cs, Sr and Ba was applied on the fresh and aged waste filtrates, to monitor their chemical behavior, which leads to increased control of the waste treatment process. Although, concentration measurements of both fresh and aged filtrates confirmed that the degradation process has occurred mainly due to a harsh chemical environment, the concentration of Cs(I), Sr(II) and Ba(II) increased slightly in the aged filterate compared with the fresh filtrate. This is due to the decomposition and/or degradation of their metal complexes and hence leads to free metal ion species in the filtrate. These observations indicate that the organic content of mixed waste filtrate is dynamic and need continuous analytical monitoring

Results of HWVP transuranic process waste treatment laboratory and pilot-scale filtration tests using specially ground zeolite

International Nuclear Information System (INIS)

Eakin, D.E.

1996-03-01

Process waste streams from the Hanford Waste Vitrification Plant (HWVP) may require treatment for cesium, strontium, and transuranic (TRU) element removal in order to meet criteria for incorporation in grout. The approach planned for cesium and strontium removal is ion exchange using a zeolite exchanger followed by filtration. Filtration using a pneumatic hydropulse filter is planned to remove TRU elements which are associated with process solids and to also remove zeolite bearing the cesium and strontium. The solids removed during filtration are recycled to the melter feed system to be incorporated into the HWVP glass product. Fluor Daniel, Inc., the architect-engineering firm for HWVP, recommended a Pneumatic Hydropulse (PHP) filter manufactured by Mott Metallurgical Corporation for use in the HWVP. The primary waste streams considered for application of zeolite contact and filtration are melter off-gas condensate from the submerged bed scrubber (SBS), and equipment decontamination solutions from the Decontamination Waste Treatment Tank (DWTT). Other waste streams could be treated depending on TRU element and radionuclide content. Laboratory and pilot-scale filtration tests were conducted to provide a preliminary assessment of the adequacy of the recommended filter for application to HWVP waste treatment

Chernobyl radioactivity impacts and remediation of forest ecosystems

Energy Technology Data Exchange (ETDEWEB)

Rennie, C.D.; Baweja, A.S.

1992-01-01

This report gives an overview of the results of the Chernobyl nuclear accident, the impacts of strontium, cesium, and plutonium on forestry ecosystems, the toxicity of the radionuclides, remediation techniques such as upgrading the soils with the addition of potassium and calcium, and other possible measures for remediation, based primarily on the Bikini Atoll model.

Radioecological investigations of the Bilibino Nuclear Power Station area

Energy Technology Data Exchange (ETDEWEB)

Emelyanova, L.; Neretin, L. [Moscow State Univ. (Russian Federation). Geographical Faculty]|[Russian Academy of Sciences, Moscow (Russian Federation). P.P. Shirshov Inst. of Oceanology

1995-12-31

The landscape structure of the territory and the current radioactive state of ecosystems in the vicinity of Bilibino Nuclear Power Station (Western Chukotka Peninsula) within the area of its potential influence on the environment were studied in 1989--1990. Accumulation of strontium-90 and cesium-137 radionuclides in several key biological members of the ecosystems has been analyzed. Maximal weighted content of cesium-137 was revealed in mountain pine cones (Pinus pumila) -- 9,200 Bq/kg.d.w., cowberry fruits have demonstrated considerable contamination by strontium and cesium isotopes. The purification of first two components of food chain ``lichen-reindeer-man`` was pointed out in the investigated area. Besides the chemical characteristics, visual biological anomalies of biocomponents nearby the Bilibino NPS ecosystems are observed. On the basis of field radioecological investigations and future work, programs were developed for the conditions of the Bilibino Nuclear Power Station area. This experience could be applied to the researches of radioactive contamination in ecosystems of other northern territories.

Cesium migration experiments in different media

International Nuclear Information System (INIS)

Tello, C.C.O. de

1992-01-01

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

Biological effects of cesium-137 injected in beagle dogs of different ages

Energy Technology Data Exchange (ETDEWEB)

Nikula, K.J.; Muggenburg, B.A.; Griffith, W.C. [and others

1995-12-01

The toxicity of cesium-137 ({sup 137}Cs) in the Beagle dog was investigated at the Argonne National Laboratory (ANL) as part of a program to evaluate the biological effects of internally deposited radionuclides. The toxicity and health effects of {sup 137}Cs are important to understand because {sup 137}Cs is produced in large amounts in light-water nuclear reactors. Large quantities of cesium radioisotopes have entered the human food chain as a result of atmospheric nuclear weapons test, and additional cesium radioisotopes were released during the Chernobyl accident. Although the final analyses are not complete, three findings are significant: older dogs dies significantly earlier than juvenile and young adult dogs; greater occurrence of sarcomas in the cesium-137 injected dogs; the major nonneoplastic effect in dogs surviving beyond 52 d appears to be testicular atrophy.

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

Use of cesium-137 methodology in the evaluation of superficial erosive processes

International Nuclear Information System (INIS)

Andrello, Avacir Casanova; Appoloni, Carlos Roberto; Guimaraes, Maria de Fatima; Nascimento Filho, Virgilio Franco do

2003-01-01

Superficial erosion is one of the main soil degradation agents and erosion rates estimations for different edaphic climate conditions for the conventional models, as USLE and RUSLE, are expensive and time-consuming. The use of cesium- 137 anthropogenic radionuclide is a new methodology that has been much studied and its application in the erosion soil evaluation has grown in countries as USA, UK, Australia and others. A brief narration of this methodology is being presented, as the development of the equations utilized for the erosion rates quantification through the cesium- 137 measurements. Two watersheds studied in Brazil have shown that the cesium- 137 methodology was practicable and coherent with the survey in field for applications in erosion studies. (author)

Impact of a chronic ingestion of radionuclides on cholesterol metabolism in the rat: example of depleted uranium and cesium 137

International Nuclear Information System (INIS)

Racine, Radjini

2009-01-01

Depleted uranium (DU) and cesium-137 ( 137 Cs) are radionuclides spread in the environment due to industrial activities, incidents or accidents. This pollution sets a risk of human exposure to low levels of radiations through contaminated foodstuff. The impact of a chronic ingestion of DU or 137 Cs on cholesterol metabolism in the liver and the brain has been studied. Indeed, cholesterol is crucial in physiology, being a component of cell membranes and a precursor to numerous molecules (bile acids...). Disruption of its metabolism is associated to many pathologies such as atherosclerosis or Alzheimer disease. Rats daily ingested a low level of DU or 137 Cs over 9 months. For each radionuclide, a reference model (rats contaminated since adulthood) and a more sensitive model (hypercholesterolemic or contaminated since fetal life) were studied. The effects mainly consist of changes in gene expression or enzymatic activity of various actors of cholesterol metabolism. DU mainly affects one catabolism enzyme in both models, as well as membrane transporters and regulation factors. 137 Cs mainly affects the storage enzyme in both models as well as catabolism enzymes, apolipoproteins, and regulation factors. No change in the plasma profile or in the tissue concentration of cholesterol (hepatic/cerebral) is recorded, whatever the model and the radionuclide. Thus, a chronic internal contamination with DU or 137 Cs induces molecular modifications in cholesterol metabolism in the rat, without affecting its homeostasis or the general health status in all of our experimental models. (author)

Electrically switched cesium ion exchange

International Nuclear Information System (INIS)

Lilga, M.A.; Orth, R.J.; Sukamto, J.P.H.; Schwartz, D.T.; Haight, S.M.; Genders, J.D.

1997-04-01

Electrically Switched Ion Exchange (ESIX) is a separation technology being developed as an alternative to conventional ion exchange for removing radionuclides from high-level waste. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution are controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. A case study for the KE Basin on the Hanford Site was conducted based on the results of the development testing. Engineering design baseline parameters for film deposition, film regeneration, cesium loading, and cesium elution were used for developing a conceptual system. Order of magnitude cost estimates were developed to compare with conventional ion exchange. This case study demonstrated that KE Basin wastewater could be processed continuously with minimal secondary waste and reduced associated disposal costs, as well as lower capital and labor expenditures

Fast concentration of dissolved forms of cesium radioisotopes from large seawater samples

International Nuclear Information System (INIS)

Jan Kamenik; Henrieta Dulaiova; Ferdinand Sebesta; Kamila St'astna; Czech Technical University, Prague

2013-01-01

The method developed for cesium concentration from large freshwater samples was tested and adapted for analysis of cesium radionuclides in seawater. Concentration of dissolved forms of cesium in large seawater samples (about 100 L) was performed using composite absorbers AMP-PAN and KNiFC-PAN with ammonium molybdophosphate and potassium–nickel hexacyanoferrate(II) as active components, respectively, and polyacrylonitrile as a binding polymer. A specially designed chromatography column with bed volume (BV) 25 mL allowed fast flow rates of seawater (up to 1,200 BV h -1 ). The recovery yields were determined by ICP-MS analysis of stable cesium added to seawater sample. Both absorbers proved usability for cesium concentration from large seawater samples. KNiFC-PAN material was slightly more effective in cesium concentration from acidified seawater (recovery yield around 93 % for 700 BV h -1 ). This material showed similar efficiency in cesium concentration also from natural seawater. The activity concentrations of 137 Cs determined in seawater from the central Pacific Ocean were 1.5 ± 0.1 and 1.4 ± 0.1 Bq m -3 for an offshore (January 2012) and a coastal (February 2012) locality, respectively, 134 Cs activities were below detection limit ( -3 ). (author)

Radioactive substances

International Nuclear Information System (INIS)

Butler, G.C.; Hyslop, C.

1980-01-01

The purpose of this chapter is to show how to assess the detriment resulting from the release of radioactive materials to the environment. The minimum information required for the assessments is given for seven radionuclides of interest from the point of view of environmental contamination. The seven radionuclides are tritium, krypton-85, strontium-90, iodine-131, cesium-137, radium-226 and plutonium-239. Information is given on the radiation doses and the radiation effects on man due to these radioisotopes. (AN)

Task summary: Hot demonstration of proposed commercial nuclide removal technology

International Nuclear Information System (INIS)

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

1995-11-01

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

Cesium-137. Environment. Man

International Nuclear Information System (INIS)

Moiseev, A.A.

1985-01-01

Analysis of all main sourses of cerium-137 formation and intake into the external medium is given. Special attention is paid to the estimation of possible influence of rapidly developing nuclear power industry on contamination of the external medium by the radionuclide. Levels of contamination of the external medium by cerium-137, main regularities of its migration through food chains, levels of its intake and accumulation in population's organisms in USSR and its separate regions, are considered. Great attention is paid to the control methods of external environmental contamination by cesium-137 and to its measurements in human body

Application of dicyclohexyl-18-crown-6 to selective extraction of radioactive strontium from waters

International Nuclear Information System (INIS)

Yakshin, V.V.; Myasoedov, B.F.; Vilkova, O.M.; Tuzova, A.M.; Fedorova, A.T.; Rodionova, I.M.

1989-01-01

Influence of various factors on strontium extraction in the system nitric acid-dicyclohexyl-18-crown-6 was studied to develop the technique for determining 89 Sr and 90 Sr content in natural waters and aqueous salt solutions. Conditions for selective strontium extraction from complex salt systems containing Ba, Cs, Ru, Ce and other radionuclides were found. It is shown that coefficient of strontium distribution is sufficiently higher, as compared to coefficients of Cs, Ru, Ce distribution. Extraction performance under chosen conditions enables to elevate sufficiently the distribution coefficient of these substances. The scheme of radiochemical analysis is given. Strontium content in natural waters and salt solutions was determined with the use of described radiochemical method

Development of a technique of the rapid analysis for forecasting of possible radionuclides accumulation in the harvest of agricultural crops

International Nuclear Information System (INIS)

Yadgarov, Kh.T.; Pugachev, V.V.; Kim, A.A.

2005-01-01

One of the main ways of pollution of plants by radionuclides is the receipt of radionuclides in plants from ground through root system and direct uptake of radionuclides by underground parts of plants. Therefore receipt of radioisotopes in rhizosphere of plants plays the main role in radionuclides accumulation in the plants. For plants cultivation in conditions of radioactive pollution of region it is necessary to estimate the value of possible radionuclides accumulation in a harvest of plants. Such forecasts are necessary at planning of growing of agricultural crops for the food, forage or technical purposes depending on a degree of their pollution by radionuclides. We investigated correlation between the content of strontium - 90 in plants in early phases of their development (20 days time) and in a harvest of plants at a soil way of radionuclide receipt. Our results of study of dependence of strontium - 90 accumulation in a harvest from its content in 20 days time sprouts show, that with reduction of the content of strontium - 90 in 20 days time sprouts, its quantity in a harvest of agriculture cultures is reduced. The correlation analysis of the received data has confirmed positive connection between accumulation of radionuclide in young and adult plants. So, correlation coefficients for a cotton, wheat and barley are 0,89; 0,91 and 0,91 correspondingly. Thus, the direct connection between the contents of strontium - 90 in plants of young age and its accumulation in a harvest of adult plants is established. It enables to predict pollution of' harvest by strontium - 90 under its contents in young plants. Using the received data, with the help of the least- squares method, we have calculated coefficients of the regression equation of a kind: y = a + bx, Where: y - the predicted contents of radionuclide in the harvest; x - the content of radionuclide in 20 days time sprouts; a, b - the empirical coefficients. Rather good coincidence of theoretical calculations and

Comparison or organic and inorganic ion exchange materials for removal of cesium and strontium from Hanford waste

Energy Technology Data Exchange (ETDEWEB)

Brown, G.N.; Carson, K.J.; DesChane, J.R.; Elovich, R.J. [Pacific Northwest National Lab., Richland, WA (United States)

1997-10-01

This work is part of an ESP-CP task to develop and evaluate high-capacity, selective, solid extractants for the uptake of cesium, strontium, and technetium (Cs, Sr, and Tc) from nuclear wastes. Pacific Northwest National Laboratory (PNNL) staff, in collaboration with researchers from industry, academia, and national laboratories are investigating these and other novel and commercial ion exchangers for use in nuclear waste remediation of groundwater, HLW, and LLW. Since FY 1995, experimental work at PNNL has focused on small-scale batch distribution (K{sub d}) testing of numerous solid sorbents with actual and simulated Hanford wastes, chemical and radiolytic stability of various organic ion exchanger resins, bench-scale column ion exchange testing in actual and simulated Complexant Concentrate (CC) and Neutralized Current Acid Waste (NCAW), and Tc and Sr removal from groundwater and LLW. In addition, PNNL has continued to support various site demonstrations at the Idaho National Engineering Laboratory, Savannah River Site, West Valley Nuclear Services, Hanford N-Springs, and Hanford N-Basin using technologies developed by their industrial partners. This summary will focus on batch distribution results from the actual waste tests. The data collected in these development and testing tasks provide a rational basis for the selection and direct comparison of various ion exchange materials in simulated and actual HLW, LLW, and groundwater. In addition, prediction of large-scale column loading performance for the materials tested is possible using smaller volumes of actual waste solution. The method maximizes information while minimizing experimental expense, time, and laboratory and process wastes.

Distribution coefficients (Kd's) for use in risk assessment models of the Kara Sea.

Science.gov (United States)

Carroll, J; Boisson, F; Teyssie, J L; King, S E; Krosshavn, M; Carroll, M L; Fowler, S W; Povinec, P P; Baxter, M S

1999-07-01

As a prerequisite for most evaluations of radionuclide transport pathways in marine systems, it is necessary to obtain basic information on the sorption potential of contaminants onto particulate matter. Kd values for use in modeling radionuclide dispersion in the Kara Sea have been determined as part of several international programs addressing the problem of radioactive debris residing in Arctic Seas. Field and laboratory Kd experiments were conducted for the following radionuclides associated with nuclear waste: americium, europium, plutonium, cobalt, cesium and strontium. Emphasis has been placed on two regions in the Kara Sea: (i) the Novaya Zemlya Trough (NZT) and (ii) the mixing zones of the Ob and Yenisey Rivers (RMZ). Short-term batch Kd experiments were performed at-sea on ambient water column samples and on samples prepared both at-sea and in the laboratory by mixing filtered bottom water with small amounts of surficial bottom sediments (particle concentrations in samples = 1-30 mg/l). Within both regions, Kd values for individual radionuclides vary over two to three orders of magnitude. The relative particle affinities for radionuclides in the two regions are americium approximately equal to europium > plutonium > cobalt > cesium > strontium. The values determined in this study agree with minimum values given in the IAEA Technical Report [IAEA, 1985. Sediment Kd's and Concentration Factors for Radionuclides in the Marine Environment. Technical Report No. 247. International Atomic Energy Agency, Vienna.]. Given the importance of Kd's in assessments of critical transport pathways for radionuclide contaminants, we recommend that Kd ranges of values for specific elements rather than single mean values be incorporated into model simulations of radionuclide dispersion.

Tracing Fukushima Radionuclides in the Northern Hemisphere -An Overview

Science.gov (United States)

Thakur, Punam; Ballard, Sally; Nelson, Roger

2013-04-01

A massive 9.0 earthquake and ensuing tsunami struck the northern coast of the Honshu-island, Japan on March 11, 2011 and severely damaged the electric system of the Fukushima- Daiichi Nuclear Power Plant (NPP). The structural damage to the plant disabled the reactor's cooling systems. Subsequent fires, a hydrogen explosion and possible partial core meltdowns released radioactive fission products into the atmosphere. The atmospheric release from the crippled Fukushima NPP started on March 12, 2011 with a maximum release phase from March 14 to 17. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases xenon (Xe-133) and krypton (Kr-85); iodine (I-131,I-132); cesium (Cs-134,Cs-136,Cs-137); and tellurium (Te-132). The non-volatile radionuclides such as isotopes of strontium and plutonium are believed to have remained largely inside the reactor, although there is evidence of plutonium release into the environment. Global air monitoring across the northern hemisphere was increased following the first reports of atmospheric releases. According to the source term, declared by the Nuclear and Industrial Safety Agency (NISA) of Japan), approximately 160 PBq (1 PBq (Peta Becquerel = 10^15 Bq)) of I-131 and 15 PBq of Cs-137 (or 770 PBq "iodine-131 equivalent"), were released into the atmosphere. The 770 PBq figure is about 15% of the Chernobyl release of 5200 PBq of "iodine-131 equivalent". For the assessment of contamination after the accident and to track the transport time of the contaminated air mass released from the Fukushima NPP across the globe, several model calculations were performed by various research groups. All model calculations suggested long-range transport of radionuclides from the damaged Fukushima NPP towards the North American Continent to Europe and to Central Asia. As a result, an elevated level of Fukushima radionuclides were detected in air, rain, milk, and vegetation samples across the northern

The glass block site radionuclide migration study

International Nuclear Information System (INIS)

Killey, R.W.D.; Champ, D.R.

1990-01-01

In 1960 25 nepheline syenite glass blocks containing 14 TBq of mixed fission products in 50 kg of glass were placed below the water table in a shallow sand aquifer at Chalk River Laboratories. Experimental studies undertaken at the site since 1960 have included detailed mapping of the plume of 90 Sr in 1963, 1966 and 1971. Mathematical modeling studies have employed the radiostrontium plume data in determining the split between ion exchange and chemisorption of 90 Sr, and in obtaining reaction rate data for chemisorption. The distribution of 137 Cs on downgradient soils was mapped in 1963 and 1979. An extended plume of low-level 137 Cs contamination observed in the 1979 study prompted an investigation of the role of particulate materials in radionuclide transport. IN 1983, large volume groundwater sampling and separation of cationic, anionic, and neutral dissolved species, as well as particulates, detected anionic and cationic dissolved europium isotopes (154 and 155), and again encountered particulate 137 Cs. A variety of investigations of cesium and strontium sorption have provided a data base on sediment mineralogy, particle surface features, and information on sorption sites and processes. The year 1990 saw the inauguration of a three-year program to update investigations of radionuclide release, transport, and sorption at the glass block site. The first stage of the program has been a detailed definition and simulation of the hydrogeologic setting. Plume mapping and aqueous speciation studies are in progress. This paper summarizes past investigations, reviews the status of the current program, and discusses components of future studies, including investigations of sediment sorption mechanisms. (Author) (17 refs., 8 figs.)

Process for recovering cesium from cesium alum

International Nuclear Information System (INIS)

Mein, P.G.

1984-01-01

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

A survey of radioactive fallout data in Alaska

International Nuclear Information System (INIS)

DePhillips, M.P.

1995-01-01

Considerable attention has been directed by the scientific community to assessing the levels and fate of radionuclides in Arctic ecosystems. The following text and tables present available data and discussion of radionuclide fallout in Alaska. A literature search of 23 on-line databases (Table 1) using Alaska, Strontium (Sr), Cesium (Cs), Plutonium (Pu) and Radionuclide as constraint terms responded with 177 possible citations. After eliminating duplicate citations, 31 articles were available: 17 were relevant to the subject matter; the remainder addressed geologic issues. All of the cited literature addressed 137 Cs, 90 Sr and 239,240 Pu as a result of radionuclide fallout from nuclear testing or accidental release

Radionuclide contaminant analysis of rodents at a waste burial site, Los Alamos National Laboratory

International Nuclear Information System (INIS)

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

1996-01-01

Small mammals were sampled at two waste burial sites (Sites 1 and 2) at Area G, TA-54, and a control site outside Area G (Site 3) to identify radionuclides that are present within surface and subsurface soils at waste burial sites, to compare the amount of radionuclide uptake by small mammals at waste burial sites to a control site, and to identify the primary mode of contamination to small mammals, either through surface contact or ingestion/inhalation. Three composite samples of at least five animals per sample were collected at each site. Pelts and carcasses of each animal were separated and analyzed independently. Samples were analyzed for americium ( 241 Am), strontium ( 90 Sr), plutonium ( 238 Pu and 239 Pu), total uranium (U), and examined by gamma spectroscopy (including cesium [ 137 Cs]). Significantly higher (parametric t-test at p = 0.05) levels of total U, 241 Am, 238 Pu, and potassium ( 40 K) were detected in pelts as compared to the carcasses of small mammals at TA-54. Concentrations of other measured radionuclides in carcasses were nearly equal to or exceeded the mean concentrations in the pelts. The results show higher concentrations in pelts compared to carcasses which is similar to what has been found at waste burial/contaminated sites outside of Los Alamos National Laboratory. Site 1 had significantly higher (alpha = 0.05, P = 0.0095) total U concentrations in carcasses than Sites 2 and 3. Site 2 had significantly higher (alpha = 0.05, P = 0.0195) 239 Pu concentrations in carcasses than either Site 1 or Site 3

Tracing cohesive sediment transportation at river mouths around Tokyo, Japan by Cesium originated from Fukushima Daiichi Power Plant

Science.gov (United States)

koibuchi, Y.

2012-12-01

Sediment transport at river mouths, which consists of suspended-load and bed-load, has not been fully understood, since bed-load transport of cohesive sand is difficult to observe. Especially, the impact of sediment transport on the total amount of fine-grained cohesive sediment has not been elucidated. Cesium-134 and cesium-137 were spread from the Fukushima Daiichi Nuclear Power Plant (FDNPP) after the earthquake of March 11 of 2011, and attached to the fine-grained sand on the land. The contaminated sand flowed into the river mouths through the rivers possibly due to the complex physical processes in estuarine areas. To evaluate the fine-grained sediment transport around Tokyo and Tokyo Bay, field observations were carried out utilizing radionuclide originated from FDNPP as an effective tracer. The cohesive sediment transport at three different river mouths around Tokyo was successfully quantified. The cohesive sediment transport deposited in the estuary was found to be greatly dependent on the land use, geometry, river discharge and salinity. In addition,the transport driven by the rainfall was minute, and its behavior was quite different from suspended solids. Although further field observations of radionuclide are necessary, it is clear that fine-grained sediment in the bay from rivers already settled on the river mouth by aggregation. The settled sand will not move even in rainfall events. Consequently, the transport of radionuclide to the Pacific Ocean may not occur.; Cesium distribution around Tokyo Bay ; Cesium Concentration in Edogawa river

Study of methods for removing strontium, plutonium, and ruthenium from Savannah River Plant waste supernate

International Nuclear Information System (INIS)

Wiley, J.R.

1976-06-01

As a part of long-term waste management studies at the Savannah River Laboratory, tests were made to study removal of strontium, plutonium, and ruthenium from simulated and actual waste supernates. Plutonium was sorbed by Duolite ARC-359 ion exchange resin, the same resin that is used to remove cesium from waste supernate. Strontium was removed from supernate by sorption on a chelating resin Chelex 100, or by precipitation as Sr 3 (PO 4 ) 2 . Activities of 137 Cs, 90 Sr, and 238-241 Pu remaining in processed waste supernate should be 1-10 nanocuries of each element per gram of salt. Of the methods that were tested, none was adequate for plant-scale removal of ruthenium

Radioactive uptake by plants

Energy Technology Data Exchange (ETDEWEB)

Horak, O

1986-01-01

The fundamentals of radionuclide uptake by plants, both by leaves and roots are presented. Iodine, cesium, strontium and ruthenium are considered and a table of the measured concentrations in several agricultural plants shortly after the Chernobyl accident is presented. Another table gives the Cs and Sr transfer factors soil plants for some plants. By using them estimates of future burden can be obtained.

Cesium-137

International Nuclear Information System (INIS)

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

2014-06-01

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

Determination of strontium-90 in the environmental samples at PINSTECH

International Nuclear Information System (INIS)

Perveen, N.; Aziz, A.

1979-01-01

Strontium-90 a bone seeking radionuclide and a long lived beta emitter is one of the toxic radionuclides detected in the environment arising mainly from the fall out from nuclear detonations. Its concentration in various environmental media such as air, precipitation, surface water, vegetables and other items of diet was measured. This report describes the method of collection, treatment and radiochemical analyses of environmental samples for the determination of Sr-90. The levels of Sr-90 concentration in these media are also recorded. (authors)

Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

Energy Technology Data Exchange (ETDEWEB)

Washington, A. L. II; Peters, T. B.; Fink, S. D.

2013-02-25

Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. {sup 237}Np and {sup 243}Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU.

The effect of organic amendment on mobility of cesium in tropical soils - The effect of organic amendment on sorption mechanisms for cesium and cobalt in tropical soils

Energy Technology Data Exchange (ETDEWEB)

Wasserman, M.A.V.; Santos-Oliveira, R. [Instituto de Engenharia nuclear/CNEN. Rua Helio de Almeida, 75. Cidade Universitaria - Ilha do Fundao, Rio de Janeiro, RJ. CEP 21941-906 (Brazil); Garcia, R.J.L.; Ferreira, A.C.M.; Rochedo, E.R.R.; Sobrinho, G.A.N. [Instituto de Radioprotecao e Dosimetria/CNEN. Av. Salvador Allende s /no. Rio de Janeiro, RJ. CEP: 22780-160 (Brazil); Perez, D.V. [Centro Nacional de Pesquisa de Solos/EMBRAPA. R. Jardim Botanico, 1024.Rio de Janeiro, RJ, CEP: 22460-000 (Brazil); Wasserman, J.C. [dUFF Network of Environment and Sustainable Development (REMADS-UFF), University Federal Fluminense, Niteroi, RJ (Brazil)

2014-07-01

This work aimed to investigate the mechanisms involved in the sorption of {sup 137}Cs and {sup 60}Co as a function of the physico-chemical properties of some types of Brazilian soils and the changes on the behavior of these radionuclides due to changes in soil properties promoted by organic amendment. The experimental study was conducted in a controlled area, where pots containing different types of soils (Ferralsol, Nitisol and Histosol) and different doses of organic amendment (no amendment; 2 kg.m{sup -2} and 4 kg.m{sup -2}) were spiked with {sup 137}Cs and {sup 60}Co. The organic amendment used in this experiment was obtained in the Unit of Compost of the Organic Material of Pinheiral (RJ, Brazil), where the compost is made up from the leaves swept from the streets of the Pinheiral city. The mobility of these radionuclides in the soil was assessed through sequential chemical extraction and desorption studies as a function of pH. The bioavailability was evaluated through the effective absorption of radionuclide by root crops (Raphanus sativus, L). This study evidenced that the organic amendment plays an important role in the desorption processes of cobalt and cesium, reducing desorption of both nuclides beneath higher organic amendment dose. This behavior was observed in acid conditions as well in alkaline. However extreme acid conditions may mobilize both radionuclides, although cobalt mobility was shown to be more sensitive to low pH than cesium. (authors)

An overview of BORIS: Bioavailability of Radionuclides in Soils

International Nuclear Information System (INIS)

Tamponnet, C.; Martin-Garin, A.; Gonze, M.-A.; Parekh, N.; Vallejo, R.; Sauras-Yera, T.; Casadesus, J.; Plassard, C.; Staunton, S.; Norden, M.; Avila, R.; Shaw, G.

2008-01-01

The ability to predict the consequences of an accidental release of radionuclides relies mainly on the level of understanding of the mechanisms involved in radionuclide interactions with different components of agricultural and natural ecosystems and their formalisation into predictive models. Numerous studies and databases on contaminated agricultural and natural areas have been obtained, but their use to enhance our prediction ability has been largely limited by their unresolved variability. Such variability seems to stem from incomplete knowledge about radionuclide interactions with the soil matrix, soil moisture, and biological elements in the soil and additional pollutants, which may be found in such soils. In the 5th European Framework Programme entitled Bioavailability of Radionuclides in Soils (BORIS), we investigated the role of the abiotic (soil components and soil structure) and biological elements (organic compounds, plants, mycorrhiza, and microbes) in radionuclide sorption/desorption in soils and radionuclide uptake/release by plants. Because of the importance of their radioisotopes, the bioavailability of three elements, caesium, strontium, and technetium has been followed. The role of one additional non-radioactive pollutant (copper) has been scrutinised in some cases. Role of microorganisms (e.g., K d for caesium and strontium in organic soils is much greater in the presence of microorganisms than in their absence), plant physiology (e.g., changes in plant physiology affect radionuclide uptake by plants), and the presence of mycorrhizal fungi (e.g., interferes with the uptake of radionuclides by plants) have been demonstrated. Knowledge acquired from these experiments has been incorporated into two mechanistic models CHEMFAST and BIORUR, specifically modelling radionuclide sorption/desorption from soil matrices and radionuclide uptake by/release from plants. These mechanistic models have been incorporated into an assessment model to enhance its

An overview of BORIS: Bioavailability of Radionuclides in Soils

Energy Technology Data Exchange (ETDEWEB)

Tamponnet, C. [Institute of Radioprotection and Nuclear Safety, DEI/SECRE, CADARACHE, B.P. 1, 13108 Saint-Paul-lez-Durance, Cedex (France)], E-mail: christian.tamponnet@irsn.fr; Martin-Garin, A.; Gonze, M.-A. [Institute of Radioprotection and Nuclear Safety, DEI/SECRE, CADARACHE, B.P. 1, 13108 Saint-Paul-lez-Durance, Cedex (France); Parekh, N. [Center for Ecology and Hydrology, Lancaster Environment Centre, Lancaster University, Lancaster LA1 4YQ (United Kingdom); Vallejo, R.; Sauras-Yera, T.; Casadesus, J. [Department of Plant Biology, University of Barcelona, 08028 Barcelona (Spain); Plassard, C.; Staunton, S. [INRA, UMR Rhizosphere and Symbiosis, Place Viala, 34060 Montpellier (France); Norden, M. [Swedish Radiation Protection Institute, 171 16 Stockholm (Sweden); Avila, R. [Facilia AB, Valsgaerdevaegen 12, 168 53 Bromma, Stockholm (Sweden); Shaw, G. [Division of Agricultural and Environmental Sciences University Park, Nottingham NG7 2RD (United Kingdom)

2008-05-15

The ability to predict the consequences of an accidental release of radionuclides relies mainly on the level of understanding of the mechanisms involved in radionuclide interactions with different components of agricultural and natural ecosystems and their formalisation into predictive models. Numerous studies and databases on contaminated agricultural and natural areas have been obtained, but their use to enhance our prediction ability has been largely limited by their unresolved variability. Such variability seems to stem from incomplete knowledge about radionuclide interactions with the soil matrix, soil moisture, and biological elements in the soil and additional pollutants, which may be found in such soils. In the 5th European Framework Programme entitled Bioavailability of Radionuclides in Soils (BORIS), we investigated the role of the abiotic (soil components and soil structure) and biological elements (organic compounds, plants, mycorrhiza, and microbes) in radionuclide sorption/desorption in soils and radionuclide uptake/release by plants. Because of the importance of their radioisotopes, the bioavailability of three elements, caesium, strontium, and technetium has been followed. The role of one additional non-radioactive pollutant (copper) has been scrutinised in some cases. Role of microorganisms (e.g., K{sub d} for caesium and strontium in organic soils is much greater in the presence of microorganisms than in their absence), plant physiology (e.g., changes in plant physiology affect radionuclide uptake by plants), and the presence of mycorrhizal fungi (e.g., interferes with the uptake of radionuclides by plants) have been demonstrated. Knowledge acquired from these experiments has been incorporated into two mechanistic models CHEMFAST and BIORUR, specifically modelling radionuclide sorption/desorption from soil matrices and radionuclide uptake by/release from plants. These mechanistic models have been incorporated into an assessment model to enhance

Spectroscopy and Laser-SNMS on stable and radioactive strontium

Energy Technology Data Exchange (ETDEWEB)

Bosco, Hauke; Walther, Clemens [Institut fuer Radiooekologie und Strahlenschutz, Leibniz Universitaet Hannover (Germany); Franzmann, Michael [Institut fuer Radiooekologie und Strahlenschutz, Leibniz Universitaet Hannover (Germany); Institut fuer Physik, Johannes Gutenberg Universitaet Mainz (Germany); Kron, Tobias; Wendt, Klaus [Institut fuer Physik, Johannes Gutenberg Universitaet Mainz (Germany)

2016-07-01

Nuclear accidents as experienced e.g. in Chernobyl or Fukushima and nuclear weapon tests released considerable activity levels and a variety of medium to long-lived radionuclides into the environment. Strontium-90 appears as a significant share of the fission products in spent nuclear fuel and correspondingly in any possible release. Due to its chemical properties it is subject to long range transport through the environment and can cause considerable dose to man when entering the food chain. Correspondingly, the investigation of speciation and migration channels is of major relevance. A radioanalytical approach is severely hampered by the low beta energy of the strontium-90 decay and the need to separate strontium-90 from the secular equilibrated daughter yttrium-90. Hence, application of a mass spectrometric method without chemical separation of the elements is a promising alternative for low-level investigation of strontium-90. Application of the new Laser-SNMS system at IRS Hannover could well suit those needs. It applies three Ti:Sa lasers for resonant ionization of neutral atoms produced by primary ion sputtering in a SIMS together with a time-of-flight mass analysis which provides high spatial resolution. The analytical measurements are preceded by spectroscopic studies on the level structure of strontium to develop a most efficient ionization scheme.

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%

Decontamination of radionuclides on construction materials

International Nuclear Information System (INIS)

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

2013-01-01

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

Investigation of Various LiCl Waste Salt Purification Technologies

International Nuclear Information System (INIS)

Yung-Zun Cho; Hee-Chul Yang; Han-Soo Lee; In-Tae Kim

2008-01-01

Various purification research of LiCl waste molten salt generated from electroreduction process were tested. The purification of the LiCl waste salt very important in a various aspects, where the purification means separation of cesium and strontium form LiCl salt melts. In this study, for the separation of cesium and strontium from LiCl salt melts, precipitant agent addition techniques such as sulfate and carbonate addition method and, as a new attempt, zone freezing technique for concentration of cesium and strontium elements was investigated. As a results of this research, only strontium was carbonated by reaction with Li 2 CO 3 (cesium did not react with Li 2 CO 3 ). In case of sulfate addition method, both cesium and strontium were converted into their sulfate that is Cs 2 S 2 O 6 and SrSO 4 and maximum sulfate efficiency of cesium and strontium were about 72% and 95%, respectively. Cesium and strontium involved in LiCl molten salt could be concentrated in the molten salt by using zone freezing method. (authors)

Effect of selected foodstuffs on strontium 89 metabolism in rats

International Nuclear Information System (INIS)

Keslev, D.; Jotov, M.

1975-01-01

The influence of a variety of food products used in human nutrition on strontium-89 cumulation in rat organism is studied. To this end the animals were fed for a week with meat, beans, maize, white and brown bread, cabbage, milk or potatoes prepared so as to be edible by man. Then for additional 15 days the animals were fed the same diet + a daily oral dose of 2 μCi strontium-89. On the 16th day radionuclide activity in the thigh bone was measured. Beans was the food product exerting optimal limiting effect on strontium deposition (reduction factor (RF) 17), milk and ranking next (RF 13, resp. 6.5). All other products showed approximately equal efforts (RF 1.4 - 1.8). The different calcium content of each of these food products is responsible for their different effectiveness. Together with the discrimination which the living organism displays in the presence of calcium, other constituents of the food products which form complexes with strontium and prevent its deposition in the bones are equally essential. (Ch.K.)

Fate of cesium, strontium, iodine and some transuranium elements in farm animals

International Nuclear Information System (INIS)

Mueller-Brunecker, G.

1982-11-01

Domestic animals may take up Cs, I, Sr and the most important transuranium elements by contaminated food, inhalation and cutaneous resorption. The resorption takes place (with differing percentage distribution) via gastrointestinal tract, lungs, skin and with wounds via injured skin areas. With chronical exposure and after resorption of radionuclides a distribution balance develops in the blood; with a single incorporation the activity concentration in the blood one increases and decreases again. According to the affinity of the radionuclide its major part is transported to one particular organ or tissue system, where depending on the degree of specific activity the most different damages may be provoked. Considerable amounts of the radionuclide quantities are discharged with urine, feces or milk. The amount discharged into the milk is of particular radioecologic interest. The portion of the radionuclides, which is discharged into the muscles and the milk of animals for slaughter is indicated by transmission factors, which have to be subjected to revision. The transmission factors given in literature are classified according to the animal species and discussed in the corresponding chapters. (orig./MG) [de

Producing new radionuclides for medicine

International Nuclear Information System (INIS)

Michaut, C.

2009-01-01

The Arronax cyclotron, a new particle accelerator dedicated to the production of radionuclides for medicine and research has been commissioned in Nantes (France). Because of its unique features: an energy of 70 MeV and an intensity of 750 μA, Arronax will produce radionuclides that can not be produce in present cyclotrons. Among others it will produce Strontium-82 and Germanium-68 that are the precursors for Rubidium-82 and Gallium-68 respectively. 20 per cent of the research works will be dedicated to other domains like radioactive wastes, the radiation biological damage and the radiation damage on electronic devices. (A.C.)

Review of the sorption of radionuclides on the bedrock of Haestholmen and on construction and backfill materials of a final repository for reactor wastes

International Nuclear Information System (INIS)

Kulmala, S.; Hakanen, M.

1992-10-01

Imatran Voima Oy (IVO) has plans to build a final repository for reactor wastes in the bedrock of the nuclear power plant site at Haestholmen, Loviisa. This report summarizes the sorption studies of radionuclides in Finnish bedrock performed at the Department of Radiochemistry, University of Helsinki. The values of mass distribution ratios, K d , and surface distribution ratios, K a ; of carbon, calsium, Zirconium, niobium, cobalt, nickel, strontium, cesium, uranium, plutonium, americium, thorium, chlorine, iodine and technetium are surveyed. Special attention is paid to the sorption data for construction and backfill materials of rector waste repository and the bedrock of Haestholmen. Safety assessment of a repository includes calculations of migration of the waste element in construction materials and backfill in the nearfield and in bedrock. Retardation by sorption of waste nuclides compared to groundwater flow is described by using distribution ratios between solid materials and water. (orig.)

Biogeochemical cycling of radionuclides in the environment

International Nuclear Information System (INIS)

Livens, F.R.

1990-01-01

The biogeochemical cycling of radionuclides with other components such as nutrients around ecosystems is discussed. In particular the behaviour of cesium in freshwater ecosystems since the Chernobyl accident and the behaviour of technetium in the form of pertechnetate anions, TcO 4 , in marine ecosystems is considered. (UK)

Sensitivity and uncertainty analysis of the PATHWAY radionuclide transport model

International Nuclear Information System (INIS)

Otis, M.D.

1983-01-01

Procedures were developed for the uncertainty and sensitivity analysis of a dynamic model of radionuclide transport through human food chains. Uncertainty in model predictions was estimated by propagation of parameter uncertainties using a Monte Carlo simulation technique. Sensitivity of model predictions to individual parameters was investigated using the partial correlation coefficient of each parameter with model output. Random values produced for the uncertainty analysis were used in the correlation analysis for sensitivity. These procedures were applied to the PATHWAY model which predicts concentrations of radionuclides in foods grown in Nevada and Utah and exposed to fallout during the period of atmospheric nuclear weapons testing in Nevada. Concentrations and time-integrated concentrations of iodine-131, cesium-136, and cesium-137 in milk and other foods were investigated. 9 figs., 13 tabs

Applicability of sodium alginate in decorporation therapy of strontium radioisotopes in human being; Aplicabilidade do alginato de sodio na terapia de decorporacao de radioisotopos de estroncio em seres humanos

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Aloisio Cordilha

1999-10-01

The increasing release of fission products from nuclear weapon tests in the environment has been rising the levels of radioactive contamination of food chains caused by the fall-out of these elements. In cases of accidental exposure, human subjects could be submitted to an internal contamination, which is likely to include several radionuclides. Special concern must be given, however, to the radioactive isotopes of strontium, cesium and iodine, along with the highly radio toxic transuranium elements like cerium. It was found that sodium alginate, a polyelectrolyte commonly used in food industry and obtained from brown algae (Phaeophyceae), provides the selective suppression of absorption of radioactive strontium presented in the ingested food material with no disturbance of the electrolyte balance nor undesirable side effects, even for a long term treatment. Moreover, these patterns were maintained when alginate was associated to other decontamination additives, specially those related to the other radioisotopes mentioned above, as, in this case, losses in the effectiveness, mutual interference or adverse health effects were not detected. These conclusions ground the discussion about the present trend in the usual choice of EDTA/DTPA complex therapy rather than of alginate therapy for medical assistance of radiocontaminated patients, although they corroborate the efficiency and usefulness of alginate salts in situations related to extensive intakes of strontium radioisotopes alone or associated to other fission products. The purpose of the present work is to make a general review of the alginate therapy as well as to discuss its present and future therapeutic importance from the scientific and institutional points of view. (author)

Colloid stable sorbents for cesium removal: Preparation and application of latex particles functionalized with transition metals ferrocyanides

Energy Technology Data Exchange (ETDEWEB)

Avramenko, Valentin [Institute of Chemistry, Far Eastern Branch, Russian Academy of Sciences, 159 ave 100-letiya Vladivostoka, Vladivostok 690022 (Russian Federation); Bratskaya, Svetlana, E-mail: sbratska@ich.dvo.ru [Institute of Chemistry, Far Eastern Branch, Russian Academy of Sciences, 159 ave 100-letiya Vladivostoka, Vladivostok 690022 (Russian Federation); Zheleznov, Veniamin; Sheveleva, Irina [Institute of Chemistry, Far Eastern Branch, Russian Academy of Sciences, 159 ave 100-letiya Vladivostoka, Vladivostok 690022 (Russian Federation); Voitenko, Oleg [Far Eastern Federal University, Laboratory of Electron Microscopy and Image Processing, 27, Oktyabr' skaya Street, Vladivostok 690950 (Russian Federation); Sergienko, Valentin [Institute of Chemistry, Far Eastern Branch, Russian Academy of Sciences, 159 ave 100-letiya Vladivostoka, Vladivostok 690022 (Russian Federation)

2011-02-28

In this paper we suggest a principally new approach to preparation of colloid stable selective sorbents for cesium uptake using immobilization of transition metals (cobalt, nickel, and copper) ferrocyanides in nanosized carboxylic latex emulsions. The effects of ferrocyanide composition, pH, and media salinity on the sorption properties of the colloid stable sorbents toward cesium ions were studied in solutions containing up to 200 g/L of sodium nitrate or potassium chloride. The sorption capacities of the colloid sorbents based on mixed potassium/transition metals ferrocyanides were in the range 1.3-1.5 mol Cs/mol ferrocyanide with the highest value found for the copper ferrocyanide. It was shown that the obtained colloid-stable sorbents were capable to penetrate through bulk materials without filtration that made them applicable for decontamination of solids, e.g. soils, zeolites, spent ion-exchange resins contaminated with cesium radionuclides. After decontamination of liquid or solid radioactive wastes the colloid-stable sorbents can be easily separated from solutions by precipitation with cationic flocculants providing localization of radionuclides in a small volume of the precipitates formed.

Selective extraction of cesium: from compound to process

International Nuclear Information System (INIS)

Simon, N.; Eymard, S.; Tournois, B.; Dozol, J.F.

2000-01-01

Under the French law of 30 December 1991 on nuclear waste management, research is conducted to recover long-lived fission products from high-level radioactive effluents generated by spent fuel reprocessing, in order to destroy them by transmutation or encapsulate them in specific matrices. Cesium extraction with mono and bis-crown calix(4)arenes (Frame 1) is a candidate for process development. These extractants remove cesium from highly acidic or basic pH media even with high salinity. A real raffinate was treated in 1994 in a hot cell to extract cesium with a calix-crown extractant. The success of this one batch experiment confirmed the feasibility of cesium decontamination from high-level liquid waste. It was then decided to develop a process flowchart to extract cesium selectively from high-level raffinate, to be included in the general scheme of long-lived radionuclide partitioning. It was accordingly decided to develop a process based on liquid-liquid extraction and hence optimize a calixarene/diluent solvent according to: - hydraulic properties: density, viscosity, interfacial tension, - chemical criteria: sufficient cesium extraction (depending on the diluent), kinetics, third phase elimination... New mono-crown-calixarenes branched with long aliphatic groups (Frame 2) were designed to be soluble in aliphatic diluents. To prevent third phase formation associated with nitric acid extraction, the addition of modifiers (alcohol, phosphate and amide) in the organic phase was tested (Frame 3). Table 1 shows examples of calixarene/diluent systems suitable for a process flowchart, and Figure 2 provides data on cesium extraction with these new systems. Alongside these improvements, a system based on a modified 1,3-di(n-octyl-oxy)2,4-calix[4]arene crown and a modified diluent was also developed, considering a mixed TPH/NPHE system as the diluent, where TPH (hydrogenated tetra propylene) is a common aliphatic industrial solvent and NPHE is nitrophenyl

Optimization of operational conditions in continuous electrodeionization method for maximizing Strontium and Cesium removal from aqueous solutions using artificial neural network

Energy Technology Data Exchange (ETDEWEB)

Zahakifar, Fazel; Keshtkar, Alireza; Nazemi, Ehsan; Zaheri, Adib [Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of)

2017-09-01

Strontium (Sr) and Cesium (Cs) are two important nuclear fission products which are present in the radioactive wastewater resulting from nuclear power plants. They should be treated by considering environmental and economic aspects. In this study, artificial neural network (ANN) was implemented to evaluate the optimal experimental conditions in continuous electrodeionization method in order to achieve the highest removal percentage of Sr and Ce from aqueous solutions. Three control factors at three levels were tested in experiments for Sr and Cs: Feed concentration (10, 50 and 100 mg/L), flow rate (2.5, 3.75 and 5 mL/min) and voltage (5, 7.5 and 10 V). The obtained data from the experiments were used to train two ANNs. The three control factors were utilized as the inputs of ANNs and two quality responses were used as the outputs, separately (each ANN for one quality response). After training the ANNs, 1024 different control factor levels with various quality responses were predicted and finally the optimum control factor levels were obtained. Results demonstrated that the optimum levels of the control factors for maximum removing of Sr (97.6%) had an applied voltage of 10 V, a flow rate of 2.5 mL/min and a feed concentration of 10 mg/L. As for Cs (67.8%) they were 10 V, 2.55 mL/min and 50 mg/L, respectively.

Radioprotection technical entries for the use of radionuclides in unsealed sources

International Nuclear Information System (INIS)

Anon.

1996-01-01

These entries are devoted to responsible persons and employees of various laboratories or medical, pharmaceutical, university and industrial departments where radionuclides are handled as well as all the persons who attend to safety in this field. They contain the essential radiation protection data for the use of radionuclides in unsealed sources. This new series includes the following radionuclides: nickel 63; gallium 68; selenium 75; krypton 85; indium 111; cesium 137; barium 137m; iridium 192 and gold 198. (O.M.)

Internal exposure of populations to long-lived radionuclides released into the environment

International Nuclear Information System (INIS)

Balonov, M.I.

1997-01-01

This chapter discusses the events that led to the contamination of environments with the long-lived radionuclides of caesium, strontium and other elements, and to the internal exposure of populations living in contaminated areas. Among these events are radioactive releases into the river Techa from the Soviet nuclear weapons facility Mayak in 1949-1956, thermonuclear weapons test in the 1950s and 1960s, the Kyshtim and Windscale accidents in 1957, and the Chernobyl and Tomsk-7 accidents in 1986 and 1993, respectively. Methods of environmental monitoring and individual internal dose monitoring of inhabitants are described. These are based on measuring the content of radionuclides not only in the air, drinking water and local food products, but also in humans using whole-body counters and analysing excreta and autopsy samples. The dynamics of internal exposure of people of different ages to radionuclides of caesium, strontium and plutonium from the environment are considered. Examples of radionuclide distributions in the environment, and of individual/collective internal doses and related medical effects are presented. (Author)

Process for recovering cesium from cesium alum

International Nuclear Information System (INIS)

Mein, P.G.

1984-01-01

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

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

Proceedings of the Task 4 Waste Isolation Safety Assessment Program second contractor information meeting

Energy Technology Data Exchange (ETDEWEB)

Serne, Jeff R.

1978-01-01

Volume II contains the following papers: Laboratory Studies of Radionuclide Distributions between Selected Groundwaters and Geologic Media; Applicability of Microautoradiography to Sorption Studies; The Kinetics and Reversibility of Radionuclide Sorption Reactions with Rocks; Mobility and Sorption Processes of Radioactive Waste Materials in Subsurface Migration; Batch K/sub d/ Experiments with Common Minerals and Representative Groundwaters; Cesium and Strontium Migration in Unconsolidated Geologic Material; Statistical Investigation of the Mechanics Controlling Radionuclide Sorption; The ARDISC Model - A Computer Program to Calculate the Distribution of Trace Element Migration in Partially-Equilibrating Media; and Some Geochemical Aspects of the Canadian Nuclear Waste Disposal System. Individual papers were processed.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

Possible measures for stimulating the elimination of radioactive strontium and cesium

International Nuclear Information System (INIS)

Volf, V.

1987-01-01

This review presents therapeutic methods which have been tested in man and can be recommended for clinical use. Oral administration of adsorptive substances such as barium sulfate, aluminum phosphate or alginate proved effective as a first aid means to block intestinal * Sr absorption, while dilution therapy with stable calcium or strontium may stimulate * Sr excretion. Oral administration of ferrihexacyanoferrate (Prussian Blue) represents the treatment of choice after incorporation of * Cs. Practical recommendations for Germany are concerned with the choice of a suitable preparation and its dosage as well as with the indications for treatment. (orig.) [de

Measurements of cesium-137 in residents of Seascale and its environs

Energy Technology Data Exchange (ETDEWEB)

Fry, F A; Sumerling, T J

1984-07-01

Measurements of the body content of cesium-137 have been made on almost 300 members of the public residing in or near Seascale, a community in west Cumbria close to the nuclear installation at Sellafield operated by British Nuclear Fuels plc. The major objective of this study was to compare the levels found in the population with those predicted from environmental measurements. No artificially-produced radionuclides were detected in the overwhelming majority of those measured. Cesium-137 was detected in about 7% of the measured population but, in general, the levels were much lower than those expected. The highest body content found was comparable with the average predicted from environmental measurements and estimates of food consumption rates; this body content corresponds to intake of cesium-137 at a rate of somewhat less than 2% of the appropriate annual limit on intake for members of the public. From this study, it is concluded that contamination of foodstuffs with cesium-137 leads to exposure of the local population at levels that are of low radiological significance, and that estimates of intake obtained from environmental monitoring data are cautious for most of the population.

Review of advanced methods for treating radioactive contaminated water

International Nuclear Information System (INIS)

Dubourg, M.

2002-01-01

The accidental release of large quantities of radionuclide after a nuclear accident tends to contaminate the groundwater system of rivers and lakes by the transfer of the main radionuclides such as Cesium 137, Strontium 90 or Cobalt 60, Ruthenium 106 and others (including transuranic radionuclides, such as: Pu 239, Pu 240, Am 241..). The aim of this paper is to review the possible solutions for the removal of these contaminants from large quantities of water. the use of crown ethers for the selective removal of strontium 90 such as the di-cyclohexyl 18 crown 6 which is able to remove with 90% of efficiency the strontium. the use of zeolites for the removal of Cesium 137. On larger scale the use of electromagnetic filtration technology is able to process in a relatively short time large quantities of water by using a seeding system of resin coated metallic magnetic particles to enhance the filtering efficiency under cold conditions. Examples of efficiencies and results obtained on loops at a fairly large will be given in this paper, theses examples show rather high efficiency of removal even at low concentration of contaminants (a few ppb: part per billion). Examples of water treatment concepts will be also given for treatment of contaminated surface water and to treat large groundwater applications. Major applications could be implemented on various sites namely in Russia (Karatchai lake) or in Belarus and Ukraine. The magnetic filtration is not a new concept but with the use of various selective adsorbing treatment particles, this concept has been proven so effective that dissolved metals in process water have been reduced to level in the very low ppb range. (authors)

Effect of cooking on radionuclide concentrations in waterfowl tissues

International Nuclear Information System (INIS)

Halford, D.K.

1983-01-01

Twenty-four commercially raised mallar ducks (Anas platyrhyncos) were released at the Test Reactor Area radioactive leaching ponds, and subsequently collected 56 to 188 days later. Liver, gizzard, and carcass were analyzed for radionuclide concentrations before and after cooking. Significant decreases (P 137 Cs, 134 Cs, 60 Co, 140 La and /sup 110m/Ag concentrations in carcass and liver samples occurred after cooking. Radionuclide concentrations in gizzard showed no significant change in radionuclide concentrations after cooking. Cesium-134 and 137 Cs concentrations decreased by 27% in carcass after cooking and reduced the dose commitment to man by that amount

Characterizing radionuclides in the B Plant HEPA filters

International Nuclear Information System (INIS)

Roege, P.E.

1998-01-01

B Plant was built during World War II to separate plutonium for nuclear weapons from reactor fuel. Later, the plant was re-equipped and used to separate radioactive fission products from the Hanford Site's nuclear processing waste tanks. The facility is now being deactivated: eliminating, stabilizing, and documenting existing hazards to allow safe surveillance and maintenance pending a final disposition which is yet to be determined. The processing areas of the plant, including process cells and exhaust air system, are heavily contaminated with radioactive cesium and strontium from the tank waste separation process. However, detailed characterization is difficult because many of these areas are inaccessible because of physical barriers and high radiological dose rates. The five existing canyon high efficiency particulate air (HEPA) filters were thought to contain a significant fraction of the inventory, but estimates were highly uncertain. This paper describes the process used to inspect and characterize the radionuclide content in one of these filters. The investigation required a collaborative effort among field and technical personnel. Sophisticated computer modeling and detector technologies were employed in conjunction with sound radiological control and field work practices. The outcome of the effort was a considerable reduction in the filter inventory estimate, accompanied by a greatly improved level of confidence in the data. The information derived from this project will provide a sound basis for future decisions regarding filter disposition

On the behaviour of artificial radionuclides at the Baltic sea coastal zone

International Nuclear Information System (INIS)

Styro, D.B.; Astrauskene, N.P.; Kadzhene, G.I.; Lukinskene, M.V.

1988-01-01

The measured results of the 137 Cs, 90 Sr and 144 Ce radionuclide concentrations near the settlement of Juodkrante at the Baltic Sea coast have been considered. The instability of the mean values of the radionuclide concentrations, especially that of strontium-90, has been determined. A certain increase of the radionuclide concentration near the sea coast as compared to that in the open sea has been noted, as well as the influence of the stormy weather on the absolute values of the radionuclide concentration at the coastal zone. 5 refs.; 3 figs.; 1 tab

Kinetics and reversibility of radionuclide sorption reactions with rocks. Progress report for fiscal year 1979

International Nuclear Information System (INIS)

Barney, G.S.; Brown, G.E.

1979-01-01

Sorption-desorption reactions of cesium, strontium, neptunium, americium, and plutonium on basalt, granite, and argillite were observed for 218 days. Equilibrium in batch experiments was not reached for most radionuclides even after this long time. Reactions of the crushed rock with ground waters (dissolution, hydrolysis, precipitation, etc.) also did not reach equilibrium after 150 days. The dissolution of basalt is accompanied by the formation of colloidal particles which contain Si, Fe, Ca, and Al. These colloids sorb Cs, Sr, Am, and Pu during equilibration. Some of the colloids pass through 0.3-μm flters, are not retained even on 0.01-μm filters and, therefore, cause calculated K/sub d/ values to be too low. Samples of crushed basalt, granite, and argillite were artificially weathered by continuous leaching with distilled water for 6 months both in air and in an oxygen-free stream of nitrogen gas. The weathered rock was then characterized for surface area, surface structure, cation exchange capacity, and composition of weathered surface on the rock. Comparisons were made of radionuclide sorption (after 14 days) on fresh rock, rock weathered in air, and rock weathered in N 2 . Sorption on rocks weathered in N 2 generally is less than on rock weathered in air. This is possibly due to the lack of an Fe(OH) 3 coating on the rock weathered in N 2 . The Fe(OH) 3 is known to scavenge cations and silica from solution. Sorption of Cs, Si, Am, and Pu is strongly affected by weathering basalt and argillite. However, the cation exchange capacity is changed very little, suggesting that ion exchange plays a minor role in sorption of these radionuclides

90Sr and 137Cs migration in food chain: soil-forage-cattle

International Nuclear Information System (INIS)

Korneev, N.A.; Sirotkin, A.N.

1982-01-01

It is established that the coefficients of biological absorption (CBA) of radionuclides by osteal and muscle tissue change with the age of animals. The CBA of strontium-90 and cesium-137 of the grown animals is 3.0 and 2.8 times respectively higher, than of young animals in the migration chain soil-forage, and in the chain forage-bone, and forage-muscles-3.4 and 1.5 times lower

Effectiveness of liquid radioactive waste purification by inorganic granulated sorbents

International Nuclear Information System (INIS)

Komarevskij, V.M.; Stepanets, O.V.; Sharygin, L.M.; Matveev, S.A.

1995-01-01

Study results on purification of simulative and real liquid radioactive wastes from fission products radionuclides and by inorganic corrosion-nature sorbents 'Thermoxide' are presented. Properties by sorption of cesium, strontium and cobalt are studied; results of experiments on purification of weakly-salted water solutions (waste waters, ships drainage tanks, showers and laundries) of the Beloyarsk NPP are presented. Sorbents source characteristics are determined. 4 refs., 2 figs., 3 tabs

Influence of competitive ions on sorption of strontium on Slovak bentonites

International Nuclear Information System (INIS)

Galambos, M.; Kufcakova, J.; Rajec, P.

2009-01-01

Production of nuclear energy, processing of irradiated fuel, preparation and use of radionuclides are processes connected with radioactive waste. Safe disposal of radioactive waste, especially of liquid high-level waste and spent nuclear fuel is a common problem of today .The most important way of the waste storage are deep geological repositories that are formed by natural and engineered barriers isolating long-lived radionuclides from the biosphere. Clay is the basic component of these barriers in many cases. Bentonite is generally considered as the most appropriate clay material. The Sr-90 (T 1/2 ∼28 years) is eco-toxically significant radioisotope of strontium has a high extraction yield in nuclear fission. From the achieved results of this work it is possible to conclude that bentonites from the localities of Jelsovy potok, Kopernica, Lastovce and Lieskovec have satisfying sorption properties for ions of strontium. The results indicate that sorption of Sr can be heavily influenced by presence of high cation concentrations of various salts, which can be present e.g. waste waters. (authors)

Adsorption behavior of strontium on kaolinite and montmorillonite and their mixtures

Energy Technology Data Exchange (ETDEWEB)

Atun, G. [Istanbul Univ. (Turkey). Engineering Faculty, Chemistry Dept.; Bascetin, E. [Cekmece Nuclear Research and Training Center, Istanbul (Turkey)

2004-07-01

{sup 90}Sr, with a long half-life of 28.5 years, is the most dangerous strontium isotope. The adsorption behavior of radionuclides in the environment are closely related to the safe disposal of radioactive wastes. Since various types of minerals may exist in and around the repositories used for ultimate disposal of nuclear waste, the adsorption behavior of certain radionuclides onto and from these minerals and similar adsorbents should be studied in order to estimate the rates of transport of the nuclides in the event of water penetration into and through the repository. Information on the adsorption properties of the purified individual clay minerals may not be sufficient to predict the adsorption properties of a corresponding mixture, because these clay minerals may interact with each other and lead to modification of the adsorption properties of the mixture as compared to the pure minerals. The adsorption behavior of strontium on kaolinite and montmorillonite minerals and their mixtures was studied by means of a batch method and a tracer technique. (orig.)

Influence of competitive ions on sorption of strontium on Slovak bentonites

International Nuclear Information System (INIS)

Galambos, M.; Kufcakova, J.; Rajec, P.

2008-01-01

Production of nuclear energy, processing of irradiated fuel, preparation and use of radionuclides are processes connected with radioactive waste. Safe disposal of radioactive waste, especially of liquid high-level waste and spent nuclear fuel is a common problem of today .The most important way of the waste storage are deep geological repositories that are formed by natural and engineered barriers isolating long-lived radionuclides from the biosphere. Clay is the basic component of these barriers in many cases. Bentonite is generally considered as the most appropriate clay material. The Sr-90 (T 1/2 ∼28 years) is eco-toxically significant radioisotope of strontium has a high extraction yield in nuclear fission. From the achieved results of this work it is possible to conclude that bentonites from the localities of Jelsovy potok, Kopernica, Lastovce and Lieskovec have satisfying sorption properties for ions of strontium. The results indicate that sorption of Sr can be heavily influenced by presence of high cation concentrations of various salts, which can be present e.g. waste waters. (authors)

Upward migration of radio-cesium and strontium in a sand-filled lysimeter

International Nuclear Information System (INIS)

Sanford, W.E.; Larsen, I.L.; McConnell, J.W.; Rogers, R.D.

1998-01-01

The upward migration of 134 Cs, 137 Cs, and 90 Sr was observed in a silica sand-filled lysimeter at the Field Lysimeter Investigations: Low Level Waste Data Base Development experiment site at Oak Ridge National Laboratory. The source of the radionuclides first observed on the surface was identified from isotopic analysis as being from the buried waste. Cores of the sand were collected and analyzed for the vertical distribution of the radionuclides. Results of analyses revealed that pulses (elevated levels) in the activity of the Cs and Sr radioisotopes occurred at the same depths. During the sectioning of the sand core collected from directly above the buried waste form it was discovered that a fine root from an unidentified plant was present throughout all but the upper few centimeters of the core. Because the upward migration was unexpected, information that may lead to the determination of a definitive mechanism of migration was not preserved. The distribution of the radionuclides coupled with the presence of the root suggest that Cs and Sr migrated upward in the evapotranspiration stream of the root. Further study must be undertaken to confirm this phenomenon. Upward migration of radionuclides as observed here could result in direct exposures and offsite releases from underground storage facilities. (Copyright (c) 1998 Elsevier Science B.V., Amsterdam. All rights reserved.)

Global deposition of fallout radionuclides and their dietary intake

International Nuclear Information System (INIS)

Morisawa, Shinsuke

1993-01-01

Japanese foods depend largely on foreign countries and domestic food supply now is no more than 30 percents if feedstuffs for live-stocks are included. Therefore not only ecological/natural but also social, e.g., human activities related, transportation of fallout radionuclides are to be taken into accounts for estimation of baseline internal irradiation dose and health risks of Japanese peoples through dietary intake of radionuclides. In this study, mathematical model is developed and examined for practical application on estimating Japanese dietary intake level of fallout strontium-90, which is accumulated in various kinds of foodstuffs and is transported to Japan associated with worldwide trades of foods, under appropriate limitations such that direct deposition on plants and seafood intake pathways are not evaluated. Deposition of strontium-90 onto the surface soil was simulated using the model, the compartment model described by a set ordinary differential equations, and the estimates were examined by comparing them with the observed data colleted and complied by the global scale environmental monitoring networks. Sensitivity analysis is also practised to find possible reduction of dietary intake of fallout radionuclides and the related potential health risks. (author)

Strontium-90 and promethium-147 recovery

International Nuclear Information System (INIS)

Hoisington, J.E.; McDonell, W.R.

1982-01-01

Strontium-90 and promethium-147 are fission product radionuclides with potential for use as heat source materials in high reliability, non-interruptible power supplies. Interest has recently been expressed in their utilization for Department of Defense (DOD) applications. This memorandum summarizes the current inventories, the annual production rates, and the possible recovery of Sr-90 and Pm-147 from nuclear materials production operations at Hanford and Savannah River. Recovery of these isotopes from LWR spend fuel utilizing the Barnwell Nuclear Fuels Plant (BNFP) is also considered. Unit recovery costs at each site are provided

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

Energy Technology Data Exchange (ETDEWEB)

Freire, Carolina Braccini

2007-07-01

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

Strontium-90 in milk and mixed diet in the Czech Republic

International Nuclear Information System (INIS)

Bartuskova, M.; Schlesingerova, E.

2014-01-01

Among various activities of National Radiation Protection Institute (SURO) monitoring of radionuclides in environment and food chain plays an important role. The monitoring takes place in frame of Czech Radiation Monitoring Network (RMN). Determinations of 90 Sr are performed according to the monitoring schedule of RMN. Strontium-90 was released into environment during the tests of nuclear weapons in the fifties and sixties of XX. century and to some extent in 1986 owing to the Chernobyl accident. Strontium is a chemical analogue of calcium and accordingly when entering a mammal body, it behaves very much like calcium. A large portion of the strontium will accumulate in bone and like calcium it transfers to milk. Since the Sr uptake by the human body from milk is an important pathway for radiostrontium incorporation, milk and milk powder are good indicators of 90 Sr content in human diet. Along with milk and milk powder, mixed diet samples composed of representative locally purchased food items according to food consumption statistics are also analysed for 90 Sr.The analyses are made using oxalate precipitation method, when interfering radionuclides are removed by precipitation scavenging and after its ingrowth 90 Y is separated and repeatedly measured by gas flow proportional counter. Strontium-90 activity is calculated as equal to 90 Y activity in equilibrium. Time evolution of 90 Sr activities in milk in Northern Moravia region (1988 present) and in Prague (1965 - present), in milk powder from the regions of the Czech Republic and in the mixed diet samples from the whole republic is presented on the poster. A very small increase due to the Chernobyl accident can be seen in milk. After the ban of atmospheric tests the level of 90 Sr has steadily been falling. The decrease is caused by radioactive decay and migration of the radionuclide in the environment. Due to this decrease activity concentrations in many samples have recently fallen under minimum significant

SORPTION AND DISPERSION OF STRONTIUM RADIONUCLIDE IN THE BENTONITE-QUARTZ-CLAY AS BACKFILL MATERIAL CANDIDATE ON RADIOACTIVE WASTE REPOSITORY

Directory of Open Access Journals (Sweden)

Herry Poernomo

2010-12-01

Full Text Available The experiment of sorption and dispersion characteristics of strontium in the mixture of bentonite-quartz, clay-quartz, bentonite-clay-quartz as candidate of raw material for backfill material in the radioactive waste repository has been performed. The objective of this research is to know the grain size effect of bentonite, clay, and quartz on the weight percent ratio of bentonite to quartz, clay to quartz, bentonite to clay to-quartz can be gives physical characteristics of best such as bulk density (rb, effective porosity (e, permeability (K, best sorption characteristic such as distribution coefficient (Kd, and best dispersion characteristics such as dispersivity (a and effective dispersion coefficient (De of strontium in the backfill material candidate. The experiment was carried out in the column filled by the mixture of bentonite-quartz, clay-quartz, bentonite-clay-quartz with the weight percent ratio of bentonite to quartz, clay to quartz, bentonite to clay to quartz of 100/0, 80/20, 60/40, 40/60, 20/80, 0/100 respectively at saturated condition of water, then flowed 0.1 N Sr(NO32 as buffer solution with tracer of 0.05 Ci/cm3 90Sr as strontium radionuclide simulation was leached from immobilized radioactive waste in the radioactive waste repository. The concentration of 90Sr in the effluents represented as Ct were analyzed by Ortec b counter every 30 min, then by using profile concentration of Co and Ct, values of Kd, a and De of 90Sr in the backfill material was determined. The experiment data showed that the best results were -80+120 mesh grain size of bentonite, clay, quartz respectively on the weight percent ratio of bentonite to clay to quartz of 70/10/20 with physical characteristics of rb = 0.658 g/cm3, e = 0.666 cm3/cm3, and K = 1.680x10-2 cm/sec, sorption characteristic of Kd = 46.108 cm3/g, dispersion characteristics of a = 5.443 cm, and De = 1.808x10-03 cm2/sec can be proposed as candidate of raw material of backfill material

Incorporation of cesium into phosphates of apatitic and rhabdophane lattices. Application to the conditioning of separated radionuclides

International Nuclear Information System (INIS)

Campayo, L.

2003-04-01

Two phosphate-based materials were investigated for cesium immobilization after its partitioning from spent nuclear fuel: apatites and rhabdophanes. The incorporation of cesium into the apatitic lattice creates steric stresses. These stresses induce the formation of secondary phases which are rapidly leached. The effectiveness of the cesium immobilization in this material is not therefore validated. A second phosphate CsCaNd(PO 4 ) 2 was consistently found at the end of the leach test and its properties were further characterized. The structure of CsCaNd(PO 4 ) 2 , which is rhabdophane-like, is made of large channels which enable the incorporation of the largest alkaline cations. The synthesis involves two intermediates: the monazite, NdPO 4 , and a soluble phosphate, CsCaPO 4 . The study of a rhabdophane with 10 wt.% of cesium reveals satisfactory intrinsic properties: a thermal stability up to 1100 C and a leach rate of 10 -2 g/(m 2 .d). The next step will be to improve the reaction yield. (author)

Toxicity of strontium-90 depending on the way of its administration to animal organisms

International Nuclear Information System (INIS)

Shvedov, V.L.

1978-01-01

Toxicity of strontium-90 administered orally is almost thrice lower than that after parenteral administration. The values of the doses absorbed in the critical organ of rats, corresponding to LDsub(50/30), were 2400 to 2600 rad irrespective of the route of the radionuclide administration

Applicability and reliability of the 'observed ratio' model as a means of describing the strontium and the cesium transfer from soil to plant. Eignung und Zuverlaessigkeit des 'observed ratio' Modells fuer die Beschreibung des Strontium- und Caesium-Transfers vom Boden in die Pflanze

Energy Technology Data Exchange (ETDEWEB)

Leising, C.

1986-12-01

The report examines the suitability of the observed ratio, (OR), model as a means of describing the soil-to-plant transfer of cesium and strontium, and the reliability of results determined by this model. Literature studies have been made and are reported in order to show the discrimination between Sr and Ca, or Cs and K, respectively, and in order to show the magnitude of the OR value and the range of values it may cover. For the evaluation of results, care has been taken that only the physiologically relevant constituents of Sr, Ca, Cs, and K concentrations in the soil are taken into account, which are the water-soluble and the adsorptively bound forms. Non-mobile forms cannot be taken up by the plant and therefore are not considered in the model. In accordance with the literature reviewed, the report also differentiates between two experimental approaches: (1) hydroponics, and (2) greenhouse or field experiments.

Cesium and strontium behaviors in wastewater collected by different sewer systems

Energy Technology Data Exchange (ETDEWEB)

Ishikawa, Nao K.; Hatanaka, Takuma; Umita, Teruyuki [Department of Civil and Environmental Engineering, Iwate University, 020-8551, Ueda 4-3-5, Morioka, Iwate (Japan); Ito, Ayumi [Department of Frontier Materials and Function Engineering, Graduate School of Engineering Iwate University, 020-8551, Ueda 4-3-5, Morioka, Iwate (Japan)

2014-07-01

The nuclear accident at the Fukushima Daiichi Nuclear Power Plant resulted in the release of radionuclides such as {sup 134}Cs, {sup 137}Cs, and {sup 90}Sr into the environment. Some of these radionuclides have been entering sewage treatment plants through sewer systems and then being transferred to sewage sludge. There are two types of sewer systems, e.g. a combined sewer system (CSS) and a separated sewer system (SSS). The CSS transfers rainwater runoff and domestic wastewater to the treatment plants in a single pipe. The SSS has independent pipes; one pipe transfers domestic wastewater to the treatment plant and the other pipe transfers rainwater runoff to river or sea. Since most of the radionuclides released into the atmosphere by the nuclear accident fell onto the land surface by precipitation, the CSS should collect more radionuclides than the SSS. However, there is little information about behavior differences of radionuclides in wastewater between the two types of sewer systems. The objective of the present study was to clarify the differences of radionuclide behavior in wastewater between the CSS and SSS. Behaviors of stable Cs and Sr in wastewater were observed as a means to predict radiocesium and radiostrontium. Two types of wastewater were collected in Morioka city, Japan: wastewater in a CSS in a rain event (WC) and wastewater in a SSS (WS). The WC was taken at a high rate filtration plant every 20 minutes from the beginning of the rain event for several hours in 2013. The WS was collected at a sewage treatment plant once a month from June to October 2013; sometimes the collection was at the time of a rain event. Suspended solid (SS) in each sample was measured as a physicochemical property. The element concentrations in total, dissolved, and particulate fractions were determined. While the SS in the WS taken on rainy day was 0.11 g/L, the SS in the WC was 0.36 g/L in the beginning of the rainfall and then decreased with time. Total Cs concentration

Feasibility Assessment of Cesium Removal using Microaglae

Energy Technology Data Exchange (ETDEWEB)

Kim, Ilgook; Ryu, Byung-Gon; Seo, Bum-Kyoung; Moon, Jei Kwon; Choi, Jong-Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

The aim of this work is to assess the feasibility of selected one of microalgae in the uptake of Cs+. The obtained results showed the maximum Cs+ removal by D. armatus SCK was 280μM indicating 70% removal efficiency. Also, D. armatus SCK could uptake Cs+ in the presence of K+, is particularly known to be transported into cells as an analog of Cs+ in freshwater condition. Recently, increased attention has been directed on the use of biological technologies for the removal of radionuclides as the cheap and eco-friendly alternative to the non-biological methods. Metal including radioactive compounds uptake by microorganisms can be occurred by metabolism –independent and/or -dependent processes. One involves biosorption based on the ability of microbial cells to bind dissolved metals; on the other involves bioaccumulation, which depends on the metabolic ability of cells to transport metals into the cytoplasm. The purpose of this work is to investigate the feasibility of microalgae in bioaccumulation system to remove cesium from solution. The effect of different environmental parameters on cesium removal was also examined.

Process for encapsulating radionuclides

International Nuclear Information System (INIS)

Brownell, L.E.; Isaacson, R.E.

1976-01-01

Radionuclides are immobilized in virtually an insoluble form by reacting at a temperature of at least 90 0 C as an aqueous alkaline mixture having a solution pH of at least 10, containing a source of silicon, the radionuclide waste, and a metal cation. The molar ratio of silicon to the metal cation is on the order of unity to produce a gel from which complex metalosilicates crystallize to entrap the radionuclides within the resultant condensed crystal lattice. The product is a silicious stone-like material which is virtually insoluble and nonleachable in alkaline or neutral environment. One embodiment provides for the formation of the complex metalo-silicates, such as synthetic pollucite, by gel formation with subsequent calcination to the solid product; another embodiment utilizes a hydrothermal process, either above ground or deep within basalt caverns, at greater than atmospheric pressures and a temperature between 90 and 500 0 C to form complex metalo-silicates, such as strontium aluminosilicate. Another embodiment provides for the formation of complex metalo-silicates, such as synthetic pollucite, by slurrying an alkaline mixture of bentonite or kaolinite with a source of silicon and the radionuclide waste in salt form. In each of the embodiments a mobile system is achieved whereby the metalo-silicate constituents reorient into a condensed crystal lattice forming a cage structure with the condensed metalo-silicate lattice which completely surrounds the radionuclide and traps the radionuclide therein; thus rendering the radionuclide virtually insoluble

Sorption of caesium and strontium onto calcium silicate hydrate in saline groundwater

International Nuclear Information System (INIS)

Sugiyama, D.; Fujita, T.

2005-01-01

Full text of publication follows: In the concept for radioactive waste disposal in Japan, cement is a potential waste packaging and backfilling material and is expected to provide chemical containment. The sorption of radionuclides onto cement materials, which controls the aqueous concentrations of elements in the pore-water, is a very important parameter when considering the release of radionuclides from the near field of a cementitious radioactive waste repository. Many safety assessment calculations currently assume radionuclide retardation as linear sorption equilibrium and describe it with a distribution ratio (R d value). In this study, the sorption mechanism is discussed by measuring the sorption isotherm of caesium, strontium (10 -5 ∼ 10 -2 mol dm -3 ) and sodium (10 -4 ∼ 10 -1 mol dm -3 ) onto Calcium Silicate Hydrate (C-S-H gel, Ca/Si 0.65 ∼ 1.2) at a liquid:solid ratio of 100:1, to support the assumption. In addition, the competitive sorption between caesium or strontium, and sodium is studied by sorption measurements using a range of sodium chloride concentration to simulate different ionic strengths in saline groundwater. The initial and equilibrated aqueous compositions were measured in the sorption experiments and it was found that caesium, strontium and sodium were sorbed by substitution for Ca in C-S-H phases by examining the mass balance. Based on the experimental results, we propose a modelling approach in which the ion-exchange model is employed and the presence of some calcium sites with different ion-exchange log K values in C-S-H is assumed by considering the composition and the structure of C-S-H. The modelling calculation results predict the measured Rd values well and also describe the competition of sorption of caesium or strontium, and sodium in the experiments. The log K values for sorption of each cation element decreased as Ca/Si ratio of C-S-H gel increased. This agrees with the trend that C-S-H gel is negatively charged at low

Sorption of graphites at high temperatures. Progress report, February 1, 1976--January 31, 1977

International Nuclear Information System (INIS)

Pyecha, T.D.; Zumwalt, L.R.

1977-01-01

Preliminary to mixed isotherm studies, one additional cesium isotherm was obtained with a finned-rod H-451 graphite sample at 1100 0 C. The results indicated that not only are long times required to reach saturation, but also there is a hysteresis effect at low vapor pressures and concentrations and that under these conditions sorption of cesium in graphite is not readily reversible. Several cesium isotherms (at 1000 0 C) were obtained of H-451 graphite which had been pre-impregnated with selected concentrations of Sr-85-tagged strontium. The runs were of long duration to attain equilibrium. The data obtained showed a substantial effect of the presence (concentration) of strontium on cesium sorption. End-of-run cesium and strontium concentration profiles were obtained. As yet the data on the mixed-sorption behavior, relative to possible models, has not been analyzed in depth. As a preliminary to the mixed-sorption studies, strontium impregnation in the absence of cesium was studied and a few experiments on the effect of concentration on strontium diffusion were carried out with interesting results. Finally a few experiments on sample characterization and on the microdistribution of cesium and strontium were conducted. It was found difficult to obtain distributions at the concentration levels characteristic of our experiments

Strontium and calcium determination in sea fishes in neighborhood of Angra nuclear power plant

International Nuclear Information System (INIS)

Ferreira, L.M.J.

1985-01-01

Strontium-90 is an important radionuclide present in the liquid effluents of the Angra Nuclear Power Plant, located in the coastline of Rio de Janeiro State. It has a long effective half-life, easy entry into food chain due to its chemical similarity to calcium and stays for a long time in solution. With the aim of calculating the concentration factor (CF) for 90 Sr and observed ratio (OR) in the most abundant local fish, it was determined the strontium and calcium content in the edible fraction of nine species and in sea water by atomic absorption spectrophotometry. (author)

Sorption of cesium in intact rock

International Nuclear Information System (INIS)

Puukko, E.

2014-04-01

The mass distribution coefficient K d is used in performance assessment (PA) to describe sorption of a radionuclide on rock. The R d is determined using crushed rock which causes uncertainty in converting the R d values to K d values for intact rock. This work describes a method to determine the equilibrium of sorption on intact rock. The rock types of the planned Olkiluoto waste disposal site were T-series mica gneiss (T-MGN), T-series tonalite granodiorite granite gneiss (T-TGG), P-series tonalite granodiorite granite gneiss (P-TGG) and pegmatitic granite (PGR). These rocks contain different amount of biotite which is the main sorbing mineral. The sorption of cesium on intact rock slices was studied by applying an electrical field to speed up migration of cesium into the rock. Cesium is in the solution as a noncomplex cation Cs + and it is sorbed by ion exchange. The tracer used in the experiments was 134 Cs. The experimental sorption on the intact rock is compared with values calculated using the in house cation exchange sorption model (HYRL model) in PHREEQC program. The observed sorption on T-MGN and T-TGG rocks was close to the calculated values. Two PGR samples were from a depth of 70 m and three samples were from a depth of 150 m. Cesium sorbed more than predicted on the two 70 m PGR samples. The sorption of Cs on the three 150 m PGR samples was small which was consistent with the calculations. The pegmatitic granite PGR has the smallest content of biotite of the four rock types. In the case of P-TGG rock the observed values of sorption were only half of the calculated values. Two kind of slices were cut from P-TGG drill core. The slices were against and to the direction of the foliation of the biotite rims. The sorption of cesium on P-TGG rock was same in both cases. The results indicated that there was no effect of the directions of the electric field and the foliation of biotite in the P-TGG rock. (orig.)

Studies of soils erosion in Protected Areas of Cienfuegos, Cuba, using Cesium - 137 as radiotracer

International Nuclear Information System (INIS)

Sibello Hernandez, Rita Y.; Febles Gonzalez, Jose M.

2011-01-01

The large-scale nuclear explosions that had taken place due to the nuclear weapons tests or as a result of nuclear accidents are the main causes of the great dispersion of artificial radionuclides around the world. One of these radionuclides is Cesium-137, which is strongly fixed to the fine soils particles. This fact, together with its half-life of 30 years and its easy detection by gamma spectrometry have converted Cesium-137, in a good radiotracer of the soils movement. This technique has been widely used and validated in different landscapes throughout the world. Its effectiveness was also previously validated and proved in Cienfuegos province too. This research was aimed at using the Cesium-137 technique to study soil redistribution and quantify erosion in the called Protected Areas in Cienfuegos province, where soil loss and sediment transport are the main causes of deterioration of these ecosystems with the consequent economic and / or environmental losses. The results were represented in a map using the software gvSIG by kriging, achieving greater visibility of the soil redistribution in the plot studied. The methodology used in this study can be used in other places wherever it is necessary to know the magnitude of the erosion problems and to know the soil redistribution pattern in the landscape which can be very useful to draw the plans for reorganization of land use.(author)

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

International Nuclear Information System (INIS)

Choma, J.; Stasiuk, J.

1992-01-01

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

Caspian Sea water balance and dynamics studies using anthropogenic radionuclides: Implications for environmental changes

International Nuclear Information System (INIS)

Oregioni, B.; Gastaud, J.; Pham, M.K.; Povinec, P.P.

2002-01-01

Full text: Environmental changes in the Caspian Sea have recently become of great interest in connection with fluctuations in sea level changes. Radioactive and stable isotopes have been used as powerful tracers to investigate water balance and dynamics and have contributed significantly to understanding climatically driven environmental changes in the Caspian Sea. The Caspian Sea is the world largest inland water body with a surface area of about 386000 km 2 and a volume of about 67000 km 3 , located in a large continental depression about 28 m below sea level. With no surface outlet, the Caspian Sea is particularly sensitive to climatic variations. The drainage area of the Caspian Sea is approximately 3.7 million square kilometers. The Volga, Ural and Terek empty into the North Caspian, with their combined annual flow accounting for 88% of all water entering the sea. The Sulak, Samur, Kura and a number of small rivers contribute about 7% of the inflow, the remainder comes from the rivers of the Iranian shore. The Caspian Sea is divided into three basins with approximately the same surface. The North Caspian Basin, maximum depth 15 m, average depth 5 m, contains 1% of the total water. The Middle Caspian (or Central) Basin has a maximum depth of 800 m and contains 22% of the total water. The South Caspian Basin, maximum depth 1024 m, average depth 330 m, contains 77% of the total Caspian Sea water. Recently there have been concerns over the environmental conditions of the Caspian Sea, especially over observed sea level changes, which have had a strong impact on the region. Anthropogenic radionuclides like 90 Sr, 137 Cs and 239 , 240 Pu are particularly useful tracers for the investigation of water dynamics. Two research-training cruises were carried out in September 1995 and August-September 1996. At every station, 60-70 liters samples of seawater from different depths were processed for sequential separation of plutonium, cesium and strontium isotopes. This was

Selection of distribution coefficients for contaminant fate and transport calculations: Strontium as a case study

International Nuclear Information System (INIS)

Kaplan, D.I.; Krupka, K.M.; Serne, R.J.

1997-01-01

As part of an ongoing project funded by a cooperative effort involving the Office of Radiation and Indoor Air (ORIA) of the U.S. Environmental Protection Agency (EPA), the Office of Environmental Restoration (EM-40) of the Department of Energy (DOE), and the Nuclear Regulatory Agency (NRC), distribution coefficient (K d ) values are being compiled from the literature to develop provisional tables for cadmium, cesium, chromium, lead, plutonium, strontium, thorium, and uranium. The tables are organized according to important aqueous- and solid-phase parameters affecting the sorption of these contaminants. These parameters, which vary with contaminant, include pH and redox conditions; cation exchange capacity (CEC); presence of iron-oxide, aluminum-oxide, clay, and mica minerals; organic matter content; and solution concentrations of contaminants, competing ions, and complexing ligands. Sorption information compiled for strontium is used to illustrate our approach. The strontium data show how selected geochemical parameters (i.e., CEC, pH, and clay content) affect Strontium K d values and the selection of open-quote default close-quote K d values needed for modeling contaminant transport and risks at sites for which site specific data are lacking. Results of our evaluation may be used by site management and technical staff to assess contaminant fate, migration, and risk calculations in support of site remediation and waste management decisions

Strontium-90 and cesium-137 in raw milk

International Nuclear Information System (INIS)

1979-01-01

Under the commission of Science and Technology Agency, prefectural public health laboratories and institutes and Japan Chemical Analysis Center have measured the levels of 90 Sr and 137 Cs in milk samples. Sampling was done as follows: 4 times of raw milk samples a year in 10 prefectures for the report to WHO, 2 times of raw milk samples a year in 4 prefectures; and 2 times of city milk samples a year in 29 prefectures. Three litters of fresh milk were collected and carbonated in the prefectural public health laboratories and institutes of each prefecture, and the carbonated samples were collected at Japan Chemical Analysis Center. At Japan Chemical Analysis Center, these collected samples were radiochemically analysed for 90 Sr and 137 Cs using the method applied for the analysis of the radionuclides contents in total diet materials. (author)

A procedure for preferential trapping of cesium cations from aqueous solutions and their separation from other inorganic cations

International Nuclear Information System (INIS)

Plesek, J.; Hermanek, S.; Selucky, P.; Williams, R.E.

1995-01-01

The title procedure is as follows. Deltahedral heteroborane anions are added to the aqueous solution containing cesium ions, precipitate (if any) is separated off, and the cesium salts involving the deltahedral heteroborane anions are trapped on activated carbon. The cobaltocarborane anion [3-Co-(1,2-C 2 B 9 H 11 ) 2 ] and/or its substitution derivatives are particularly well suited to this purpose. The process can find use in the separation of radionuclides present in waste solutions arising from spent nuclear fuel treatment. (P.A.). 1 fig

Microwave assisted synthesis of hydroxyapatite - biomass composite sorbent for strontium removal

International Nuclear Information System (INIS)

Parab, Harshala; Shenoy, Niyoti; Kumar, Sanjukta A.; Kumar, Sangita D.; Reddy, A.V.R.

2015-01-01

Radioactive wastes are a cause of concern for the environment; in case of any accidental release or improper storage. 90 Sr is one of the major fission products present in the waste solutions generated during the reprocessing of spent nuclear fuel. Its chemical resemblance to calcium, leads to various health hazards; if there is any discharge/appearance of strontium in the food chain. This necessitates the development of simple and efficient methods of strontium separation from the aqueous solutions. Among various methods used for separation, ion exchange methods are highly efficient but expensive. Recently efforts have been made for development of bioremediation based approach as a viable alternative for such problems. However, the basic requirement for of biomaterials for the use in radionuclides separation is that it should be able to withstand the radiation damage and prevent leaching of sorbed radionuclides with time. In the present studies, authors have developed a composite sorbent comprising of hydroxyapatite and coir pith (HAP-CP) and evaluated its performance for sorption of strontium. Coir pith - an agroindustrial lignocellulosic waste biomass is known for its structural stability due to the large number of aromatic rings in lignin structure. Hydroxyapatite, has also been explored by the researchers for its radiation stability and metal remediation properties. Herein, the HAP-CP composite adsorbent was prepared by microwave heating of a mixture containing phosphoric acid (H 3 PO 4 ) and calcium nitrate tetrahydrate solutions (Ca(NO 3 ) 2 .4H 2 O) in the presence of coir pith at pH 10 until complete dryness

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

Science.gov (United States)

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

2013-12-01

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

Strontium-90 in milk and mixed diet in the Czech Republic

International Nuclear Information System (INIS)

Bartuskova, M.; Schlesingerova, E.

2014-01-01

Among various activities of National Radiation Protection Institute (SURO) monitoring of radionuclides in environment and food chain plays an important role. The monitoring takes place in frame of Czech Radiation Monitoring Network (RMN). Determinations of 90 Sr are performed according to the monitoring schedule of RMN. Strontium-90 was released into environment during the tests of nuclear weapons in the fifties and sixties of XX. century and to some extent in 1986 owing to the Chernobyl accident. Strontium is a chemical analogue of calcium and accordingly when entering a mammal body, it behaves very much like calcium. A large portion of the strontium will accumulate in bone and like calcium it transfers to milk. Since the Sr uptake by the human body from milk is an important pathway for radiostrontium incorporation, milk and milk powder are good indicators of 90 Sr content in human diet. Along with milk and milk powder, mixed diet samples composed of representative locally purchased food items according to food consumption statistics are also analysed for 90 Sr.The analyses are made using oxalate precipitation method, when interfering radionuclides are removed by precipitation scavenging and after its ingrowth 90 Y is separated and repeatedly measured by gas flow proportional counter. Strontium-90 activity is calculated as equal to 90 Y activity in equilibrium. Time evolution of 90 Sr activities in milk in Northern Moravia region (1988 present) and in Prague (1965 - present), in milk powder from the regions of the Czech Republic and in the mixed diet samples from the whole republic is presented on the poster. A very small increase due to the Chernobyl accident can be seen in milk. After the ban of atmospheric tests the level of 90 Sr has steadily been falling. The decrease is caused by radioactive decay and migration of the radionuclide in the environment. Due to this decrease activity concentrations in many samples have recently fallen under minimum significant

In situ vitrification of Oak Ridge National Laboratory soil and limestone

International Nuclear Information System (INIS)

Carter, J.G.; Bates, S.O.; Maupin, G.D.

1987-03-01

Process feasibility studies were successfully performed on two different developmental scales to determine the technical application of in situ vitrification (ISV) to Oak Ridge National Laboratory (ORNL) intermediate-level waste. In the laboratory, testing was performed on crucibles containing quantities of 50% ORNL soil and 50% ORNL limestone. In the engineering-scale testing, a 1/12-scaled simulation of ORNL Trench 7 was constructed and vitrified, resulting in waste product soil and limestone concentrations of 68% and 32%, respectively. Results from the two scales of testing indicate that the ORNL intermediate-level waste sites may be successfully processed by ISV; the waste form will retain significant quantities of the cesium and strontium. Because 137 Cs is the major component of the radionuclide inventory in the ORNL seepage pits and trenches, final field process decontamination factors (i.e., off gas at the ground surface relative to the waste inventory) of 10 4 are desired to minimize activity buildup in the off-gas system. These values were realized during the engineering-scale test for both cesium and strontium. The vitrified material effectively contained 99.996% of the cesium and strontium placed in the engineering-scale test. This is equivalent to decontamination factors of greater than 10 4 . Volume reduction for the engineering-scale test was 60%. No migration of the cesium to the uncontaminated surrounding soil was detected. These favorable results indicate that, once verified in a pilot-scale test, an adequately designed ISV system could be produced to treat the ORNL seepage pits and trenches without excessive activity accumulation in the off-gas treatment system

Modelling of contamination of surface atmosphere for deflation of Cesium-137 on contaminated territories

International Nuclear Information System (INIS)

Bogdanov, A.P.; Zhmura, G.M.

1994-01-01

Presence of Cesium 137 in near land air is caused at the contaminated territories by 'local' dusting and transport of the dust from the zone of strong contamination. For large distance is it caused by resuspension of radioactive dust from the surface in the given region. In accordance with the models of dusting round square sources based on Gauss statistical model of dissemination of admixtures in the atmosphere, the contaminated areas of european part of the former of USSR with the density of contamination over 1 Ci/km 2 with Cesium 137 were represented by 30 round square sources covering the main spots of contamination. The results of calculation of contamination of the atmosphere for several cities of Belarus, Russia and Ukraine, where there are the permanent points of observation for the content of radionuclides in the air, have shown that the proposed model of dusting sources describes the contamination of near land air with Cesium 137 reasonably well. 7 refs., 3 tabs

Use of Cesium-137 Fallout in Soil Erosion Investigations in Protected Areas in Cienfuegos Province, Cuba

International Nuclear Information System (INIS)

Sibello Hernandez, Rita Y.

2011-01-01

The large-scale nuclear explosions that had taken place due to the nuclear weapons tests or as a result of nuclear accidents are the main causes of the great dispersion of artificial radionuclides around the world. One of these radionuclides is Cesium-137, which is strongly fixed to the fine soils particles. This fact, together with its half-life of 30 years and its easy detection by gamma spectrometry have converted Cesium-137, in a good radiotracer of the soils movement. This technique has been widely used and validated in different landscapes throughout the world. Its effectiveness was also previously validated and proved in Cienfuegos province too. This research was aimed at using the Cesium-137 technique to study soil redistribution and quantify erosion in the called Protected Areas in Cienfuegos province, where soil loss and sediment transport are the main causes of deterioration of these ecosystems with the consequent economic and / or environmental losses. The results were represented in a map using the software SURFER 8.0, achieving greater visibility of the soil redistribution in the plot studied. The methodology used in this study can be used in other places wherever it is necessary to know the magnitude of the erosion problems and to know the soil redistribution pattern in the landscape which can be very useful to draw the plans for reorganization of land use. (Author)

Study on radionuclide migration through a buffer material of the repository for high level nuclear waste

International Nuclear Information System (INIS)

Tsukamoto, Masaki; Ohe, Toshiaki

1989-01-01

The present report discusses radionuclide migration through a buffer material from the view point of experimental and data analysis. Na-bentonite loosely compacted with dry density of 0.8 - 1 g/cm 3 was contacted with cesium chloride solution of about 100 ppb containing Cs-134 as a tracer at 40degC and at 70degC. After the experiments, the bentonite cake was sliced and cesium distribution in the cake was measured by gamma-spectrometry. Apparent diffusivities of 2∼5 x 10 -7 cm 2 /sec was determined through the analysis method where pore diffusion and adsorption were involved. Numerical solution well described the observed data. The pore diffusion would be clearfied to be a dominant mechanism of the radionuclide migration in the bentonite, through discussing the pore diffusion mechanism and activation energy of the diffusion. This report also discusses the capability of the chemical transport model CHEMTRN for long-term predictions of the radionuclide migration. (author)

Small-Scale Ion Exchange Removal of Cesium and Technetium from Hanford Tank 241-AN-102

International Nuclear Information System (INIS)

Hassan, N.M.

2000-01-01

The pretreatment process for BNFL, Inc.'s Hanford River Protection Project is to provide decontaminated low activity waste and concentrated eluate streams for vitrification into low and high activity waste glass, respectively. The pretreatment includes sludge washing, filtration, precipitation, and ion exchange processes to remove entrained solids, cesium, transuranics, technetium, and strontium. The cesium (Cs-137) and technetium (Tc-99) ion exchange removal is accomplished by using SuperLig 644, and 639 resins from IBC Advanced Technologies, American Fork, Utah. The resins were shown to selectively remove cesium and technetium (as anionic pertechnetate ) from alkaline salt solutions. The efficiency of ion exchange column loading and elution is a complex function involving feed compositions, equilibrium and kinetic behavior of ion exchange resins, diffusion, and the ionic strength and pH of the aqueous solution. A previous experimental program completed at the Savannah River Tech nology Center2 demonstrated the conceptualized flow sheet parameters with an Envelope C sample from Hanford Tank 241-AN-107. Those experiments also included determination of Cs and Tc batch distribution coefficients by SuperLig 644 and 639 resins and demonstration of small-scale column breakthrough and elution. The experimental findings were used in support of preliminary design bases and pretreatment flow sheet development by BNFL, Inc

Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

Energy Technology Data Exchange (ETDEWEB)

William Linak

2004-12-16

Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification.

Isolation of Metals from Liquid Wastes: Reactive Scavenging in Turbulent Thermal Reactors

International Nuclear Information System (INIS)

William Linak

2004-01-01

Sorption of cesium and strontium on kaolinite powders was investigated as a means to minimize the emissions of these metals during certain high temperature processes currently being developed to isolate and dispose of radiological and mixed wastes. In this work, non-radioactive aqueous cesium acetate or strontium acetate was atomized down the center of a natural gas flame supported on a variable-swirl burner in a refractory-lined laboratory-scale combustion facility. Kaolinite powder was injected at a post-flame location in the combustor. Cesium readily vaporizes in the high temperature regions of the combustor, but was reactively scavenged onto dispersed kaolinite. Global sorption mechanisms of cesium vapor on kaolinite were quantified, and are related to those available in the literature for sodium and lead. Both metal adsorption and substrate deactivation steps are important, and so there is an optimum temperature, between 1400 and 1500 K, at which maximum sorption occurs. The presence of chlorine inhibits cesium sorption. In contrast to cesium, and in the absence of chlorine, strontium was only partially vaporized and was, therefore, only partially scavengeable. The strontium data did not allow quantification of global kinetic mechanisms of interaction, although equilibrium arguments provided insight into the effects of chlorine on strontium sorption. These results have implications for the use of sorbents to control cesium and strontium emissions during high temperature waste processing including incineration and vitrification

Radionuclide Concentrations in Terrestrial Vegetation and Soil Samples On and Around the Hanford Site, 1971 Through 2008

Energy Technology Data Exchange (ETDEWEB)

Simmons, Mary Ann; Poston, Ted M.; Fritz, Brad G.; Bisping, Lynn E.

2011-07-29

Environmental monitoring is conducted on the U.S. Department of Energy (DOE) Hanford Site to comply with DOE Orders and federal and state regulations. Major objectives of the monitoring are to characterize contaminant levels in the environment and to determine site contributions to the contaminant inventory. This report focuses on surface soil and perennial vegetation samples collected between 1971 and 2008 as part of the Pacific Northwest National Laboratory Surface Environmental Surveillance Project performed under contract to DOE. Areas sampled under this program are located on the Hanford Site but outside facility boundaries and on public lands surrounding the Hanford Site. Additional samples were collected during the past 8 years under DOE projects that evaluated parcels of land for radiological release. These data were included because the same sampling methodology and analytical laboratory were used for the projects. The spatial and temporal trends of six radionuclides collected over a 38-year period were evaluated. The radionuclides----cobalt-60, cesium-137, strontium-90, plutonium-238, plutonium-239/240, and uranium (reported either as uranium-238 or total uranium)----were selected because they persist in the environment and are still being monitored routinely and reported in Hanford Site environmental reports. All these radionuclides were associated with plutonium production and waste management of activities occurring on the site. Other sources include fallout from atmospheric testing of nuclear weapons, which ended in 1980, and the Chernobyl explosion in 1986. Uranium is also a natural component of the soil. This assessment of soil and vegetation data provides important information on the distribution of radionuclides in areas adjacent to industrial areas, established perimeter locations and buffer areas, and more offsite nearby and distant locations. The concentrations reflect a tendency for detection of some radionuclides close to where they were

Synthesis and Characterization of Silicon Titanate as Cation Exchanger and Their Use in the Treatment of Radioactive Liquid Waste

International Nuclear Information System (INIS)

El-Naggar, I.M.; Belacy, N.; Mohamed, D.A.; Abou-Mesalam, M.M.

1999-01-01

Anew class of inorganic ion exchanger called crystalline silicon titanates has excellent chemical and radiation stability. The materials exhibited high selectivity for the ion exchange of cesium, strontium and several other radionuclides from highly acidic solutions. The ion exchange capacity was determined for Na +, Cs +, Co 2+ and Sr 2+ ions and found to be 1.17 , 1.9, 1.38 and 1.52 meq./g, respectively. Besides, the drying temperature of silicon titanates have a profound effect on the ion exchange capacities and distribution coefficient values of the above mentioned cations. Moreover, the studied results of distribution coefficient indicating the ability of separation of these radionuclides from radwaste solutions

Waste Encapsulation and Storage Facility (WESF) Waste Analysis Plan

International Nuclear Information System (INIS)

SIMMONS, F.M.

2000-01-01

The purpose of this waste analysis plan (WAP) is to document waste analysis activities associated with the Waste Encapsulation and Storage Facility (WESF) to comply with Washington Administrative Code (WAC) 173-303-300(1), (2), (3), (4), (5), and (6). WESF is an interim status other storage-miscellaneous storage unit. WESF stores mixed waste consisting of radioactive cesium and strontium salts. WESF is located in the 200 East Area on the Hanford Facility. Because dangerous waste does not include source, special nuclear, and by-product material components of mixed waste, radionuclides are not within the scope of this documentation. The information on radionuclides is provided only for general knowledge

Assessment of Neptunium, Americium, and Curium in the Savannah River Site Environment

International Nuclear Information System (INIS)

Carlton, W.H.

1997-01-01

A series of documents has been published in which the impact of various radionuclides released to the environment by Savannah River Site (SRS) operations has been assessed. The quantity released, the disposition of the radionuclides in the environment, and the dose to offsite individuals has been presented for activation products, carbon cesium, iodine, plutonium, selected fission products, strontium, technetium, tritium, uranium, and the noble gases. An assessment of the impact of nonradioactive mercury also has been published.This document assesses the impact of radioactive transuranics released from SRS facilities since the first reactor became operational late in 1953. The isotopes reported here are 239Np, 241Am, and 244Cm

Cesium-137 inventory of the undisturbed soil areas in the Londrina Region, Parana, Brazil

International Nuclear Information System (INIS)

Andrello, Avacir C.; Appoloni, Carlos Roberto

2005-01-01

Cesium-137 is an artificial radionuclide introduced in the environment through the radioactive fallout of the superficial tests of nuclear weapons. The cesium-137 deposition occurred to middles of the 1980-decade and, due to the Chernobyl accident, great part of Europe had a additional fallout of cesium-137. The contaminations of this accident do not have reached Southern Hemisphere. Cesium-137 is an alkaline metal, high electropositive, that in contact with the soil is strongly adsorbed to the clay in the FES (Frayed Edge Sites) and RES (Regular Edge Sites) positions, and it movement by chemical processes in the soil is insignificant. Because of this, cesium-137 became a good soil marker, and its movement is related to the soil movement particles, so that the cesium-137 have been used in the study of the soil redistribution processes, as a tool of quantifying the rates of soil losses and gain. To use this methodology, it is necessary the knowledge of the reference inventory of cesium-137, that is given as function of the total concentration of cesium-137 deposited in an area by the radioactive fallout. If a sampling point presents less cesium-137 than the reference inventory, this point is considered a point with soil loss; otherwise, the point is considered a point with soil deposition. To evaluate the cesium-137 inventory in the Londrina region, four areas of the undisturbed soil were sampling in grid of 3x3, with a distance of 9 meters among the points. Of these four sampling areas, three areas were of native forest (labeled Mata1, Mata2 and Mata UEL), and one was a pasture area. Cesium-137 inventory was 223 ± 41 Bq m -2 , 240 ± 65 Bq m -2 and 305 ± 36 Bq m -2 for Mata UEL, Mata1 and Mata2, respectively, and of 211 ± 28 Bq m -2 for the native pasture. Considering the deviation in each value, it is not possible to conclude that there are differences among the values of cesium-137 inventory, so that the average reference inventory of cesium-137 for the

Selective decontamination for cesium and strontium in evaporation concentrates from reprocessing plants with crown ethers by transport through supported liquid membranes

International Nuclear Information System (INIS)

Casas i Garcia, J.

1991-01-01

Reprocessing operations lead to the production of radioactive medium activity liquid waste which is treated by evaporation. The concentrates from reprocessing plant evaporators have to be stored in geological storage sites in view of their strong caesium, strontium and actinides activity. These elements, contained in acid and high sodium nitrate content liquid waste, are removed by means of selective extractants, using the supported liquid membrane technique (SLM), which allows them to be stored in surface sites, the actinides and long-life fission products being respectively recycled and concentrated into reduced volumes. The removal of the actinides is done by means of an Octyl N.N Diisobutyl Carbamoyl Methyl Phosphine Oxyde (C.M.P.O.) based liquid membrane, whereas the removal of the caesium and strontium involves crown ethers. Supported liquid membranes (S.L.M.s) have the advantage of implementing very small quantities of extractant, but, they generally have poor stability. The extractant, the diluent and the phase modifier that constitute the organic phase impregnating the membrane play a vital role in SLM stability; the support also affects stability by its nature and geometry. For the extraction of strontium, DtBu 18 C6 enables higher strontium transfer kinetics to be attained than with DC18 C6. As regards caesium, nDec B21 C7 is the most efficient. Unlike strontium, caesium cannot be quantitatively removed, due to the competition of sodium ions in the concentrate. Stable membranes are obtained with DC18 C6 or DtBu18 C6 diluted in alkylbenzene with an added phase modifier such as decanol or isotridecanol. The highest strontium transfer kinetics were obtained with the DC18 C6/hexylbenzene/isotridecanol mixture

Representation of a model of radionuclide transfer in food chains following deposition of strontium-90, cesium-137 and iodine-131 on areas for agricultural use

International Nuclear Information System (INIS)

Proehl, G.

1990-09-01

The 'SINK' model (contaminants in food chains - FORTRAN 77) was used in an attempt to predict the amounts of radioactivity building up in animal and vegetable foods after one single deposition of Sr-90, Cs-137 and I-131. The model is described in detail. The input quantities include such factors as time-integrated concentration of activity in the air just above the ground, physicochemical form of the radionuclides, activity deposited with precipitation and amount of rain to fall in any particular case. The model was so designed as to take account of 18 different plants, 11 animal products and 14 kinds of processed nutrients. The radionuclide contents of vegetable foods were calculated with reference to the season of the year, at which deposition took place. The estimations of the activity concentrations in animal foods were in each case based on different fudder rations. (orig./HP) [de

Radiochemical schemes of obtaining 89Sr and 90Y radionuclides

International Nuclear Information System (INIS)

Usarov, Z. O.

2010-03-01

Key words: strontium-89, yttrium-90, extraction and extraction-chromatographic purification of radionuclides, radiopharmaceuticals. Subjects of research: strontium-89 and yttrium-90 radionuclides and their chloride forms. Purpose of work is developing of radiochemical technologies on obtaining of 89 Sr and 90 Y on the WWR-SM reactor with high radionuclide purity. Methods of research: extraction and extraction-chromatographic methods of radionuclides separation, beta- and gamma-spectrometric methods of activity measuring. The results obtained and their novelty: Were determined the conformity to laws of Y and Sr distribution in two-phase systems TBP-HNO 3 , TBP-NH 4 NO 3 , TBP-HCI, HDEHP-NO 3 , HDEHP-NH 4 NO 3 and HDEHP-HCI. Were determined the conformity to laws of Y and Sr distribution in systems with craun ethers DB-18K-6 and DTBDB-18K-6 from water solutions of HNO 3 . Radiochemical technologies on obtaining of 89 Sr and 90 Y radionuclides including radiochemical process of yttrium target with using the systems TBP-HNO 3 and HDEHP/Teflone were developed. Practical value: the radiochemical technology of obtaining 89 Sr with high radionuclide purity was developed. The method of preparation a chloride compound of 89 SrCl 2 which is used as a drug form for preparation of 89 Sr- 'Metastron' was developed. The relatively simple method of on the way obtaining 90 Y in the reactor with high radionuclidic purity that is useful for follow using in medical practice was offered. Degree of embed and economic effectivity: the developed technologies have approbation in manufacturing conditions in Radiopreparat Enterprise of INP AS RU and were offered for receiving of domestic preparations against of import foreign analogues. The statement about using the invention by obtained patent is attached to dissertation. Field of application: the received results will be introduced in manufacture at Radiopreparat Enterprise of INP AS RU for receiving of domestic preparations

Levels of strontium 90 in the environment at PINSTECH (Period 1979-1980)

International Nuclear Information System (INIS)

Perveen, N.; Aziz, A.

1981-01-01

Strontium 90, a most toxic among the beta emitting radionuclides, is found in the environment originating mostly from the global fallout from nuclear tests. Radioactive concentration of this radionuclide was measured in air-borne particulates, precipitation, surface water, seasonal vegetables and other items of diet. The report describes a radiochemical procedure for the separation of Y 90 by solvent extraction leading to the determination of Sr 90 content in the environmental and biological samples. The report also presents data on the concentration of Sr 90 in the biomedia at PINSTECH during 1979-80. The values of these concentrations are fairly comparable to those published in the current literature. (author)

Permanganate Treatment of Savannah River Site Simulant Wastes for Strontium and Actinide Removal

International Nuclear Information System (INIS)

Wilmarth, W.R.

2003-01-01

This study examined the use of sodium permanganate and strontium nitrate to remove the actinides and radio-strontium from Savannah River Site (SRS) waste supernate. We examined the quantities of chemical feed reagents along with increased mixing and the excess of organic reductant. Additionally, we examined two processing schemes including that applicable to either the Salt Waste Processing Facility or the Alpha Removal Process (ARP) (5.6 M sodium ion concentration) conditions and the conditions for an In-Tank application (7.5 M sodium ion concentration). Our results support the following conclusions: The process met minimum required decontamination factors (DFs) within the tested parameter sets for strontium and plutonium in both the ARP and In-Tank application. The strontium DFs far exceeded the required values within the tested parameter sets. Within the ARP application, the use of peroxide as the reductant for permanganate produced higher plutonium DFs than the use of sodium formate. Reductant concentration and degree of mixing strongly influenced radionuclide decontamination. In the formate application under the ARP process, increasing the reductant concentration and mixing energy resulted in higher Sr and Pu decontamination

Ion exchange removal of strontium from simulated and actual N-Springs well water at the Hanford 100-N Area

International Nuclear Information System (INIS)

Brown, G.N.; Carson, K.J.; DesChane, J.R.; Elovich, R.J.; Kafka, T.M.; White, L.R.

1996-06-01

Experimental ion exchange studies are being conducted by the Pacific Northwest national Laboratory (PNNL) under the Efficient Separations and Processing (ESP) Crosscutting Program to evaluate newly emerging materials and technologies for removing cesium, strontium, technetium, and transuranic elements from simulated and actual wastes at Hanford. Previous work focused on applications to treat high-level alkaline tank wastes, but many of the technologies can also be applied in process and ground-water remediation. Ultimately, each process must be evaluated in terms of life-cycle costs, removal efficiency, process chemical consumption and recycle, stability of materials exposed to chemicals and radiation, compatibility with other process streams, secondary waste generation, process and maintenance costs, and final material disposal. This report assesses the performance of the 3M-designed Process Absorber Development Unit (PADU) and the AlliedSignal-produced sodium nonatitanate (NaTi) material in trace quantities of strontium from simulated and actual Hanford N-Springs ground water. The experimental objective was to determine the strontium-loading breakthrough profile of a proprietary 3M-engineered material in either disk or cartridge forms

Precipitation-adsorption process for the decontamination of nuclear waste supernates

Science.gov (United States)

Lee, L.M.; Kilpatrick, L.L.

1982-05-19

High-level nuclear waste supernate is decontaminated of cesium by precipitation of the cesium and potassium with sodium tetraphenyl boron. Simultaneously, strontium-90 is removed from the waste supernate sorption of insoluble sodium titanate. The waste solution is then filtered to separate the solution decontaminated of cesium and strontium.

Radionuclide transport modelling for a buried near surface low level radioactive waste

International Nuclear Information System (INIS)

Terzi, R.

2004-01-01

The disposal of radioactive waste, which is the last step of any radioactive waste management policy, has not yet been developed in Turkey. The existing legislation states only the discharge limits for the radioactive wastes to be discharged to the environment. The objective of this modelling study is to assist in safety assessment and selecting disposal site for gradually increasing non-nuclear radioactive wastes. This mathematical model has been developed for the environmental radiological assessment of near surface disposal sites for the low and intermediate level radioactive wastes. The model comprised of three main components: source term, geosphere transport and radiological assessment. Radiation dose for the babies (1 years age) and adults (≥17 years age) have been computed for the radionuclides Cesium 137 (Cs-137) and Strontium 90 (Sr-90), having the activity of 1.10 12 Becquerel(Bq), in radioactive waste through transport of radionuclide in liquid phase with the various pathways. The model consisted of first order ordinary differential equations was coded as a TCODE file in MATLAB program. The radiation dose to man for the realist case and low probability case have been calculated by using Runge-Kutta solution method in MATLAB programme for radionuclide transport from repository to soil layer and then to the ground water(saturated zone) through drinking water directly and consuming agricultural and animal products pathways in one year period. Also, the fatal cancer risk assessment has been made by taking into account the annual dose received by people. Various dose values for both radionuclides have been found which depended on distribution coefficient, retardation factor and dose conversion factors. The most important critical parameters on radiological safety assessment are the distribution coefficient in soil layer, seepage velocity in unsaturated zone and thickness of the unsaturated zone (soil zone). The highest radiation dose and average dose to

New sorption-reagent materials for decontamination of liquid radioactive waste

International Nuclear Information System (INIS)

Avramenko, V.A.; Golikov, A.P.; Zheleznov, V.V.; Kaplun, E.V.; Marinin, D.V.; Sokolnitskaya, T.A.

2001-01-01

Full text: Use of selective sorbents in liquid radioactive waste (LRW) management is widely spread in the field of nuclear power objects liquid waste decontamination, since the main objective there is to remove long-lived radionuclides of the nuclear cycle. The latter include, first of all, cesium-137, strontium-90, cobalt-60 and a number of α-irradiators. In this case LRW composition for most of the nuclear power objects is rather simple, except acidic deactivation solutions. At the same time, liquid radioactive wastes of different research centers have a variable chemical and radiochemical composition depending on objectives and tasks of a given center research activities. As a result, application of sorption technologies in such waste decontamination determines special requirements to these sorbents selectivity: a wide spectrum of radionuclides that can be removed and fairly high selectivity enabling to remove radionuclides from solutions of complex chemical composition (containing surfactants, complexing agents etc.). This paper is concerned with studying properties of new materials selective to different radionuclides. These materials are capable to interact with solution components whether already contained in the waste or deliberately added into resulting solution. Such sorption-reagent materials combine universal character of co-precipitation methods with simplicity of sorption methods. In this work we studied sorption-reagent inorganic ion-exchange materials interacting with sulfate-, carbonate-, oxalate-, sulfide-, and permanganate-ions. Insoluble compounds formed as a result of this interaction increase tens- and hundreds-fold the sorption selectivity of different radionuclides - strontium, cobalt, mercury, iron, and manganese as compared to conventional ion-exchange system. By means of X-ray phase analysis, IR-spectroscopy, chemical and radiochemical analysis, we have studied the mechanism of radionuclide sorption on different sorption

An overview of Fukushima radionuclides measured in the northern hemisphere

International Nuclear Information System (INIS)

Thakur, P.; Ballard, S.; Nelson, R.

2013-01-01

The Great East Japan Earthquake and tsunami on March 11, 2011 resulted in the tragic accident at the Fukushima Nuclear Power Plant (NPP) and subsequently uncontrolled release of radioactive contaminants into the atmosphere. This review article attempts to compile and interpret data collected by various national and international monitoring networks in response to the Fukushima releases across the northern hemisphere. The majority of the releases occurred during the period March 12–22 with a maximum release phase from March 14–17, 2011. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases (xenon and krypton), iodine, cesium, and tellurium. The radioactive gases and particles released in the accident were dispersed over the middle latitudes of the entire northern hemisphere and for the first time also measured in the southern Hemisphere. Isotopes of iodine and cesium were detected in air, water, milk and food samples collected across the entire northern hemisphere. Elevated levels of fission products were detected from March to May 2011 at many locations over the northern hemisphere. This article focuses on the most prevalent cesium and iodine isotopes, but other secondary isotopes are also discussed. Spatial and temporal patterns and differences are contrasted. The activity ratios of 131 I/ 137 Cs and 134 Cs/ 137 Cs measured at several locations are evaluated to gain an insight into the fuel burn-up, the inventory of radionuclides in the reactor and the isotopic signature of the accident. It is important to note that all of the radiation levels detected outside of Japan have been very low and are well below any level of public and environmental hazard. - Graphical abstract: The trace levels of radioactivity in air, water, and milk samples collected across the northern hemisphere between March–May, 2011 from the damaged Fukushima Daiichi nuclear power plant, Japan are discussed. Highlights: • We report

An overview of Fukushima radionuclides measured in the northern hemisphere

Energy Technology Data Exchange (ETDEWEB)

Thakur, P., E-mail: pthakur@cemrc.org [Carlsbad Environmental Monitoring and Research Center, 1400 University Drive, Carlsbad, NM 88220 (United States); Ballard, S. [Carlsbad Environmental Monitoring and Research Center, 1400 University Drive, Carlsbad, NM 88220 (United States); Nelson, R. [Department of Energy, Carlsbad Field Office, 4021, National Parks Hwy, Carlsbad, NM 88220 (United States)

2013-08-01

The Great East Japan Earthquake and tsunami on March 11, 2011 resulted in the tragic accident at the Fukushima Nuclear Power Plant (NPP) and subsequently uncontrolled release of radioactive contaminants into the atmosphere. This review article attempts to compile and interpret data collected by various national and international monitoring networks in response to the Fukushima releases across the northern hemisphere. The majority of the releases occurred during the period March 12–22 with a maximum release phase from March 14–17, 2011. The radioactivity released was dominated by volatile fission products including isotopes of the noble gases (xenon and krypton), iodine, cesium, and tellurium. The radioactive gases and particles released in the accident were dispersed over the middle latitudes of the entire northern hemisphere and for the first time also measured in the southern Hemisphere. Isotopes of iodine and cesium were detected in air, water, milk and food samples collected across the entire northern hemisphere. Elevated levels of fission products were detected from March to May 2011 at many locations over the northern hemisphere. This article focuses on the most prevalent cesium and iodine isotopes, but other secondary isotopes are also discussed. Spatial and temporal patterns and differences are contrasted. The activity ratios of {sup 131}I/{sup 137}Cs and {sup 134}Cs/{sup 137}Cs measured at several locations are evaluated to gain an insight into the fuel burn-up, the inventory of radionuclides in the reactor and the isotopic signature of the accident. It is important to note that all of the radiation levels detected outside of Japan have been very low and are well below any level of public and environmental hazard. - Graphical abstract: The trace levels of radioactivity in air, water, and milk samples collected across the northern hemisphere between March–May, 2011 from the damaged Fukushima Daiichi nuclear power plant, Japan are discussed. Highlights

Radionuclides release from re-irradiated fuel under high temperature and pressure conditions. Gamma-ray measurements of VEGA-5 test

Energy Technology Data Exchange (ETDEWEB)

Hidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko; Kanazawa, Toru; Kiuchi, Toshio; Uetsuka, Hiroshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2003-03-01

The VEGA (Verification Experiments of radionuclides Gas/Aerosol release) program is being performed at JAERI to clarify mechanisms of radionuclides release from irradiated fuel during severe accidents and to improve source term predictability. The fifth VEGA-5 test was conducted in January 2002 to confirm the reproducibility of decrease in cesium release under elevated pressure that was observed in the VEGA-2 test and to investigate the release behavior of short-life radionuclides. The PWR fuel of 47 GWd/tU after about 8.2 years of cooling was re-irradiated at Nuclear Safety Research Reactor (NSRR) for 8 hours before the heat-up test. After that, the two pellets of 10.9 g without cladding were heated up to about 2,900 K at 1.0 MPa under the inert He condition. The experiment reconfirmed the decrease in cesium release rate under the elevated pressure. The release data on short-life radionuclides such as Ru-103, Ba-140 and Xe-133 that have never been observed in the previous VEGA tests without re-irradiation was obtained using the {gamma} ray measurement. (author)

Biosorption of uranium, radium, and cesium

International Nuclear Information System (INIS)

Strandberg, G.W.

1982-01-01

Some fundamental aspects of the biosorption of metals by microbial cells were investigated. These studies were carried out in conjunction with efforts to develop a process to utilize microbial cells as biosorbents for the removal of radionuclides from waste streams generated by the nuclear fuel cycle. It was felt that an understanding of the mechanism(s) of metal uptake would potentially enable the enhancement of the metal uptake phenomenon through environmental or genetic manipulation of the microorganisms. Also presented are the results of a preliminary investigation of the applicability of microorganisms for the removal of 137 cesium and 226 radium from existing waste solutions. The studies were directed primarily at a characterization of uranium uptake by the yeast, Saccharomyces cerevisiae, and the bacterium, Pseudomonas aeruginosa

Quality control methods of strontium chloride 89SrCl2, radiopharmaceutical for palliative treatment of bone metastases

International Nuclear Information System (INIS)

Deptula, C.Z.; Kempisty, T.; Markiewicz, A.; Mikolajczak, R.; Stefancyk, S.; Terlikowska, T.; Zulczyk, W.

1997-01-01

Strontium chloride, 89 SrCI 2 , a radiopharmaceutical used for palliative therapy of bone metastases from breast and prostate cancer is produced by irradiation in a nuclear reactor. The analytical quality control procedures are established to confirm the radionuclidic purity of the preparation, its chemical composition and specific activity. Chemical concentration of strontium in the product is determined by complexometry with arsenazo III and chlorides assay by potentiometric titration with silver nitrate. The contamination with chemical impurities is determined by DC graphite spark spectrography. The specific activity and isotonicity of the solution are corrected by addition of natural SrCI 2 and NaCI. 90 Sr is produced in the 89 Sr(n,γ) 90 Sr reaction contributes to impurities. It decays to 90 Y and the activity of 90 Sr can be calculated from the activity of 90 Y. The extraction chromatography on nonionic acrylic ester polymer coated with organic solutions of selective features (Spec resins for Eichrom) is applied for separation of radionuclides. The extraction chromatography system consisting of two columns: strontium selective resin and rare earth elements selective resin was used for separation of 90 Y from 90 Sr in the 89 SrCI 2 solution. The 90 Y and 90 Sr carrier-free solutions used as tracers helped for determination of extraction conditions and efficiency. The concentration of 90 Sr determined in the analysed solution is at the level of 2.10 -4 % which conforms with the data calculated from irradiation parameters. The obtained product, strontium chloride 89 SrCI 2 for injection, forms a sterile and isotonic water solution (pH - 4-7) with specific activity of 89 Sr in the range from 3.5 to 6.3. MBq/mg and radioactive concentration of 37.5 MBq/ml. The radionuclidic purity of the obtained preparations is at the level of 99.9% with respect to 89 Sr

Radiochemical analysis of fallout in Norway

Energy Technology Data Exchange (ETDEWEB)

Bergh, H; Finstad, G; Lund, L; Michelsen, O; Ottar, B

1957-01-01

Data are tabulated on the concentration of radioactive iodine, strontium, and cesium in samples of milk and radioactive strontium and cesium in samples of drinking water collected in Norway during June 1957.

Assessment of the radionuclide composition of "hot particles" sampled in the Chernobyl nuclear power plant fourth reactor unit.

Science.gov (United States)

Bondarkov, Mikhail D; Zheltonozhsky, Viktor A; Zheltonozhskaya, Maryna V; Kulich, Nadezhda V; Maksimenko, Andrey M; Farfán, Eduardo B; Jannik, G Timothy; Marra, James C

2011-10-01

Fuel-containing materials sampled from within the Chernobyl Nuclear Power Plant (ChNPP) Unit 4 Confinement Shelter were spectroscopically studied for gamma and alpha content. Isotopic ratios for cesium, europium, plutonium, americium, and curium were identified, and the fuel burn-up in these samples was determined. A systematic deviation in the burn-up values based on the cesium isotopes in comparison with other radionuclides was observed. The studies conducted were the first ever performed to demonstrate the presence of significant quantities of 242Cm and 243Cm. It was determined that there was a systematic underestimation of activities of transuranic radionuclides in fuel samples from inside of the ChNPP Confinement Shelter, starting from 241Am (and going higher) in comparison with the theoretical calculations.

Ion exchange of radionuclides on natural and modified micaceous minerals

International Nuclear Information System (INIS)

Kojvula, R.; Lekhto, Yu.

1998-01-01

Interaction of 134 Cs, 85 Sr and 60 Co with three micaceous minerals: muscovites, biotites and phlogopite is studied. Two types of micaceous minerals: natural ones, wherein potassium is an exchange cation, and samples, converted into sodium form, are studied/ It is found that biotite and phlogopite in the sodium form are specified by high selectivity to cobalt with distribution coefficient above 10 5 ml/g, whereas the muscovite potassium form is characterized by high selectivity to cesium. Neither of the micaceous minerals is characterized by selectivity to strontium. Distribution coefficients strongly depend on pH of the medium

Transfer coefficients of radionuclides secreted in milk of dairy cows

International Nuclear Information System (INIS)

Sam, D.; Williams, W.F.; Rockmann, D.D.; Allen, J.T.

1980-01-01

This study simulated experimentally the transfer of radionuclides to milk of dairy cows on a worst-case situation using various radionuclides known to emanate from nuclear power stations and which have been detected on particulates. Two lactating Holstein cows were administered orally one gelatin capsule containing 10 radionuclides in water-soluble form per day for 14 consecutive days. Milk samples were collected and aliquots analyzed in a germanium lithium-drifted detector coupled to a 2048-multichannel gamma-ray analyzer to measure small amounts of complex mixtures of radionuclides. The transfer coefficients of the radionuclides were calculated when their secretion in milk reached or approached a plateau of concentration. The radionuclides and their transfer coefficients to milk were: chromium 51 less than 0.01%; manganese 54 0.033 +- 0.005%; cobalt 60 0.01 +- 0.002%; iron 59 0.0048 +- 0.002%; zinc 65 0.31 +- 0.07%; selenium 75 0.29 +- 0.1%; antimony 125 0.011 +- 0.003%; iodine 131 0.88 +- 0.05%; and cesium 137 0.79 +- 0.08%

Radionuclides in the Mosel river in the years 1981 to 2011

International Nuclear Information System (INIS)

Hartkopf, Jens

2012-01-01

As a consequence of the reactor accidents in Fukushima Daiichi the radionuclide content in the Mosel river is of increased interest since the water is intensively used by the population. The report covers the measured data on radionuclides (gamma emitting nuclides and strontium-90 activity) in the Mosel water with specific consideration of the nuclear power plant Cattenom and the reactor accidents in Chernobyl and Fukushima Daiichi. The derived theoretical radiation exposure of the public is discussed considering the drinking water path and the spoil ground path. It turns out that the radionuclide content is far below the limit of the radiation protection law and the potential effective doses for the public is negligible compared to the natural radioactivity.

Radiolysis of dilute aqueous solutions of cesium iodide

International Nuclear Information System (INIS)

Gorbovitskaya, T.I.; Galinkin, D.L.; Kants, L.K.; Tiliks, Yu.E.; Kotelkin, I.M.; Luzanova, L.M.

1993-01-01

Study of physical-chemical processes in the NPP containment by severe accident is carried out. Radiolysis of reactor cooling water containing iodine and cesium radionuclides penetrated therein in the course of accident is considered as of such processes. Role of ionizing radiation in the process of formation and release of ecologically hazardous volatile forms of radioiodine from reactor water into environment is studied. Experiments on radiolysis of CsI diluted water solutions are carried out. The data obtained were used for clarification of radiolysis mechanism for iodine-containing water system, enabling forecast of iodine behaviour in the course of the accident. 5 refs., 4 figs., 1 tab

Colloid-Facilitated Transport of Cations in an Unsaturated Fractured Soil Under Transient Conditions

Energy Technology Data Exchange (ETDEWEB)

Ryan, Joseph [Univ. of Colorado, Boulder, CO (United States)

2015-01-31

Rainfall experiments were conducted using intact soil cores and an instrumented soil pedon to examine the effect of physical heterogeneity and rainfall characteristics on the mobilization of colloids, organic matter, cesium, and strontium in a fractured soil. To measure the spatial variability of infiltration of colloids and contaminants, samples were collected through a 19-port grid placed below the soil core in laboratory study and in 27 samplers at multiple depths in the soil pedon in the field study. Cesium and strontium were applied to the soil cores and the soil pedon prior to mobilization experiments. Rainwater solutions of multiple ionic strengths and organic matter concentrations were applied to the soil cores and soil pedon to mobilize in situ colloids, cesium, and strontium. The mobilization of colloids and metal cations occurred through preferential flow paths in the soil cores. Compared to steady rainfall, greater amounts of colloids were mobilized during rainfall interrupted by pauses, which indicates that the supply of colloids to be mobilized was replenished during the pauses. A maximum in the amount of mobilized colloids were mobilized during a rainfall following a pause of 2.5 d. Pauses of shorter or longer duration resulted in less colloid mobilization. Freeze-thaw cycles, a transient condition in winter, enhanced colloid mobilization and colloid-facilitated transport of cesium and strontium in the soil cores. The exchange of solutes between the soil matrix and macropores caused a hysteretic mobilization of colloids, cesium, and strontium during changes in ionic strength. Colloid-facilitated mobilization of cesium and strontium was important at low ionic strength in fractures where slow flow allowed greater exchange of flow between the fractures and the surrounding matrix. The release of cesium and strontium by cation exchange occurred at high ionic strength in fractures where there is a little exchange of pore water with the surrounding matrix

Sorption of strontium and fractal scaling of the heterogeneous media in a candidate VLLW disposal site

International Nuclear Information System (INIS)

Jinsheng Wang; Rui Zuo; Yanguo Teng; Zongjian Sun; Qinhong Hu

2010-01-01

Because of the deposit and accumulation from the debris flow, the heterogeneous geological characteristics is obvious for a candidate very low level waste (VLLW) disposal site, with the grain size ranging from tens of microns to 75 cm. Therefore, it is challenging to directly measure the sorption capacity of the media and the distribution coefficient of some radionuclides, such as strontium. We have studies the correlation of the particle mass content with different grade size and the sorption capacity, which is important in the modeling of radionuclide migration in the heterogeneous disposal site. A total of three deep pits and five shallow trenches were excavated, and 21 solid samples were collected for laboratory experiments. The grade and percentage of the different-sized particles were obtained, and the fractal dimension (D) of the media was calculated from the results of sieved experiments. Steady state sorption time and sorption isotherm of strontium was determined in the heterogeneous media, and sorption and distribution of strontium in the heterogeneous media were evaluated by the relationship between the mass percentage and distribution coefficient (K d ) of the fine-particle media, which was comprised of selected particles with a diameter less than 1 mm, and the correlation on the K d and D was regressed fit. The results indicated that fractal dimension bounded from 2.39 to 2.62 in the media, and K d values of strontium ranged between 119 and 126 in the fine-particle media, and corresponding value was 11 and 43 in the original media. The correlation between K d and D was approximately linear. (author)

Influence of organic components onto state of radioactive strontium in soils

International Nuclear Information System (INIS)

Sokolik, G.A.; Ovsyannikova, S.V.; Cherevko, E.S.; Rubinchik, S.Ya.

2005-01-01

Influence of soil organic components onto radioactive strontium mobility in the soil medium has been analyzed. Distribution of the Sr 90 between various organic fractions of soils having different quantitative and qualitative composition of organic matter has been studied. The samples of mineral and organic soils contaminated by radionuclides of Chernobyl origin were used as the objects of investigation. Fulvic- and humic-acid fractions differed in solubility and mobility in a soil medium have been separated. Differentiation of soils on the Sr 90 mobility in accordance with portion of radionuclide in the immobile organic fractions has been fulfilled. New types of organic and organomineral additives decreased mobility and biological availability of the Sr 90 have been suggested on a base of obtained data. (authors)

The activity of selected gamma radionuclides in the Tatra National Park

Directory of Open Access Journals (Sweden)

Kubica Barbara

2017-01-01

Full Text Available Cesium is naturally occurring active metal, represented by one stable isotope 133Cs, and number of artificial, unstable, isotopes. The most common artificial isotope of cesium is 137Cs, present in the environment of the Tatra Mountains due to nuclear weapon testing in late `50, and nuclear reactor accident in Chernobyl in 1986. However in recent years the growth in biofuels use for power generation can be the next source of 137Cs emission. Burning wood cultivated on grounds contaminated by 137Cs can introduce secondary emission of this isotope to the atmosphere.This paper presents the results of determination of gamma emitting radionuclides artificial 137Cs and natural 40K in soil samples from the Tatra Mountains. Results show some differences in the vertical distribution of examined radionuclides. It was found that the change of activity of 137Cs in the soil samples depends mostly on the soil density and on the concentration of organic material. The state of “zero” 137Cs activity was developed in the form of maps.

Gamma-emitting radionuclides in the bottom sediments of some Finnish lakes

International Nuclear Information System (INIS)

Ilus, E.; Puhakainen, M.; Saxen, R.

1993-10-01

In 1988 and 1990 bottom sediment and surface water samples were taken from eight large lakes representing all five categories of deposition regions contaminated by the chernobyl fallout in Finland. All samples were analysed for gamma-emitting radionuclides. The 137 Cs concentrations in surface waters varied in 1988 from 20 to 310 Bq/m 3 and in 1990 from 78 to 170 Bq/m 3 . The other radionuclides of Chernobyl origin detected in water samples were 106 Ru, 125 Sb and 134 Cs. In the sediments the total amount of 137 Cs per square metre varied in 1988 from 1100 to 160 000 Bq/m 2 and in 1990 from 14 000 to 250 000 Bq/m 2 . The maximum values were in Lake Pyhaejaervi. The maximum concentration of 137 Cs in the surface layer of sediment (0-2cm) was 55 700 Bq/kg dry wt in Lake Naesijaervi. In addition to the cesium isotopes 137 Cs and 134 Cs , Chernobyl derived 106 Ru, 125 Sb amd 144 Ce were detected i the surface layer of sediment in most lakes. 54 Mn, 60 Co and 110m Ag were also detected in some lakes situated in the regions most contaminated by the Chernobyl fallout. In 1988 the maximum concentrations of 137 Cs and 134 Cs were in the uppermost layer of sediment (0-2cm) at almost all stations. In 1990, the cesium peaks already occurred at many stations in the second slice (2-5cm), which may indicate downward diffusion of cesium in sediments or mixing of sediment layers during sampling. The most important factors affecting cesium values in sediments were the local amount of deposition and the type of sediment. This study did not reveal any correletion between the maximum depth of the lake and the area of the lake with the cesium amounts in the sediments. (orig.). (23 refs., 10 figs., 6 tabs.)

Accumulation of strontium-90 and cesium-137 in a number of hydrobionts

Energy Technology Data Exchange (ETDEWEB)

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

1975-01-01

Accumulation factors for Sr-90 and Cs-137 are given for a number of plants and fish taken from fresh-water bodies and from the Black Sea. The best indicators for following radioactive, Sr-90 contamination in fresh-water bodies are: Lemna minor and Subularia aquatica among the plants, while Tinca tinca L, Cyprinus carpio L and Cavassius carassius L are the most suitable among the fish for Sr-90. With respect to cesium-137 the most suitable as indicators are Sparganum affine and Subularia aquatica from the plants and Salmo trutta morpha fario L and Cyprinus carpio L. from the fishes. Among the saltwater hydrobionts as indicators of Sr-90 and Cs-137 water contamination the fish Sarda sarda L takes first place, and the plants Cystoseira barbata and Zostera marina take second place. 1 table, 6 refs. (SJR)

Laboratory studies of radionuclide distributions between selected groundwaters and geologic media. Progress report, October 1, 1979-September 30, 1980

International Nuclear Information System (INIS)

Daniels, W.R.

1981-01-01

During FY-1980, Los Alamos Scientific Laboratory contributions to the Waste/Rock Interactions Technology program were primarily in the areas of migration-rate studies using crushed rock, whole core, and fractured core columns; parametric studies of variables which may influence radionuclide sorption-desorption behavior; and initial studies of actinide chemistry in near-neutral solutions and Eh control. Batch experiments in both air and a controlled atmosphere (nitrogen, less than or equal to 0.2 ppM oxygen, less than or equal to 20 ppM carbon dioxide) for the sorption of several radionuclides on granite and argillite were completed. These data also provided informaton on the effects of other parameters, such as particle size and contact time. All nine elements studied had different sorption ratios for argillite when measured under the controlled atmosphere than when measured in air, except possibly for americium where any effect was smaller than the standard deviations. As expected, strontium, cesium, and barium are least affected by the presence or absence of oxygen and carbon dioxide. Columns of crushed rock and solid and cracked cores were used to study the migration of radionuclides through such materials. In general, sorption ratios measured by batch techniques are 2 to 3 times greater than those for columns; however, a wide variation in behavior was observed, depending upon the element and the mineralogy. Work has begun on a system wherein traced groundwater is circulated through a crushed rock column; this should provide a link between the usual, single-pass, crushed rock columns and the batch experiments. Materials characterization has continued, and techniques for the determination of Fe(II) in silicate rocks and groundwater have been made operational. Work on the fundamental solution chemistry of the actinides has been started

Ion exchange removal of cesium from simulated and actual supernate from Hanford tanks 241-SY-101 and 241-SY-103

International Nuclear Information System (INIS)

Brown, G.N.; Bontha, J.R.; Carlson, C.D.

1995-09-01

Pacific Northwest Laboratory (PNL), in conjunction with the Process Chemistry and Statistics Section of Westinghouse Hanford Company (WHC), conducted this study as part of the Supernatant Treatment Development Task for the Initial Pretreatment Module (IPM) Applied Engineering Project. The study assesses the performance of the CS-100 ion exchange material for removing cesium from simulated and actual alkaline supernate from Hanford tanks 241-SY-101 and 241-SY-103. The objective of these experiments is to compare the cesium ion exchange loading and elution profiles of actual and simulated wastes. Specific experimental objectives include (1) demonstration of decontamination factors (DF) for cesium removal, 92) verification of simulant performance, (3) investigation of waste/exchanger chemistry, and (4) determination of the radionuclide content of the regenerated CS-100 resin prior to disposal

Method to synthesize dense crystallized sodalite pellet for immobilizing halide salt radioactive waste

International Nuclear Information System (INIS)

Koyama, Tadafumi.

1994-01-01

A method is described for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities

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

Sorption of radionuclides on London clay

International Nuclear Information System (INIS)

Berry, J.A.; Bourke, P.J.; Green, A.; Littleboy, A.K.

1989-02-01

Techniques for studying the sorption of radionuclides on London clay have been investigated. This work involved the use of through-diffusion, in-diffusion, high-pressure convection and batch methods to study the sorption of iodide, strontium, caesium and americium. Through-diffusion and high-pressure convection methods were found to be most useful for investigating weakly and moderately sorbing nuclides and give realistic values for sorptivity. The batch technique remains the most practical method of obtaining large quantities of data within a relatively short timescale but gives very high sorptivity values. It is however very useful for intercomparisons of nuclides or geological media. The in-diffusion method requires further refinement for use with strongly sorbing nuclides. Good agreement between through-diffusion and high-pressure convection methods was obtained for the sorptivity of strontium, whilst trends observed for caesium by through-diffusion were confirmed by batch measurements. (author)

Improvements in the biokinetic model for strontium with allowance for age and gender differences in bone mineral metabolism

International Nuclear Information System (INIS)

Shagina, N.B.; Tolstykh, E.I.; Degteva, M.O.

2003-01-01

An age- and gender-dependent biokinetic model for strontium was developed based on the study of a population living along the Techa River exposed to effluents from the Mayak Production Association. To estimate parameters of a new model (Techa biokinetic model, TBM) many data sets have been assembled: our whole-body counter data on long-term retention of 90 Sr in humans, data from studies during the period of global fallout, data resulting from deliberate injections of strontium radionuclides, and non-radiological data regarding bone formation and resorption, mineral content of the body, etc. The model was developed using the basic structure of the ICRP biokinetic model for strontium, but new age- and gender-specific parameters were derived. This paper discusses the approaches applied to develop the new model. (author)

Strontium-90 and cesium-137 in total diet

International Nuclear Information System (INIS)

1979-01-01

Under the commission of Science and Technology Agency, prefectural public health laboratories and institutes and Japan Chemical Analysis Center have collected total diet samples, and determined the contents of 90 Sr and 137 Cs in these samples. Thirty-two prefectural public health laboratories and institutes have collected 2 times a year all the daily regular diet consumed for five persons, namely three meals and other eating between them. These samples were collected at Japan Chemical Analysis Center after carbonization 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 were added were destroyed with hydrochloric acid and nitric acid. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid. The nuclides were dissolved into hydrochloric acid and filtrated, after it was added with nitric acid. The samples solution including radionuclides was extracted with hydrochloric acid and water, and 90 Y which reached radioactive equivallence to 90 Sr, and 137 Cs were chemically separated from it. And the radioactivity was measured with low back ground beta-ray spectrometer. (author)

Direct measurement of strontium-90 and uranium-238 in soils on a real-time basis: 1994 summary report

International Nuclear Information System (INIS)

Schilk, A.J.; Hubbard, C.W.; Knopf, M.A.; Thompson, R.C.

1995-04-01

Traditional methodologies for quantitative characterization of radionuclide-contaminated soils over extended areas are often tedious, costly, and non-representative. A rapid characterization methodology was designed that provides reliable output with spatial resolution on the order of a few meters or less. It incorporates an innovative sensor of square plastic scintillating fibers that has been designed to be placed directly on or above a contaminated soil to detect and quantify high-energy beta particles associated with the decay chains of uranium and/or strontium. Under the direction and auspices of the DOE's Characterization, Monitoring, and Sensor Technology Integrated Program, Pacific Northwest Laboratory (PNL) constructed a high-energy beta scintillation sensor that was optimized for the detection and quantification of uranium and strontium contamination in surface soils (in the presence of potentially interfering natural and anthropogenic radionuclides), demonstrated and evaluated this detector in various field and laboratory scenarios, and provides this document in completion of the aforementioned requirements

Effects of aqueous-soluble organic compounds on the removal of selected radionuclides from high-level waste part I: Distribution of Sr, Cs, and Tc onto 18 absorbers from an irradiated, organic-containing leachate simulant for Hanford Tank 101-SY

International Nuclear Information System (INIS)

Marsh, S.F.; Svitra, Z.V.; Bowen, S.M.

1995-01-01

Many of the radioactive waste storage tanks at U.S. Department of Energy facilities contain organic compounds that have been degraded by radiolysis and chemical reactions. In this investigation, we measured the effect of some aqueous-soluble organic compounds on the sorption of strontium, cesium, and technetium onto 18 absorbers that offer high sorption of strontium from organic-free solutions. For our test solution we used a leachate from a simulated slurry for Hanford Tank 101-SY that initially contained ethylenediaminetetraacetic acid (EDTA) and then was gamma-irradiated to 34 Mrads. We measured distribution coefficients (Kds) for each element/absorber combination for dynamic contact periods of 30 min, 2 h, and 6 h to obtain information about sorption kinetics. To facilitate comparisons, we include Kd values for these same element/absorber combinations from three organic-free simulant solutions. The Kd values for strontium sorption from the simulant that contained the degraded organics usually decreased by large factors, whereas the Kd values for cesium and technetium sorption were relatively unaffected

Certain theoretical and applied aspects of radioecology

International Nuclear Information System (INIS)

Kulikov, N.V.; Tikhomirov, F.A.; Moskovskij Gosudarstvennyj Univ.

1978-01-01

Discussed are various aspects of radioecology, studying mechanisms of migration, distribution and biological effect of radionuclides in various biogeocenoses as well as the problems, connected with the prediction of consequences of biosphere radioactive pollution, ecological rating of the above pollution and reduction of its harmfull effect. The problems of agrochemistry of radioactive fission products, and the problem of studying the effect of increased radiation level on organisms and their communities are considered. Underlined is the importance of the data, accumulated in this or that field, necessary for practical recommendations to reduce the transition of strontium-90 and cesium-137 radionuclides in the ration of cattle and man and rating disposal of radioactive substances in the environment

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

Science.gov (United States)

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

2013-04-01

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

The cycling of transuranic radionuclides in the Columbia River, its estuary and the northeast Pacific Ocean: Final report

International Nuclear Information System (INIS)

Beasley, T.M.

1987-01-01

This review summarizes work during 1985 to 1986 on the radioecology of plutonium, americium and cesium in the Columbia River sediments; radionuclide kinetics of technetium in fish, and radioactivity in the Pacific Ocean

Electrically switched cesium ion exchange. FY 1997 annual report

International Nuclear Information System (INIS)

Lilga, M.A.; Orth, R.J.; Sukamto, J.P.H.

1997-09-01

This paper describes the Electrically Switched Ion Exchange (ESIX) separation technology being developed as an alternative to ion exchange for removing radionuclides from high-level waste. Progress in FY 1997 for specific applications of ESIX is also outlined. The ESIX technology, which combines ion exchange and electrochemistry, is geared toward producing electroactive films that are highly selective, regenerable, and long lasting. During the process, ion uptake and elution can be controlled directly by modulating the potential of an ion exchange film that has been electrochemically deposited onto a high surface area electrode. This method adds little sodium to the waste stream and minimizes the secondary wastes associated with traditional ion exchange techniques. Development of the ESIX process is well underway for cesium removal using ferrocyanides as the electroactive films. Films having selectivity for perrhenate (a pertechnetate surrogate) over nitrate also have been deposited and tested. Based on the ferrocyanide film capacity, stability, rate of uptake, and selectivity shown during performance testing, it appears possible to retain a consistent rate of removal and elute cesium into the same elution solution over several load/unload cycles. In batch experiments, metal hexacyanoferrate films showed high selectivities for cesium in concentrated sodium solutions. Cesium uptake was unaffected by Na/Cs molar ratios of up to 2 x 10 4 , and reached equilibrium within 18 hours. During engineering design tests using 60 pores per inch, high surface area nickel electrodes, nickel ferrocyanide films displayed continued durability. losing less than 20% of their capacity after 1500 load/unload cycles. Bench-scale flow system studies showed no change in capacity or performance of the ESIX films at a flow rate up to 13 BV/h, the maximum flow rate tested, and breakthrough curves further supported once-through waste processing. 9 refs., 24 figs

Research advances in adsorption treatment of cesium and cobalt in waste liquid of nuclear power plants by ion exchange resin

International Nuclear Information System (INIS)

Liu Dan; Wang Xin; Liu Jiean; Zhu Laiye; Chen Bin; Weng Minghui

2014-01-01

Liquid radwaste is unavoidably produced during the operation of nuclear power plants (NPP). With the development of China's nuclear power, much more attention will be paid to the impact of NPP construction on water environment. Radionuclides are the main targets for adsorption treatment of NPP liquid radwaste. Thereinto, cesium and cobalt are typical cationic ones. Currently, ion exchange process is widely used in liquid radwaste treatment system (WLS) of NPP, wherein resin plays a key role. The paper reviewed the research progress on adsorption of cesium and cobalt existed in NPP liquid radwaste using ion exchange resin. (authors)

Process for recovering cesium from pollucite

International Nuclear Information System (INIS)

Mein, P.G.

1985-01-01

Cesium is recovered from a cesium-bearing mineral such as pollucite by extraction with hydrochloric acid to obtain an extract of cesium chloride and other alkali metal and polyvalent metal chlorides. The iron and aluminum chlorides can be precipitated as the hydroxides and separated from the solution of the alkali metal chlorides to which is added potassium permanganate or other water-soluble permanganate to selectively precipitate cesium permanganate. The cesium precipitate is then separated from the residual solution containing the metal chlorides. The cesium permanganate, which is in a very pure form, can be converted to other cesium compounds by reaction with a reducing agent to obtain cesium carbonate and cesium delta manganese dioxide

Enrichment and Determination of radionuclides by ion chromatography

International Nuclear Information System (INIS)

ZAFIMANJATO, J.L.R.

1996-01-01

The fundamentals of Ion Chromatography (IC) and Liquid Scintillation Counting (LSC) are reviewed. Ion Chromatography as separation method for cations is coupled with Liquid Scintillation Counting for the determination of Radionuclides in water samples. An experimental arrangement for investigations on the applicability of guard columns for cationic radionuclide enrichment is shown. The saturation behaviour of single and bivalentic cations and their combination is presented. Our results show that radioactive bivalentic cations like strontium-90 and radium-226 are enriched on a Ion Pac CG 12 Dionex guard column from 100 to 300ml natural water in one single step. The procedure is suitable for their determination in concentrations down to 10 -2 Bq.l -1 [fr

STRONTIUM PRECIPITATION

Science.gov (United States)

McKenzie, T.R.

1960-09-13

A process is given for improving the precipitation of strontium from an aqueous phosphoric-acid-containing solution with nickel or cobalt ferrocyanide by simultaneously precipitating strontium or calcium phosphate. This is accomplished by adding to the ferrocyanide-containing solution calcium or strontium nitrate in a quantity to yield a concentration of from 0.004 to 0.03 and adjusting the pH of the solution to a value of above 8.

Application of TREECS (trademark) to Strontium 90 for Borschi Watershed near Chernobyl, Ukraine

Science.gov (United States)

2012-08-01

near Chernobyl , Ukraine by Mark S. Dortch PURPOSE: The Training Range Environmental Evaluation and Characterization System (TREECS™) (http... Chernobyl Nuclear Power Plant, Ukraine. At this site, TREECS™ was used as a modeling tool to predict the fate of radionuclides. This application also...Web site noted above. Borschi watershed is located 3 km south of the Chernobyl Nuclear Power Plant (Figure 1). Radio- strontium-90, 90Sr, which is a

Fluxes of radionuclides in the agricultural production after a nuclear accident: countermeasures and decontamination techniques

International Nuclear Information System (INIS)

Jouve, A.

1997-01-01

This thesis deals with the radiological consequences of a nuclear accident through the radioactive contamination of the food chain and the subsequent countermeasures for decreasing the fluxes of radionuclides and decontaminating agricultural lands. After a brief summary of the radioprotection ground and context in case of a nuclear accident, this work surveys existing data on the fluxes of radionuclides in soils and from soil to plants. The research work focuses on both the prediction of the fluxes of radionuclides and possible countermeasures: the measurement of the bioavailability of radionuclides in the soil solution, its use in a mathematical expression to quantify the soil-to-plant transfer of caesium and strontium, and the perspectives of an innovative technique of soil decontamination. The obtained results show that based on 4 coefficients, it is possible to predict crop contamination within a 3 % confidence interval: the fluid solid distribution coefficient of radionuclides kd, the amount of chemical analogues of caesium and strontium, i.e. potassium and calcium, respectively, soil pH and a constant characterising the plant species that is concerned. However, it generally appears from soil to plant transfer studies that the reduction of the fluxes of radionuclides is not a promising way of radiological exposure mitigation after a nuclear accident. The work performed shows that it is more efficient to tackle the source of the contamination, i.e. decontaminate the soil. The proposed technique of soil scraping using a turf harvester appears to be the most advantageous among the tested options, for the decontamination of peat-bog meadows. (author)

Radionuclides distribution in internal organs of wild animals in alienation zone of Chernobyl NPP

International Nuclear Information System (INIS)

Gorbatova, T.A.; Kudryashov, V.P.; Mironov, V.P.

2002-01-01

Activities of caesium 137, strontium 90, plutonium isotopes and americium 241 are experimentally defined in the internal organs of bearer and wolf alienation zone of Chernobyl NPP. Radionuclides distribution in the internal organs of wild animals is defined by destruction of nuclear fuel particles

Ground depositions and air concentrations of Chernobyl fallout radionuclides at Munich-Neuherberg

Energy Technology Data Exchange (ETDEWEB)

Hoetzl, H.; Rosner, G.; Winkler, R.

1987-01-01

Southern Bavaria has received a comparatively high deposition of fallout radionuclides from the reactor accident at Chernobyl. As a result, in addition to the measurement of numerous gamma emitting nuclides and of strontium isotopes, the determination of several actinides, including isotopes of uranium, neptunium, plutonium and curium was possible. The observed radionuclide composition of the fallout and the time course of ground deposition and air concentration at the site of the Gesellschaft fuer Strahlen- und Umweltforschung (GSF) at Neuherberg, 10 km north of Munich, are reported and discussed.

Ground depositions and air concentrations of Chernobyl fallout radionuclides at Munich-Neuherberg

International Nuclear Information System (INIS)

Hoetzl, H.; Rosner, G.; Winkler, R.

1987-01-01

Southern Bavaria has received a comparatively high deposition of fallout radionuclides from the reactor accident at Chernobyl. As a result, in addition to the measurement of numerous gamma emitting nuclides and of strontium isotopes, the determination of several actinides, including isotopes of uranium, neptunium, plutonium and curium was possible. The observed radionuclide composition of the fallout and the time course of ground deposition and air concentration at the site of the Gesellschaft fuer Strahlen- und Umweltforschung (GSF) at Neuherberg, 10 km north of Munich, are reported and discussed. (orig.)

Radiochemical analysis of fallout in Norway

Energy Technology Data Exchange (ETDEWEB)

Bergh, H; Finstad, G; Lund, L; Michelsen, O; Ottar, B

1957-01-01

Data are tabulated on the concentration of radioactive iodine, strontium, and cesium in samples of milk collected in Norway in September 1957. Data are included from experiments on the purification of water contaminated with radioactive strontium and cesium.

Cesium residue leachate migration in the tailings management area of a mine site : predicted vs. actual

Energy Technology Data Exchange (ETDEWEB)

Solylo, P.; Ramsey, D. [Wardrop Engineering, Winnipeg, MB (Canada). Mining and Minerals Section

2009-07-01

This paper reported on a study at a cesium products facility (CPF) that manufactures a non-toxic cesium-formate drilling fluid. The facility operates adjacent to a pollucite/tantalum/spodumene mine. The CPF was developed as a closed system, with the residue tailings slurry from the CPF process discharged to doublelined containment cells. Groundwater monitoring has shown that leachate has affected near-surface porewater quality within the tailings management area (TMA). Elevated concentrations of calcium, sulphate, strontium, cesium, and rubidium were used to identify the leachate. Porewater at the base of the tailings and in the overburden beneath the tailings has not been affected. A geochemical investigation was initiated to determine how the leachate behaves in the groundwater/tailings porewater system. Over the past 7 years of residue placement in the TMA, the footprint of the residue placement area has changed, making the comparison of predicted versus actual rate of leachate migration very subjective and difficult to quantify. Based solely on the analytical data, the source of the leachate is unknown, either from the original residue pile or the 2007 residue placement area. For purposes of long term residue management, an investigation of the geochemical behaviour of residue leachate in the groundwater/tailings system of the TMA is currently underway. 5 refs., 1 tab., 2 figs.

Atmospheric radionuclides from the Fukushima Dai-ichi nuclear reactor accident observed in Vietnam

International Nuclear Information System (INIS)

Long, N.Q.; Giap, T.V.; Phan, N.T.; Truong, Y.; Binh, N.T; Sieu, L.N.; Hien, P.D.

2012-01-01

Radionuclides from the reactor accident at the Fukushima Dai-ichi Nuclear Power Plant were observed in the surface air at stations in Hanoi, Dalat and Ho Chi Minh City (HCMC) in Vietnam, about 4500 km southwest of Japan, during the period from March 27 to April 22, 2011. The maximum activity concentrations in the air measured at those three sites were 193, 33 and 37 μBq m -3 for 131 I, 134 Cs and 137 Cs, respectively. Peaks of radionuclide concentrations in the air corresponded to arrival of the air mass from Fukushima to Vietnam after traveling for 8 days over the Pacific Ocean. Cesium-134 was detected with the 134 Cs/ 137 Cs activity ratio of about 0.85 in line with observations made elsewhere. The 131 I/ 137 Cs activity ratio was observed to decrease exponentially with time as expected from radioactive decay. The ratio at Dalat, where is 1500 m high, was higher than those at Hanoi and HCMC in low lands, indicating the relative enrichment of the iodine in comparison to cesium at high altitudes. The time-integrated surface air concentrations of the Fukushima-derived radionuclides in the Southeast Asia showed exponential decrease with distance from Fukushima. (author)

FARMLAND: model for transfer of radionuclides through terrestrial foodchains

International Nuclear Information System (INIS)

Brown, John

1995-01-01

Models to stimulate the transfer of radionuclides through terrestrial foodchains have been developed at the Board and regularly used over the last 20 years. The foodchain model is named FARMLAND (Food Activity from Radionuclide Movement on LAND) and it contains a suite of submodels, each of which simulates radionuclide transfer through a different part of the foodchain. These models can be combined in various orders so that they can be used for different situations of radiological interest. The main foods considered are: green vegetables; grain products; root vegetables; fruit; milk, meat and offal from cattle; meat and offal from sheep. A large variety of elements can be considered, although the degree of complexity with which some are modelled is greater than that for others; isotopes of caesium, strontium and iodine are treated in greatest detail. (Author)

40 CFR 141.26 - Monitoring frequency and compliance requirements for radionuclides in community water systems.

Science.gov (United States)

2010-07-01

... identified in the finished water. (iii) Annual monitoring for strontium-90 and tritium shall be conducted by... requirements for radionuclides in community water systems. 141.26 Section 141.26 Protection of Environment ENVIRONMENTAL PROTECTION AGENCY (CONTINUED) WATER PROGRAMS (CONTINUED) NATIONAL PRIMARY DRINKING WATER...

Cesium-137 as a tracer of soil turbation: example of the taiga landscapes of the Western Siberia, Russia

Energy Technology Data Exchange (ETDEWEB)

Usacheva, Anna A.; Semenkov, Ivan N. [The Organization of Russian Academy of Sciences Institute of geology of ore deposits, petrography, mineralogy and geochemistry Russian Academy of Sciences, 119017, Moscow (Russian Federation)

2014-07-01

Cesium-137 is artificial radionuclide with 30.17 years half-life. However, this element can be found anywhere due to global atmospheric fallout. Its background storage is detected in landscapes: water, bottom sediments, plants and soils. Almost no one has studied the concentration of {sup 137}Cs in the landscapes of the North, because of its negligible storage. Cesium-137 is slightly mobile in the soils of the North. The cryogenic and other material movement is a typical feature of soils of the North. However, the dating of the soil turbations less than 100 years of age, using existing methods, is possible via long-term stationary observations. To determine the age of soil turbations quicker, one can use slightly mobile artificial radionuclides with medium or long half-life. Cesium-137 satisfies all the criteria. The aim of the work is to estimate suitable of cesium-137 as geo-tracer of soil turbation. According to our evaluation, the activity of the buried layers is less than 10 Bq*kg{sup -1} at the current {sup 137}Cs contamination of surface organic horizons (60-90 Bq*kg{sup -1}). A research has been conducted to study distribution of cesium-137 in the north and middle taiga landscapes of Western Siberia (Russia). Field research was carried out in 2012 in two study areas. The first study area 'Purpe' is located in the middle part of the Pur river basin, near Gubkinsky town (Yamalo-Nenets Autonomous Okrug). The second study area 'Noyabrsk' is located in the Ob and the Pur river watersheds, near Noyabrsk-city (Yamalo-Nenets Autonomous Okrug). Moss-grass-underwood layer (n=13) contains 22±20% of {sup 137}Cs total storage in the landscapes of oligo-trophic bogs with cryohistosols and pine forests on cryopodzols. The main reservoir of cesium-137 is soils (n=24) that accumulate 78±20% of its total landscape storage. The upper 10-cm soil layer contains 90% of {sup 137}Cs soil storage. Cesium-137 activity declines from shrubs and polytric layers

Radiochemical analysis of fallout in Norway

Energy Technology Data Exchange (ETDEWEB)

Bergh, H; Finstad, G; Lund, L; Michelsen, O; Ottar, B

1957-01-01

Data are tabulated on the concentration of radioactive iodine, strontium, and cesium in samples of milk, radioactive strontium and cesium in samples of rain water, and radiocesium in preparations of tea and coffee collected in Norway during July and August 1957.

Removal of strontium and transuranics from Hanford tank waste via addition of metal cations and chemical oxidant: FY 1995 test results

International Nuclear Information System (INIS)

Orth, R.J.; Zacher, A.H.; Schmidt, A.J.; Elmore, M.R.; Elliott, K.R.; Neuenschwander, G.G.; Gano, S.R.

1995-09-01

Chelating organics and some of their degradation products in the Hanford tank waste, such as EDTA, HEDTA, and NTA act to solubilize strontium and transuranics (TRU) in the tank waste supernatant. Displacement of strontium and TRU will facilitate the removal of these radionuclides via precipitation/filtration, ion exchange, or solvent extraction so that low-level waste feed specifications can be met. Pacific Northwest Laboratory has investigated two methods for releasing organic-complexed strontium and TRU components to allow for effective pretreatment of tank waste supernatant: metal cation addition (to promote displacement and flocculation) and chemical oxidant (pennanganate) addition (to promote chelator destruction/defunctionalization and possibly flocculation). These methods, which can be conducted at near-ambient. temperatures and pressures, could be deployed as intank processes

Location analysis and strontium-90 concentrations in deer antlers on the Hanford Site

International Nuclear Information System (INIS)

Tiller, B.L.; Eberhardt, L.E.; Poston, T.M.

1995-05-01

The primary objective of this study was to examine the levels of strontium-90 ( 90 Sr) in deer antlers collected from near previously active reactor sites and distant from the reactor sites along that portion of the Columbia River which borders the Hanford Site. A second objective was to analyze the movements and home-ranges of mule deer residing within these areas and determine to what extent this information contributes to the observed 90 Sr concentrations. 90 Sr is a long-lived radionuclide (29.1 year half life) produced by fission in irradiated fuel in plutonium production reactors on the Hanford Site. It is also a major component of atmospheric fallout from weapons testing. Concentrations of radionuclides found in the developed environment onsite do not pose a health concern to humans or various wildlife routinely monitored. However, elevated levels of radionuclides in found biota may indicate routes of exposure requiring attention

Separation processes for the pretreatment of high-level nuclear wastes at the Savannah River site - 59291

International Nuclear Information System (INIS)

Hobbs, David; Peters, Thomas; Taylor-Pashow, Kathryn; Fondeur, Fernando; Nash, Charles; Fink, Samuel; Herman, David; Marra, Jim

2012-01-01

Document available in abstract form only. Full text of publication follows: Separation methods for the pretreatment of the high-level nuclear wastes (HLW) at the Savannah River Site (SRS) include the Caustic Side Solvent Extraction (CSSX) process for cesium and adsorption/ion exchange for the removal of cesium, strontium and alpha-emitting actinides. The CSSX process uses a calixarene extractant in combination with phase modifiers in a hydrocarbon diluent. Monosodium titanate (MST), a hydrous metal oxide, is the baseline material for the removal of strontium and alpha-emitting radionuclides (principally Pu-238, Pu-239, Pu-240 and Np-237). Two pretreatment facilities, the Modular Caustic Side Solvent Extraction Unit (MCU) and the Actinide Removal Process (ARP) facility began radioactive operations at SRS in 2008. Together these facilities can treat approximately 4 million liters of waste per year. The same separation processes are also planned for the much larger Salt Waste Processing Facility (SWPF). The SWPF, which has a design throughput of about 27 million liters per year, is under construction and scheduled to begin radioactive operations in 2014. Current R and D activities for the CSSX process are focused on implementing a new solvent system and stripping flowsheet that offers enhanced extraction and stripping of cesium. This next generation solvent system features a different calixarene extractant, uses caustic instead of nitric acid

Radiological statuses of Bulgarian black see shore

International Nuclear Information System (INIS)

Totzeva, R.; Badulin, V.; Tenev, J.; Kotova, R.; Ivanova, G.

2013-01-01

Full text: Introduction: In this paper own results of the radiation monitoring of the Black Sea coast - from village Shabla to village Resovo are presented. The study was carried out under a project funded by the BS ERA NET in FP7 of the European Commission, together with the project partners. Materials and Methods: Sampling was conducted in June 2012. 4 seawater samples (including depth of Varna Bay), 12 sand samples, 2 algae samples, 5 bottom sediments samples, 3 surface river water samples, 1 sea fish sample and 1 medical mud sample were examined. The samples were analyzed by gamma spectrometer for determination of the content technogenic and natural radionuclides and by radiochemical methods for defining the specific concentration of strontium- 90. A comparison between the specific activities of radionuclides in sea and river water, in the sands in sea bottom sediments in points and fractions, as well as in green and red algae. Results: The content of Cesium- 137 and Strontium -90 in the tested sea water ranged from 0.0041 (0.0007) to 0,0110 (0,0027) Bq/l and 0.00362 (0.00047) to 0,00409 (0,00049) Bq/l. The concentration of Cesium-137 in river water is ≤ 0,0012 Bq/l. The content of Potassium-40 in the sands is over a wide range from 4.9 (0.7) to 1152 (47) Bq/kg, a testament to their different origins. There is a difference in the contents of the radio-cesium into the upper and the lower fraction of the deep bottom sediment, and the various sampling points. It is clearly distinguished a selectivity of radio-cesium accumulation in red algae and they can be used for bio-indicator. Conclusion: The assessment of the radiological status of the Bulgarian Black Sea coast shows that with the exception of the beach in Vromos all investigated areas are safe from a radiological point of view. All studied coastal marine water as radiological indicators meet the quality standards set by Ordinance H-4/2012

Monitored Natural Attenuation of Inorganic Contaminants in Ground Water Volume 3 Assessment for Radionuclides IncludingTritium, Radon, Strontium, Technetium, Uranium, Iodine, Radium, Thorium, Cesium, and Plutonium-Americium

Science.gov (United States)

The current document represents the third volume of a set of three volumes that address the technical basis and requirements for assessing the potential applicability of MNA as part of a ground-water remedy for plumes with nonradionuclide and/or radionuclide inorganic contamina...

Determination of strontium-90 from direct separation of yttrium-90 by solid phase extraction using DGA Resin for seawater monitoring.

Science.gov (United States)

Tazoe, Hirofumi; Obata, Hajime; Yamagata, Takeyasu; Karube, Zin'ichi; Nagai, Hisao; Yamada, Masatoshi

2016-05-15